ML20023E120
| ML20023E120 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/25/1983 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20023E118 | List: |
| References | |
| PROC-830425-01, NUDOCS 8306140398 | |
| Download: ML20023E120 (145) | |
Text
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- ' ' EP Index l
.\ 94ERGENCY PLAN PFOCErJJRES INDEX Paqa 1
~
Rev. 30 *
- PEACH BOTltN UNITS 2 AND 3 ,,
4/25/83 *. Review Rev. Revision I Number Title Date* No. Date EP-101 Classification of Emergencies 04/13/83 7 04/13/83 EP-102 Unusual Event Resoonse 04/13/83 7 04/13/83 - EP-103 Alert Resoonse 04/13/83 8 04/13/83 EP-104 Site Emergency Respcnse 04/13/83 8 04/13/83 EP-105 General Emergency Resocnse 04/13/83 8 04/13/83 EP-110 Personnel Assembly and Accountability 04/14/82 0 04/14/89 EP-201 Technical Succort Center (TSC) Activation 04/25/83 5 04/25/83
- EP-202 Ooerations Suoport Center (OSC) Activation 04/25/83 4 04/25/83
- EP-203 Emergency Operations Pacility (IDF) Activation 04/25/83 5 04/25/83
- EP-205 Radiaticn Protection Wam k Activation 04/25/83 4 04/25/R3
- EP-205A Chemistrv 9amoling and Analysis Grouc 05/25/82 4 05/?5/82 EP-205A Ooeration of Post Accident
.1 Samoling Station 04/25/83 2 04/25/83
- EP-205A Obtaining Drywell Gas Ramoles
.2 from Containment Atnoschere Dilution l Cabinets 05/26/82 0 05/26/97 Eo-205A Retrieving and Changing 9 ample
.3 Filters and Cartridges frcm the Drvwell Radiation Monitor During Emergencies 04/25/83 1 04/25/83
- EP-205A Obtaining Drywell Gas Samples
.4 from the Drywell Radiation Monitor Sampling Station n5/25/82 0 05/9.5/32 EP-205A Obtaining Reactor Water Samoles
.5 from Sample Sinks Following Accident Ccoditiens 05/25/82 0 05/25/82 EP-205A Obtaining Canal Discharge Water ~
.6 Samoles Following Radioactive Liquid
{ Releases After Accident Conditions 05/25/82 0 05/25/82 8306140398 830606 PDR ADDCK 05000277 ' - - F PDR
o . - 4 ED Index FMERGENCY PLAN PIOCEDURES INDEX Page 2 Rev. 30
- PFACH 90't'IO4 UNITS 2 AND 3 4/25/83
- Review Rev. Revision ..,
Number Title Date No. Date EP-20,5A Obtaining the Iodine and
.7 Particulate Samples from the Main Stack and Roof Vents Following _
Accident Conditions 04/25/83 1 04/25/83
- EP-205A Obtaining Liquid Radwaste Samples
.8 from Radwaste Sample Sink Following Accident Conditions 05/25/92 0 05/?9/R2 EP-205A Obtaining Samoles from Condensate
.9 Sample Sink Following Accident Conditicris 05/25/R2 0 05/25/R2 EP-205A Obtaining Off-Gas Samoles from
.10 the Off-<ias Hydrogen Analyzer Following Accident Conditions 05/?5/R2 0 05/25/R2 ,
ED-205A Sample Preparation and Chemical j .11 Analysis of Highly Radioactive Liquid Sam.les o 05/25/82 0 05/25/R2 ED-205A Samole Preparation and Analysis
' I .12 of Highly Radioactive Particulate Filters and Iodine Cartridges 04/25/83 1 04/25/83
- EP-205A Sample preoaration and Analysis of
.13 Highly Radioactive Gas Samples 05/25/82 0 05/25/92 EP-205B Radiation Survey Groups 04/25/83 4 04/25/83
- EP-205C Personnel Dosimetry Bioassay and Respiratory Protection Group 04/08/82 2 04/08/82 EP-206 Fire and Damage Team Ac'tivation 06/04/82 5 06/04/82 EP-206A Fire Fighting Group 06/04/82 3 06/04/82 l
l EP-2069 Emergency Reoair Group 05/23/82 2 05/23/82 i ED-207 Personnel Safety Team Activation 04/25/83 5 04/?5/83
- EP-207A Search and Rescue 04/13/83 3 04/13/83 i EP-207B Personnel Accountability 05/11/82 3 05/11/92 .
EP-207C First Aid 04/25/83 3 04/25/R3 * { EP-207D Evacuation Assembly Group 3 04/25/R3 * - 04/25/83 L EP-207E Vehicle and Evacuee rmtrol Procedure 04/08/82 0 04/08/82
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o a .. EP Index D4ERGENCY PLAN PK)CEEXJRES INDEX Page 3 Rev. 30
- PEACH BOTIO4 UNI'TS 2 AND 3 4/25/83 *
(' Mumber Title Review Date Rev. Revision No. Date EP-207F Vehicle Decontamination procedure 04/1.4/82 0 04/14/82 EP-200 Security Team 04/01/R1 0 04/01/91 EP-209 Telephone List For Emergency Use 12/23/82 6 12/23/R2 EP-209 Imnediate Notification Call List Appendix A 04/11/83 7 04/11/83 EP-209 0ELETED DELETED Appendix B EP-209 Peach Bottom Station Supervision Aapendix C 04/11/83 8 04/11/93 EP-209 On Site Emergency Team Leaders Anpendix D-1 04/11/83 5 04/11/83 EP-209 Radiaticn Protection Wam Appendix D-2 04/11/83 8 04/11/R3 ( EP-209 Fire and Damage Team Acpendix D-3 04/ll/R3 7 04/11/R3 EP-209 Personnel Safety Team Accendix D-4 04/11/83 8 04/11/83 EP-209 Security Team Apoendix r>-5 04/11/R3 4 04/11/R3 EP-209 Re-Entry and Recoverv 'Ibam Apoendix D-6 . 04/11/R3 3 04/11/R3 EP-209 'Ibchnical Suprt Center Group ADpendix D-7 04/11/83 7 04/11/83 En-209 Cor15 crate Emergency Wam Leaders and Appendix E Support Personnel 04/11/83 R 04/11/83 EP-209 U. S. Government Agencies Appendix F 04/11/83 4 04/11/R3 EP-209 Emergency Management Agencies Acpendix G 04/11/83 3 04/11/83 - EP-209 Ccxnpany Consultants Aopendix H 5 04/11/83 ( 04/11/83 EP-209 Field Support Dersonnel Acpendix I-l 04/11/83 10 04/11/R3
En Index ' DE!lRGENCY PLAN P10CEDURES INDEX ! age 4 Rev. 30
- PUCH BOTKN IMITS 2 ann 3 4/25/83
- Review Rev. Revision .
Mumber Title Date No. Date EP-209 Chemistry & Health Physics Contractor Appendix I-2 Call List 04/11/83 7 04/11/R3 - EP-209 Nearby Public and Industrial Users Appendix J Of Downstream Waters 04/11/83 4 04/11/83 ; EP-209 Miscellaneous Appendix K 04/11/83 5 04/11/83 EP-209 Ixx:al Pero Phones Appendix L 04/11/83 2 04/11/83 EP-209 DELETED DELETEn Acpendix M
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EP-209 Medical Support Groups Apoendix N 04/11/83 5 04/11/R3 EP-209 Staffing Augmentation - 60 Minute Appendix P Call Procedure 04/11/83 5 04/11/83 ( EP-210 Dose Assessment Team 04/25/83 0 04/25/G3
- ED-301 Ooerating the Evacuation Alarm and Pond Page System 12/23/82 1 12/23/R2 EP-303 Partial Plant Evacuation 12/22/81 1 12/22/R1 EP-304 DELETED l
EP-305 Site Evacuation 09/07/82 4 09/07/82
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- EP-306 Evacuaticn of the Information Center 05/25/82 2 05/25/82
! EP-307 Reception and Orientation of Supoort Personnel 04/12/R2 0 04/12/87 ED-311 Handling Personnel with 9erious l Injuries, Radioactive Contamination Exoosure, or Excessive Radiation Exposure 52nergency nirector Functions 04/08/82 3 04/08/R2 EP-312 Radioactive Liquid Release (Emergency Director Functions) 04/13/R3 1 04/13/83 Eo-313 Control of Thyroid 91ocking (KI)
; Tablets 04/08/82 0 04/08/82 EP-316 Cumulative Poculation Dose Calculations 05/06/82 2 05/06/R2
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EP Index - DERGENCY PLAN PIOCF3XIRES INDEX Page 5 Rev. ~40
- PEACH ROTIOM UNITS 2 AND 3 4/25/83 *
. Review Rev. Revision .
Mumber Title Date No. Date EP-317 Direct Reccanendations to' County Emergency Management and . Civil Defense Agencies 04/14/82 0 04/1.4/82 EP-318 Liquid Release Dose Calculation Method for Intake Water at newnstream Facilities 04/13/83 1 04/13/83 EP-319 Liauid Release nose Calculation Method for Fish 04/13/83 1 03/13/83 EP-320 Procedure for Leaking Chlorine 03/12/82 1 03/12/82 EP-325 Use of the Containment Radiation Monitor to Estimate . Release Source Term 06/09/82 0 06/09/82 EP-401 Entry for Emergency Repair and Operations , 04/13/83 4 04/13/83 EP-500 Review and Revision of Emergency ( Plan (FSAR Appendix 0) 04/01/81 0 04/01/31 l om
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/ ' CONTROLLE3 APPROVED COPY- ( EP-201 Page 1 of 20, Rev. 5
< VOID PREV 10sS IsSJE GG:tth DISTRIBUTION:
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SS - SSV.. ( ~7' Control Rs.. _ P. SI[ADELPHIA ELECTRIC CMPANY APR 2 51983 ' Station Super. P PACH BOTITM UNITS 2 AND 3 Office EMERGEN N PLAN IMPLEMENI'ING PROCEDURE EP-201 'IECWICAL SUPPORT CENIER (T3C) ACTIVATION
~ PURPOSE
'Ib describe the instructions and actions required for the activati'on, manning, and operation of the Technical Succort 1
Center (TSC) . 'The 'ISC is located on the third floor of l Unit 1.
References:
Peach Bottom Atomic Power Station Emergency Plan NIRm 0654 Criteria for Preparation and Evaluation of Radiological Mnergency Resoonse Plans and preoaredness - in Support of Nuclear Dower plants. NURm 0696 Functional Criteria for Emergency Response Facilities [) S.19.1 Technical Support Center t. Mnergency Operations Facility Vent System APP m DICES EP-201-1 Equitznent Activation of Technical Rupport Center - and Emergency Ooerations Facility EP-201-2 Actions of First HP to Arrive at Technical Supcort Center and Emergency Operations Facility . EP-201-3 Actions of First Test Engineer to Arrive at
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Technical Suoport Center and Emergency Operations Facility EP-201-4 Technical Aupport Center Organization and Manning EP-201-5 mechnical Support Center Facility Layout EP-201-6 Plant Status Board
, EP-201-7 Event Chronology Status Board .
l EP-201-8 Offsite Cnmnunications Status Board ( EP-201-9 Staff Assignment Status Board EP-201-10 Procedure for Operation of 'TSC 'iv Monitors l
EP-201 Page 2 of 20; R'ev. 5 4 EP-201-11 Site Radiological Status Board ( , EP-201-12 E 'nelechone Checkoff List - l EP-201-13 TSC Habitability Guidelines AC' PION LEVEL: , Activate the T3C when an event has been classified as an alert. Site Energency or, General anergency in accordance with ; EP-101, Classification of Emergencies, or at the discretion of the anergency Director. . >g
=>. '
t PRFCATTPIONS: i
- l. Verify E habitability prior to activation.
,I Ensu're 'ISC remains habitable while the TSC is activated.- * '
Refer to Appendix Eo-201--13. , , e ,
- 2. Maintain accountability of personnel and staff -
reporting to the 'ISC throughout the incident.
- 3. Ensure 'ISC ventilation system is operating in the I recirculation /HEPA mode and that air samples are taken periodically to measure potential airborne contamination, l Also insure routine monitoring of Ping 2A moni"3r,.
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(
- 4. Ensure that pertinent actions and notifications C4
.are logged. An official log is located in the 'nschnical o Supoort Center and indicated as such.
PROCEr1TRE: , ~ IMEDIATE ACTION 9: , 1
. 1.0 Emergency Director shall:
1.1 Assign one of the on-shift I&C technicians to. cerform the steps outlined in Section 2.0 of these Immediate Actions. 1.2 As' sign an individual the duties of Comnunicator and direct the individual to perform the steps outlined in Section13.0 of these Innediate Actions. 1.3 Direct the first MP staff member that arrives at the T9C to. perform the steps outlined in Section 4.0 of these Innediate Actions. . 1.4 Direct the first Test Engineer staff member that arrives at the 'I9C to < perform the steps outlined __ in section 5.0 of these Innediate Actions. ^
- 1. 5 Obtain continuous status updates on plant condi.tions
. - EP-201 Page 3 of 20, Rev. 5
*h from the Control Room and maintain a log.of.significant f.. events and actions. ;- 1 l
'1he log shall include at least the following:
- a. Date and Time
- b. - significant Event
- c. Significant Actions
- 1. 6 Provide briefings on the emergency and pertinent plant conditions to appropriate 'ISC staff
'upon their arrival.
l.7 Inform the Control Room that the TSC is operational upon completion of steps outlined in Section 2.0 and 3.0 of these Inmediate Actions. Announce activation of the TSC when all Team Leaders are present or in charge.
- 1. 8 Ensure that the manning and operation of the 'tSC is in
, accordance with the Fbilow-up Actions of this procedure. - 2.0 On-Shif t I&C Technician shall: 2.1 Go to the guardhouse, pick up the emergency key ring, and proceed to Unit 1 using one of the dedicated I&C vehicles parked in the Company vehicle Area. Kevs for {- these vehicles are in quardhouse. 2.2 Use attached Appendix EP-201-1 to turn on lighting, HVAC, radiation monitors, and
- t. closed circuit W monitors in both the EOF and -
'tSC.
2.3 Inform the Emergency Director when 'rSC/FDF
- equipnent set-up is ocmolete and of any -
equiment problems. 2.4 Remain at the 'ISC as the Data Display Operator. Man the 'IV camera station in the 'ISC and perform any needed request frm the Faergency , Director. Use Appendix EP-201-10 for W nonitor operation instructions. t 3.0 Emergency Director Cmmunicator shall: 3.1 Using Appendix EP-201-12 ('ISC Telerhone Checkoff List), verify ammunications capability +
. , exists from the Technical Support Center. -
3.2 Inform the Emergency Director when the comunications capabilities have been verified -
- ( or of any discrepancies.
3.3 Man comnunications lines as directed by the T
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l " EP-201 Pag 2 4 of 20, Rev. 5 Emergency Director and maintain a Comnunications (' Ing containing information received from and ~ sent to Emergency Centers and offsite agencies.
'the log shall include as a minimum the following information:
- a. Date and Time (use 24 hour time notation) -- -
- b. Messages received or sent
- c. Name of person information was received or sent to
- d. Name and initials of person making entries 3.4 Inform the Emergency Director promptly of all information received from site groups and offsite agencies.
4.0 First MP Staff Member shall: 4.1 perform the steos outlined on Appendix EP-201-2 g and report canpletion to the Dnergency Director. 5.0 First Test Engineer shall: 5.1 Perform the steps outlined on Acpendix EP-201-3 and, upon completion, inform the Emergency Director i that TE,n distribution has begun. (, 6.0 Personnel Safety Team Leader shall: 6.1 Provide necessary personnel and on-site radiation status. 6.2 Assign assistants as necessary to man the site Radiological Status Board. 6.3 Coordinate with the MP&C OSC for on-site radiation problems which develop. FUCUM-UP ACTIONS: 1.0 Emergency Director shall: 1.1 Us'e attached Appendix En-201-4 and Appendix EP-201-5 to ensure that the 'rSC is adequately staffed. 1.2 Assign three individuals (test engineers or technical assistants) as Status Board
. Recorders: .
- a. cne individual for the Plant Status Board (see Apoendix EP-201-7) . ._
(. b. one individual for the Event Chronology Status Board (see Appendix EP-201-7) .
s .
. I EP-201
- . Page 5 of 20, Rev. 5
- c. one individual for the Offsite Comunications -
Status Board (see Appendix EP-201-8) and Staff Assignment Status Board (see Appendix EP-201-9) . , I 1.3 Direct the Status Board Recorders to -' Perform the steps outlined in Section 2.0
- of these FoHow-Up Actions.
1.4 Assign an individual (test engineer or
" technical assistant) to man the dedicated comunication lines to the Control Room and Operations Support Center and direct the individual to perform the steps outlined in Section ~ 3.0 of these Ponow-up Actions.
- 1. 5 If necessary dispatch an individual (test engineer or technical assistant) to the Control Room to tran_ smit requested Control Boom parameters and information to the 'tSC. -
- 1. 6 If necessary assign an individual (clerical staff) as a Telephone Operator to man the telechone ,
console in the FDP.and direct the individual to perform the steps outlined in section 3.0 , of these follow-up actions. ( 1.7 Ensure that two individuals (instrument / control technician) are assigned as Data Disolay Ooerators to man the 'IV camera station in the 'ISC. -
- 1. 8 Brief the 'ISC staff periodically (normally every 30 minutes) on the status of the emergency and pertinent plant .
conditicns. 1.9 Rely on the Personnel Safety Team Leader for status as to contaminated or injured personnel, site or local evacuations, and on-site radiological problem areas. 2.0 Status Board Recorders shall: 2.1 Set up the assigned status board given to you. Format and content of the status board are
- given in the following appendices: .
- a. Appendix EP-201-6, Plant Status Board
. b. Appendix EP-201-7, Event Chronology Status Board _ l c. Appendix EP-201-8, Offsite Cmmunications Status Board ' { d. Accendix EP-201-9, Staff Assignment Status Board , e. Appendix EP-201-ll, Site Radiological Status Board l
- . _ _ _ _ . _ . ~ . . _ . . - . . _ _ . _ _ _ _ _ , . _ . _ _ . _ _ . _ . _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ . _ - _ _ . - _ _ - _ _ . . _ _
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- F.P-201 -
Page 6 of 20, Rev. 5.
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(- 2.2 Contact the following individuals for the various status board information. .
- a. Data Disolay Operators for plant status information
- b. Comunicator to Control n:xan for event chronology information
- c. Emergency Director or control Room for offsite comunication information.
- d. Emergency Director for staff assignment information.
- e. Aux. OSC for site radiological status.
l
- f. nesignated site evacuation assembly area coordinator for evacuation information. .
2.3 Post appropriste information on assigned status baor and maintain a log record of all status board entries. Transmit plant status information and event chronology information to appropriate ( Status 1bstd Recorders at the EDF. 2.4 Review and uodate the status board at least every 15 minutes and as changes in plant conditions - or information warrant. 2.5 Inform the Emergency Director as significant changes in status board information are noted. l 3.0 Comunicators shall: . 3.1 Man assigned comnunication lines.
' 3.2 Maintain a Comunications Log containing l
information received from and sent to other f- emergency response facilities and other support organizations.
'the log shall include as a minimum the following information:
- a. Date and time (use military time notification)
- b. IncomingA)utgoing
- c. Messages received or sent -
( d. Name of person information was received frczn or sent to
- e. Name and initials of person making entries
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*h b 3.3 Inform the Emergency Director promotly of all information received from or sent to members of the emergency resoonse organization or support organizations.
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EP-201 l Pag 2 8 of 20, R'ev. 5 APPD1 DIX EP-201-l EQUIPMENP ACTIVATION OF TSC AND EOF (.
- 1. Enter Emergency Operations Facility using key B9178.
- 2. .Go to the lighting panels located just outside the north door. On Panel P-23 turn on Breakers 2, 4, and
- 6. On Panel P-43 turn on Breaker 5. - -
- 3. Go to Technical Support Center door on third floor and enter the room using key PG-6.
- 4. Go to lighting Panel P-47 located behind the status boards next to the cooying machine and turn on all breakers labeled "'mc lichting."
- 5. Go to the Ventilation Panel at the northwest -
corner of the Technical Support Center. Wrn on the ventilation system using the crocedure posted there.
- 6. W rn on the Particulate-Iodine-Noble Gas Monitor (DING) located at the northeast corner of the Technical support Center using the procedure on the PING.
f 7. Wrn on the 4 W monitors and the video recorder
\ located in center of the 'I4chnical Support Center using the procedure near the monitors. Notify the finit 2 and 3 Control Rocxn operators to energize the cameras and remove the lens covers.
- 8. Go to the 1st floor, and turn on the PING inside the entrance.
- 9. Wrn on the 2 W monitors located in the Emergency l Operations Facility using the procedure near the monitors.
- 10. Return to the %chnical Support Center, third floor, and man the TV camera station as directed by the anergency Director. Inform the Emergency l Director that you have energized the 'Ibchnical Sucport Center and the Emergency Operations Facility.
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EP-2dl Page 9 of 20, R'ev. 5
- APPENDIX EP-201-2 ACTIONS T FIRST HP TO ARRIVE AT TSC AND FDP
- 1. Go to the first floor by the Unit one entrance and inventory and prepare the Energency Equipnent l Locker and anergency Kits.
- 2. Preoare the emergency 'ILn's in the green -
Radiation Mnergency Equipnent boxes for use. These boxes are located in the hallway leading to the Alternate Chem. Lab. 7he 'ILD's should be ihventoried and readied for use by those .:50 enter the Unit One anergency Centers. C. e e I 'I . l l l (
. ... .__._..__.._x_. .
[~ . ?-7.01 Page 10 of 20, Rev. 5
/
APPDOIX EP-201-3 ACTIONS OF FIRST 'IEST ENGINEER 'IO. ARRIVE AT 'TT AND EDF (
- 1. Go to the first floor by Unit one entrance and get emergency 'ILD's frca the Radiation Equipnent lockers. If portable frisker is not already at Unit One entrance, get it from the Emergency Operations Facility and set it up at --
the desk just inside the glass door.
- 2. Go to the first floor entrace of Unit One.
Dist'ribute UID to all personnel who possess emergency resconse roles. Icq 4LO Numbers versus names. This function shall be assumed by a quard as soon as he is available. - C. l r I l l _. . l l l l l
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APPENDIX EP-201-4 . TEUIINICAL SUPPORT CENTER ORGANIZATION AND MANNING I SITE EMERGENCY ____________________________________ EMERGENCY COORDINATOR DIRECTOR
- 8 RADIATION
-Communicator (s)
PROT TEAM TECIINICAL
} LEADER ENGINEER -Status Board Keepers l
8 s
-Data Display Operators l EMERGENCY j FIRE AND ANALYSIS GROUP DAMAGE TEAM -Telephone Operator (Swbd.)
LEADER
-Secretary l'
l- - PERSONNEL SAFETY /IN-PLANT . i RAD. TEAM LDR. EVAC. ASSEMBLY AREA GROUP OPERATIONS ENGINEER (CONTROL ROOM) . F o W \ H O m l M O w 5L v>S
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- Appendix FP-201-6 p3xpg pty;;7 gg.;g _ g377 no, O
RADIOIMICAL PARAtETE?.S 4 .c
*GtERJ} LOGICAL ?;RM*.ETE?.S - tic.. ?.I .C'iOR ?Ar'A.%~TERS - timo g
- 1. poact *g ' 1. Main Stack cps nr/hr 1. Avg. Wind spded oph *
- 2. Level inches .2. U/2 Vent Stack cpm mr/hr 2. Avg. Wind Directi n *(from) fi. ?ressure PSIG 3. U/.3 Vent Stack cpm nr/hr 3. Afg.Radiationrdg mr/hr
- 4. D/W Rad Monitor R/hr 4. Avg. Ambier.t Temp. *F j -3 5.
, S. Refuel Flr Exh ar/hr Precipitation g TAINyENT PA.WiETERS - tima 6. Air Eject Off Gas ar/hr 6. Skability Class .. Iores Temp. *F 7. Radwaste Monitor cpm 7. Avg. Wind Speed (320')
.:. Drywell Te..p. 'F
- 8. Main Stack Flow CFM 8. Avg. Wind Speed (75') .
.3. Dryvell Press. psig 9. U/2 Vent Stack Plcw CFM
.; . Torts Level 10. U/3 Vent Stack Plcw CFM
'5. Containnent 102 %I!2 REACTIVITY CONTROL - time LEVEL CG T33L - ti:a bNTAI:C/.EST CONTROL - time
-[of rods not inserted past 05 l SYSTEM INJi UNAVAIL/ REASON 'RHR , TORUS TORUS D/W S/D UNAVAIL/
o IF. W. A l COOL SPRAY S? RAY COOL REASON [3314 INJ UNAVAIL/REASOI4 B A I A -
- . - C l B
' O 3 CRD A l C 8 B D i s ,
- 3. EIC Tank Level % _
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-- [Ri'3SURE CONTROL - time g;;IC e i Dypass Valves Open COND A I HPSW LON UNAVAIL/ REASON
- 1. , ,
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- 2. A BC D E FG II JlK L C B j ".ij.VS C
C.S. A I liOSED
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PO*ER SUP? LIES - time D : ! _ . . L?CI A i , ISOLATIONS ISOLATED /EXC2PTIONS S.W. :E ISUPPLYIN's UNAVAIL/ REASON B GRP I: {{{ IITE ~ C
- GRP 11 bES UTI* D GRP III E-1 igpgg g cap yy ,
E-2 B l GRP V, hn am C , ei
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COND TRANS 8 3BGTE ! CN UNAVAIL/ REASON U" P C.E R SUPPLY l RdFUEL TRANS E NS A' o 3"S 32o.s.143o.s. Diesel t UNAVAIt' SHLC B N q: -- C O W2 TRAIN A E-3 B E
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FP-201 Page 14 of 20, Rev. 5 Ob APPENDIX EP-201-7 EVFRr 6 STAM BOAE . (. . Tre swm svan I NO. e G e e h 9 ese (, . t
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. - EP-201 Page 15 of 20, Rev. 5
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( APPENDIX EP-201-8 OW SITE COeMJNICATIONS STATUS BOARD e OFFSITE TIME CIMOTICATIONS RESPWSE/OOM4ENT 4 e e. 6 e e Sun 9
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- (~ _ EP-201 rage 16 of 20, Rev. 5 APPENDIX EP-201-9 S'DEF ASSIGNENT SMIf18 BOARD .
TI'IIF, NAMR IDCATitM Shif t Superintendent Shift Supervisor Emergency Director
'rechnical Engineer Personnel Safety Team Leader Fire / Damage 'Peam Leader Site Emergency Coordinator Health Physics / Chemistry Coordinator Radiaticri Protection Team TAader (V
Dose Assessment Group Leader Field Survey Group Leader FDP Liaison Procedure 9upport Coordinator Planning Coordinator Mechanical Engineer Liaison Electrical Engineer Liaison Emergency Support Officer j
~
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EP-201 Page 17 of 20, Rbv. 5 APPENDIX EP-201-10 PRJCEDURE FOR OPERATION OF TSC/EDF 'b7 MrNI'IOR9 ,- i 1.O PURPOSE: We following procedure defines the required steps for the operation of the 'Dechnical Support Center - and Emergency Ooerations Facility W monitoring of the Main Control Room.
2.0 SCOPE
W is procedure is to be followed by all personnel who use the video-monitoring system in the Control Roo *1. 3.0 Fc:;ruFNCES: Ooerating instructions, controls for motorized zoom lenses. (Vicon Industries, Inc.) X85-780 - 6283-E-114-5-1
4.0 RESPON9IRILITY
%e person (s) operating this equipment shall be
( responsible for safe ooeration. 5.0 Pim%vISI'TS: Person (s) operating this equipment should have a knowledge of its operation in addition to - reviewing the operating instructions, and should be very familiar with the layout of instruments in the control room.
6.0 P90CEDURE
' 6.1 In the Emergency Ooerations Facility (2nd floor of Unit 1) turn en both controllers, as they act as master controllers for the controllers on the third floor.
6.2 In the Technical support Center (3rd floor of Unit 1), turn on the four W monitors, and their associated controllers. 6.3 Push 'close' button on iris a few short
- times to ensure procer lighting. _
6.4 Joystick operates camera movement. NOIE: Pan and tilt speed are a function of how far the joystick is moved away from the center ' rest' position.
~
EP-201 Page 18 of 20, Rbv. 5 ( 6.5 Motor speed is determined by knob (on/off) . NOE: 'Ihe motor speed not on the lens controller will have to be optomized for each individual camera (for focus and zoom it will be approximately mid- - - pot). 'Tb get iris control, the speed l pot must be fully clockwise. NrRE 1:
- Fuse for all cameras is in the 'IW Danel in the control room, inside the right door on the left side.
Nt7m 2: Control %om W camera switches are located at the base of each W camera. Switch is labeled "ACPower Feed On/Off". 4 b o e W
I EP-201 Page 19 of 20, Rev. 5 APPENDIX EP-201-12 , .
'ISC PHONE C.O.L. *-
Test Ring Down Phones: Operaticns OSC Aux. OSC (Wall) IOEXE 7th Floor -~ Control Room Data Taker (Wall) Control Room (Table) Emergency Operations Facility Izad Dispatcher Control Room (Wall) NRC Red Phone White - Bureau of Rad. Protection Blue - PA, E, and 5 Risk Counties Test nial Phones for Dial 'Ibne: 4625 Canputer Wrminal 4626 Emergency Analvsis %rt Wall Phone 4627 Fire / Damage Wam TAader 4628 Emerg Analysis TeaWTelecooier k' 4629 Technical Engineer 4 6'10 Manry Analysis Team 4635 Emerg Director . 4631 Emerg Director"s Table 4632 Personnel Safety Team Leader - _ 4633 TSC Status Board j 4634 Data nisolay Operators t 4321 Data nisolay Operators 4636 NRC Office l l 4692 Technical Engineer t I ( 4689 Plant Status Board l M7IE: Inform the Personnel Safety Team TAader to test the appropriate evacuation assembiv ring down phone when evacuation assembly area __ ( (FUB or North Sub Station) is manned. i' l .
n
.c m E'-201-13 TSC Hchitability G Jelines .
s a . I f
;RM 16 Ping 2A -
Gama 120 mR/hr . Low Alarm 120 mR/hr 24 hr. stay time prior to. 24 hour stay time prior to reaching quarterly reaching quarterly limit of 3000 mR. limit of 3000 mR High Alarm 275 mR/hr 8 hr. stay time prior to reaching quarterly limit of 3000 mR. Emergency 200 mR/hr off-scale. Consider initiation bf - Director should consider evacuation and request periodic surveys the Radiation Protection Team Leader to initiate j surveys and utilize Ping 2A to monitor integrated dose. , Low Alarm 50% of high alarm (2X10-4 uCi/cc).24 hr sta{g,,
~
Xe N/A { High Alarm 10% of maximum value (5X10-4 uCi/cc). Emergenc " Director should consider evacuation . 8hrskSEe 133 and request Radiation Protection Team Leader : to initiate surveys and utilize Ping 2A to monitor integrated dose. Note: MPC occupational exposure 1 X 10-5 uCi/cc Beta N/A Low Alarm 50% of high alarm (5X10-9 uCg/cc) 24 t r stay time i Particulate High Alarm 10% of maximum value (lX10 - uCi/cc) 8 hr stay i time Emergency Director should consider evacuation' : and request Radiation Protection Team Leader to i initiate surveys and utilize Ping 2A to monitor integrated dose. Note: MPC occupational exposure 3X10-10 uCi/cc I 131 N/A Low Alarm 50s of high alarm (2X10-7 uCi/cc) 24 h rstayt)me High Alarm 10% of maximum value (4X10-7 uCi/cc) 8 hr stay i time Emergency Director should consider evacuation and request Radiation Protection Team Leader to s initiate surveys and util'ize Ping 2A to monitor . om integrated dose. Note: MPC occupational mu7 exposure 9X10-9 uCi/cc.
. 0 l
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., Ep-?O?
- Dane 1 of 9, Rev. 4 CONTROLLED APPROVED COTY- GGttth VOID PE VIOUS ICSliE DI3 DI2. TID 3: /s$. -
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APR 2 51983 m g TH[LA957.D5*I A ELECTRIC COMPANY ( sc, . scy Cn:c r:1 ; ..
>FACII BO'I'1TN INI'TS 2 ann 3 NC P W I E N . PROCEDURR St t Len E.:p r.
Cfit:se EU-202 - Operations Copport Centers (N) V:tivation PURPOSE
'Ib define the actions required hv the Operations Support Center Coordinators for activating, manning and inanaging the Ooerations Cuonort Centers (09C) . 'The Auxiliarv Onerations 9upoort Center is located on El.116', finit ? Turbine Ruilding.
'the OoerationG Succort Center is located on the 135' El.
between finits 2 F. 3. REFT'RENrr3
- 1. Peach Rottom Atomic Dower Station Emergency Plan
- 2. Nureg 0654 Criteria for preoaration and Evaluation of Radiological Emergency Response Plans and Preoaredness in Support of Nuclear Power Plants.
I 3. Nureg 0696 Functional Criteria'for Emergency Response Facilities.
- 4. 10 CFR 20 APPENDIX EP-202-1 Ooerator OSr Dhone C.n.L.
l EP-202-2 Aux. 09C Phone C.O.L. EP-202-3 Goerator OAC Assignment Status Board EP-202-4 Operator OSC ' Plant Atatus Board En-202-5 Aux. Occ Assignment 9tatus Roard EP-202-6 09C's Tiabitability Guidelines AC' PION LEVEL Activate the Ooerations 9upport Centers when an event has been classified as an Alert, Site Emergency or General Emergency in accordance with EP 101, Classification of Dnergencies. PRFCAI1TIONS
- 1. Maintain an official log of pertinent actions in each of the designated Operations Support Centers. An official log is in each of the OSCs and they are indicated as such.
, FP-702 Page 2 of 9, Rev. A
- 2. Verifv habitability of Operations Suncort Centers in
( l' acx:ordance with Anoendix EP-202-6. Initiate air
. [ samoling umn activation of facilities.
1 'Iko Goerations 9unnott Centers exist. %e 9hif t Operators ( OSC is on 175', turbina buildino and the Aux. 09r is on 116', turbina hiilding. %is orevents personnel and consnunications problems between shift onerators and HP&C personnel. Each OcC has identical comminications caoabilities.
- 4. Dersonnel shall loa in and out of the Operations Support Centers in order to maintain personnel accountability.
- 5. %e Ooeraticnn Support Centers shall contain controlled copies of the emergency procedures. No extra radiation survey or emergency equirmnent need be at the center.
ImEnIA'm 4"vtom 1.0 Interim Emergencv Director shall: , 1.1 At the Alert, Site Emergency, or General Emergency level (whichever occurs first), assign a comoetent coerator as the Operator OSC (elev. 135' turbine building) coordinator. If available, an operator with supervisorv exoerience (9SV or shift Supt. tyoe) should be used or called in oer Annendix P of EP-209 call list to man this cosition. ( 2.0 Radiation protection Nam Leader shall: l '2.1 *nsure that the Aux. OAC (elev.116' turbine building) is manned and supervised with acapetent Health Physics personnel after the occurrance of an Alert, site Emergency, or General Emergency g (whichever occurs first) . Assignment of an Aux. OSC coordinator is essential to proceriv handle all MP related emergency activities. 3.0 Operations Support Center Coordinators or designees shall: 3.1 ' Assign an individual the duties of Operations Support Center Comnunicator and Status Board Keeper. Ensure that a log is available for the connunicator's use. i 3.2 Direct the Operations Rupport Center Carnunicator and Status Board Keeper to verify onerability of the connunication systens as outlined in the attached Appendices. (See Appendix EP-202-2 for Aux. OSC and I Apoendix EP-202-1 for the Shift 08C). l 3.3 Notify the Control Room when their respective Operations Support l center is manned and that ocununications are satisfactory or unsatisfactory. j 3.4 Procure equitznent and supplies necessary to assist in mitigating the emergency.
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o . f ED-202 Page 3 of 9., Rev. 4
, 1.5 ' N.;sion an individual to verify habitability of their respective
.( Ooerations Support Center (as required) adfiering to the criteria desiqnated in sten 2 of the Drecautions above. Recott the results of this verification to the 9hift 9uperintendent.
4.fi Operations Sooport Center Communicator and 9tatus Board Xcepers shan: 4.1 v erify comunication canabilities exist in their respective 4 Operations 9annort Centers bv completing the attached chone C.O.L. I appendices. Reoort results to OAC Coordinator. 4.2 Man the status board costed hv the OSC Coordinator to ensure personnel and clant status is maintained in each OSC. (See Aonendices for status hoards) . 4.3 Toq all certinent actions in the designated log book to maintain a formal record of all events nettinent to the 09C. Refer to OSC Coordinator for guidance on what to log. WKLOW-Up AhTIONS 1.0 Ocerations Suoport Center Coordinators or designees shall: 1.1 Remain in contact with the Control Room or the Technical Support Center in order to orovide assistance as needed by fornulation of Emergency Teams. { 1.2 Direct eersonnel entering and leaving their respective operations suonort Center to log in using the official log or the status boards. 1.3 Coordinate activities of their resoective OSC. 'The operator OSC should coordinate with the Control Roan and designated maintenance eersonnel to ensure local permits are promptly completed to allow g reoair work if necessary. 'The Aux. OSC should coordinate with the
'rSC, Control Doom, and all emergency team personnel to ensure proper HP suncort for all activities in the plant. In these cases, the Hp will serve as the ,RWP.
1.4 Upon leaving their resoective Operations Support Center for any reason, delegate his duties to the remaining senior operator or technician.
- 1. 5 Maintain working knowledae of radiation exposure each member of their l respective OSC is receiving in order to maintain ATARA concepts during the emergency.
2.0 Operations Support Center personnel shall: 2.1 Goon entering and leaving their respective ooerations support center l log in and out in the designated log or on the status board. 2.2 Ensure proper self-monitoring of their own pocket dosimeters when k performinq tasks during the emergency. l l l
l M'-20'
< Paga 4 of 9, Rev. 4
- APDFNDIX EP-202-1 ODERAWR ORC PtOF. P.O.7,,
g , Tent Ring Down Phones Tnitials Control 9 con l Aux. OSC Test Oial Phones for Dial ibne 4369 4690 Discrepancies: (
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- EP-202 Page 5 of 9, Rev. 4 APPFNnIX FP-202-2 NTX OcC pHONR C.O.L.
' Pest Rin<7 neun Phones Tnitials
-Pechnical Suncort center Operator OSC
%st Dial Phones for nial %ne 4262 4263 4691 4495 Discrepancies:
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. ^Paqh 6
- 9a Rev. 4 t
APPINDIX F.P-202-3 SHIFT OPERATIrNS STIPPORT C@mm AS9ICN97P S'190Y1S ROARD Time Job Description Operators 9ent Maintenance Called Fst. Re ( (
O i EP-202
, Page 7 of 4, Rev. 4 4
ADP91 DIX EP-202-4 ODERNTTR CSC PLANT STAWI9 ROARD INIT TIME: 13 Kit Bus 1: 2: HDCT:
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- R: C: RCIC:
Recirc A: 3: 912: 973: 4 KV Bus E1: E2: E"4: F4:- Diesel . A: R: C: D: RHR A: R: C: D: TiP9W A: R: C: D: Core Soray A: R: C: 0: ESW A: R: ECW: I CRD A: B: SBTI A: B: SBGT A SBGT Filter Fans A: B: C: B SRGT Filter l I I l k a w--- -t--e7 y a -w -- p-- ewyp-.e
l i I 4 F:P-202
. Dagt 8 of 9,- Rev. 4
' ~ APPENDIX FP-202-3 * { NIX OSC Assignment (;tatus Roard Time .Tob Descriotion ITD's cient 1Y'A Problems F.st. Return Time f i i E k k
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. . EP-203 Cui ROLLD AF?T.0'.'D CM- Paige 1 cf 19, Rev. 5
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PRI]ADELPHIA ELEXMIC COMPANY APR } 51983 3 Contrcl R.. PUCH BOTICM INI'rS 2 AND 3 - St; ticn Opar.EMFK dan PTAN IMPLD9WfING PROCN1URR t. Office EP-203 FNEIGNCY OPERATICNS FI42kLIW (10F) ACTIW. TION
, > i
, s 4
i 'Ib describe actions required for th[ activation, nanning,4 'and operation of the Dnergency Operations Facility (EDF) . 'Ihe EOF is located on the second floor of Unit One. t ' V REFER 33CES . s A
- 1. Peach Eottom Atomic Power Station Emergency Plan
- 2. NURFG 0654 Criteria for Preparation and Evaluation of 11 Radiological Dnergency Response Plans and Preparedness in Stgport of Nuclear Power Plants.
- 3. NUREG 0696 Functional Criteria for Emergency Response 1 . +
Facilities , (- APPENDICFS ' EP-203-1 Emergency Ooerations Facility Organizati and Manning . EP-203-2' Dnergency Operations Facility Layout EP-203'-3 Plant Status Board l EP-203-4 Event Chronology Status Board EP-203-5 Staff- Arsigrunent Status Board ' EP-203-6 Headquarters Support Requests Status Board EP-203-7 Offsite Comnunications Status Board s EP-203-8 Field Mcnitoring Data Status Board EP-203-9 Dose Assessment Data Status Board EP-203-10 Procedure for Operation of Emergency Operations Facility TV monitors EP-203-ll Activation Procedure for PING in. Emergency Operations Facility l EP-203-12 EDF Habitability Guidelines ACTION LEVEL Activate t$e EDF when an event has been classified as a Site Dnergency or General Dnergency in accordance with EP-101, Classification of Emergencies, or at the discretion of the site l Dnergency Cootdinator. -, i l PRRCAUTIONS , l ..
- 1. Verify EDF habitability prior to activation.
Ensure the EDF remains habitable while the g EOP is activated. Refer to EP-203-12.
EP-203 y Page 2 of 1:9, Rev. 'i . ( 2.. Maintain accounting of personnel reporting to the BOF P throughout the incident. . > w 1, .
- 3. Ensure EOF ventilation system is operating and in the l recirculation /HEPA mode that air samples are periodically taken to measure potential airborne contamination. Also Ping 2A on first floor is routinely monitored.
- 4. Ensure that pertinent actions and notifications are logged.
PROCEDURE 1.0 Designated Senior Engineer acting as the Interim Site Dnergency Coordinator shall perform the following actions until releived by the site Emergency Coordinator or designated alternate. 1.1 Assign at least one individual (Test Engineer, Technical Assistant, or Junior Technical Assistant) the duties of comunicator and direct the individual to perform the steps outlined in section 2.0 of these imediate actions. i 1.2 Obtain tmy radios for the radiation survey groups. Radios are available in Ccunur.ications Equignent Room. 1.3 Obtain ccntinuous status updates on plant conditions from the Control Roca or '14chnical Support Center and maintain a log of significant events and actions. 1.4 Ensure that the manning and operation of the anergency Operaticms Facility is in accordance with the follow-up actions of this procedure. * , 1.5 Provide briefings on the emergency and pertinent plant conditicns to the Site Emergency Coordinator and appropriate EDF staff upon their, arrival. 1.6 Inform the Cmtrol Room and Technical Support Cr: e; when the l Bnergency coerations Facility has been activated. l l (All Team Leaders in charge or present) 2.0 Site Emergency Coordinator Coununicator shall: 2.1 verify comunications capability by ocupleting the telephone C.O.L. for FDP (Appendix EP-203-12) . 2.2 Inform the Site anergency Coordinator or Interim Site anergency coordinator when ocmnunication capabilities have been verified or of any discrepencies. (' 2.3 Man comunicaticms lines as assigned and maintain a ocanunications log containing information received from and sent to other facilities and organizaticns. -
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EP-203 Paga 3 of 19, Rev. 5 I EDIIDl4-UP ACTIONS 1.0 Site Emergency coordinator or Interim site Emergency Coordinator shall: 1.1 Use attached Acpendix EP-203-1 and Aapendix EP-203-2 to ensure that personnel required to man the EDF are in place. 1.2 Assign an individual (test engineer or technical assistant) as a Status Board Recorder for the Plant Status Board (see Appendix EP-203-3), and the Event Chronology Status Board (see Appendix 5:P-203-5). Direct the individual to perform the steps outlined in Section 4.0 of these Follow-Up Actions. 1.3 Assign an individual (test engineer or technical assistant) as a Status Board Recorder for the Headquarters Support Requests Status Board (see Appendix EP-203-6) and Offsite Ccamunications Status Board (see Appendix EP-203-7) and direct the individual to perform the steps outlined in Secticm 4.0 of these Follow-up Actions. 1.4 Assign an individual (instrtunent and control technician) as a Data Display Operator to man the W camera station in the E0P. '1his data display ooerator should refer to Appendix EDP-203-10 for W monitor operation. 1.5 If necessary, assign an individual (clerical staff) as a runner to route information in the EDP and other appropriate facilities. 1.6 If necessary, assign an irxlividual (clerical staff) to perform, any typing and clerical work. 1.7 If necessary, assign two individuals (clerical staff) as telephone operators to man ocreunications equignent in the EOF _ _ . Coumunications 5;'quipment Room.
- 1. 8 Assign at least one individual (test engineer) as a
- conmunicator for the Site Emergency Coordinator to perform the j acticris specified in Section 5.0 of these Follow-Up Actions.
l 1.9 Upon conpletion of pertinent steps outlined in these follow-up actions, inform the Control Roczn and the Technical Support Center that the Emergency Operaticns Facility is operational and manned. 1.10 Brief the IDF staff periodicially on the status of the emergency and pertinent plant conditions. 1.11 Direct the Ccanunicator for the site anergency coordinator to maintain a log of significant events and actions. t' 'Mn above log shall include as a minimum the following information: l
EP-203 Page 4 of 19, Rev. 5
- a. Date and Time *
( . b. Significant Event Significant Actions Taken
- c. ;
1.12 nirect the Comunicator for the site Emergency Coordinator to Transnit all status board information to the Headquarters Emergency Support Center Status Board Recorder. 2.0 Radiaticm Protection % am Leader.shall: 2.1 Assign an individual (HP Technician) as a Field Survey Group Radio Comunicator to maintain radio contact with Field Survey . Teams. t 2.2 Assign an individual (HP technician) as a Status Board Recorder for the Field Monitoring Data Status Board (see Appendix EP-203-8) and direct the individual to perform the - steos outlined in Section 4.0 of these Ponow-up Actions. 2.3 Assign an individual (HP technician) as Telephone Coununicator to man appropriate communication lines assigned to the Radiation Protection Team Leader and perform the steps outlined in Section 5.0 , of these 7bilow-up Actions. p 3.0 Dose Assessment Group Leader shall: ( 3.1 Assign two individuals to perform dose projection calculations at the EDP. 3.2 Assign an individual (HP technician) as a Status Board Recorder for the Dose Assessment Data Status Board (see Appendix EP-203-9) and direct the individual to perform the steps listed in Section 4.0 of these folla m actions.
- 4.0 Status Board Recorders shall
4.1 Set uo the assigned status board. Format and content of the status boards are given in the following appendices:
- a. Appendix EP-203-3, Plant Status Board
- b. Appendix EP-203-4, Event Chronology Status Board
- c. Appendix EP-203-5, Staff Assignment Status Board
- d. Appendix EP-203-6, Headquarters Support Requests Status Board
, e. Appendix EP-203-7, Offsite Comunications Status Board l f. Appendix EP-203-8, Field Monitoring Data Status Board 9 Appendix EP-203-9, Dose Assessment Data Status Board 4.2 Centact the following indiviatala for the various status board information. ( a. Tic Plant Status Board Recorder for plant status information. .
- h. -- _ _- ---,-- - = ----.:i. =.
EP-203 Page 5 of 19, Rev. 5
- b. TSC Event Chronology Status Board Recorder for event chronology information. ,
- c. Site Emergency coordinator for staff assignement information and headquarters suppport requests.
- d. Emergency Director, site Emergency Coordinator, or control Room for offsite ocumunication information.
- e. Field Survey Group Radio Cmmunicator for field monitoring data.
- f. Dose Assessment Group Leader for dose assessement data.
4.3 Pust appropriate inform tion on assigned status board and maintain a log of all status board entries. 4.4 Review and update the status board every 15 minutes and as changes in plant conditions or information warrant. 4.5 Inform the appropriate coordinator, team leader or group leader of significant changes in status board information. 5.0 Conmunicators shall: . (, 5.1 Man communicaticn lines assigned. 5.2 Maintain a Conmunications Log containing information received from and sent to other emergency response facilities and other support organizations. I
- a. Data and time (use 24 hour time notation)
- b. Messages received or sent
- c. Name of person information was received from or sent to
- d. Initials of person making entries 5.3 Inform the appropriate coordinator, team leader or group leader pronptly of information received from or sent to menbers of the emergency response organization or suoport organizations.
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. 'F 7. Radwaste Monitor c14a 7. Apg.WindSpeed(320')
. Drywell Te:ap. 'F 8. ~ Main Stack Flow CFM S. Avg. Wind Speed (75')
- 2. Drywell Press. psig 9. U/2 Vent Stack Plcw CFM l
- 4. Torus I4 vel 10. U/3 Vent Stack Plcw CFM
- 5. Containment 402 %H2
- -tEACTIVITY CONTROL - tine LEVEL CONTR~)L - ti: .3 CON'"AINMENT CONTROL - time
- 1. vof rods not inserted past 06 l SYSTEM INJe UNAVAIL/AIASON l k-iR TORUS TO3dS D/W S/3 UNAVAIL/
2* * * '
~
[smCI INJ UNAVAIL/ REASON B . I A I : C i B lI I CRD A C l
- 3. ShIf Tank Level % B . D HPCI I
?ROSSURE CONTROL - time RCIC . I
# Bypass Valves Open COND A I l 'HPSW ON UNAVAIL/ REASON
- 1. ,;
B l A
- 2. ISRVS A SIC D ELFG H' JlK L C B 1
. l Q?EN ---- C.S. A e C i
LCIOSED 1 B i D l C POL ER SUPPLIES - time D 1 ' LPCI A I ,- ISOLATIOt4S ISOLATED / EXCEPTIONS - 52URCE SUPPLYIN3 UNAVAIL/ REASON B GRP Ii 20FFSITZ C - GRP II 3OFFSITE D GRP III yy I-l HPSW A l GRP IV j4 E-2 B l GRP V' ',o E-3 C i o E-4 o I COND TRANS SBGTS I ON UNAVAIL/ REASON g POWER SUPPLY l REFUEL TRANS IANS AI ' SUS 42o.s. 43o.s. Diesel 8 UNAVAII" - B' F SBIf E-1 Ci < E E-2 FRAIN A vi E-3 , B E-4 ...
EP-203
- Page 9 of b , Rev. 5 APPENDIX FP-203-4
{ WENT Om0NOWGY S'm'ITE BOARD TIME NO. WENT me,- -,w
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FP-203 Page 10 of 19, Rev. 5 ( APPENDIX EP-203-5 STAFF ASSIONENT STA'IUS ROA_RD Trnr. nue unrrm Shift Superintendent Shift Supervisor Emergency Director Technical Engineer Fire / Damage Team Ldr. Persmnel Safety 'Ibam Ldr. Site Emerg. Coord. Health Physics / Chem. Coord. Radiation Protection Team Idr. Dose Assessment Group Leader ( Field Survey Group Leader . EOF Liaison Procedure Support Coordinator Planning Coordinator Mech. Engr. Liaison Elec. Engr. Liaison , Emergency Support Officer l 1 I
EP-203 Page 11 of 19, Rev. 5 0 APPENDIX EP-203-6 HF)OQUAR'rERS SrTPPOR'P RFQUES'15 STA'IUS boa @D (, TIME SURMITIED 'IO I'IFM RESPCNSE STA'IUS (
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. Page 12 cf t
( APPENDIX EP-203-7 OETSI'IE (DMMICATIONS S'IMtJS BOARD OrrdI'IE TIME COPMNICATIONS , R5lSPW3E/OCDNPNP f e e i t 4
Page 13 of 19,, e ADPFNnIX EP-203-8 FIFLD KNI'IORING DATA STA'1U9 BOMD ( e n I l l l ( l r t
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EP-203 Page 14 of 19, Rev. 5 APPFNDIX EP-203-10 ( P90CFEURE FYR OPERATICN OF TSC/EOP W KNI'JORS
1.0 PURPOSE
2e following procedure defines the required steps for the operation of the 'thchnical succort Center and Emergency Operations Facility W mcnitoring of the Main Control Room.
2.0 ST)PE
i ! Wis pro dure is to be followed by an personnel who use the video-monitoring system in the Control Rocm.
3.0 RFEERBCE
l Operating instructions, controls for motorized zoom lenses. (vicon Industries, Inc.) X85-780 6280-E-114-5-1
4.0 RESPONSIBILITY
%e person (s) operating this equi 1: ment shall be resconsible for safe operation.
5.0 vmw3ISI'IES
( Perscn(s) operating this equignent should have a knowledge of its oper-ation in addition to reviewing the operating instructions, and should be very familiar with the layout of instrtunents in the Control Room. 6.0 ri u.am u s : 6.1 On the second floor of the Unit 1 building, turn on both controners, as they act as master controllers for the controllers on the third floor. 6.2 on the third floor of the Unit 1 building, turn on the four W Monitors and their associated controners. 6.3 Push 'close' button on iris a few short times to ensure proper lighting. 6.4 Joystick operates camera movement. N0'IE: Pan and tilt speed are a function of how far the jogstick is moved away from the center " rest" position. 6.5 Motor speed is determined by knob (CN/PF) . NO'!E: Se motor speed not on the lens controner will have to be optomized for each individual camera (for focus and zoom it will be approximately mid-pot) . 'Ib get iris control the speed pot must be fully clockwise. N01E l 'Puse for an cameras is in the 'llti panel in the control room , inside the right door on the l eft side. 9 _--y-,.m , .,g y-.- ,- r-w-+yy-mv.-- .w.ywwe,-meyc w, .e..-=,w.--e.,r+wy g-
EP-203 Page 15 of 19, Rev. 5 l I @'fE 2: Centrol room W camera switches are located at the base i of each W camera. Switch is labeled "AC Power Feed ON/DFF. I l e o l ,, O e
EP-203 Page 16 of 19, Rev. 5 APPENDIX EP-203-ll ( ACPIVATION OF THE EBERLINE PING-2A IN M EMFKENCY OPERATIONS FACILITY
- 1. OPEN F10NT PANEL BY 'IURNING BLACK PNOBS CXXNTERCLOCNISE AND POLLING OUT.
- 2. 'IURN "KEYROARD" KEY ON (CIDCWISE) .
- 3. ACTIVA'IE PUMP BY PUSHING M FXXJDWING SEQUENCE CN M KEYROARD:
PLMP, ON/+, FNIER T4EN M PUMP STAR'IS, CHECK PAPER PRIN7DTP 'IO ENSURE 'INAT A STA'IUS OCNDITION OF " NORMAL" FOR CHAMELS 1 'IHRU S EXISTS, IF THE PRIN'ICUT DOES N(7P SHOW " NORMAL" AND TIME PERMI'IS, EOLION S'!EP B OF HPO/CI)-140. IF M PfMP FAILS 'IO START, GO 'IO M GRAY CABINE"f IN M E.O.F. AND OB1AIN AN AC AIR SAMPLER AND PIDG IT INIO '19E WALL nebelhCLE BY M PING-2A. ( 1 l f I I
EP-203 Page 17 of 19, Rev. 5 9 i APPMDIX EP-203-12 FDP PHONE: C.O.L.
'Ibst Ring Down Phones:
Muddy Run News Center HOEC - 7th Floor TSC T9C - Control Room Test Dial Phones for Dial mone: 4205 S.E.C. 4658 S.E.C. OCPMJNICA"DR 4662 MC O WICE 4656 DOSE ASSESSMENT GROUP IEADER 4644 DOSE ASSF."eMFNr GROUP 4643 RAD PKnu;nON 'IEAM LEADER ( 4327 RAD PBCYIECTION 'IEAM 4646 HP&C COORDINA'ITR 4295 FIFLD DATA WNI'ItRING 4655 PfMA/BRP/KI) OWICE - NALL PHONE 4653 SDF 'TELECOPIER 4642 ELECT. MG. LIAISON 4641 MBCH. ENG. LIAISON 4210 Piu.uxJRE SUPPCRT CDORDINA'IIR 4650 INPO 4651 PINNING COORDINA'ITE 4652 1!DF LIAISON ' 4648 3RD 'fRBIE 4649 3BD 'IRBIE (. 4640 PENA /RRPACO OWICE 4647 3BD 'IRBIE
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Page 1 4688 PLANT STA'IUS-FNENT CHRONOIDGY BOAPD
, 4640 STATES 4645 DOSE ASSESSMENT 4654 PA. MR. OF RAD PTOiWr10N 4657 CONFERENCE FOOM 4656 S.E.C. WALL PHONE 4693 'E:LECDPIER Ring Down - DO NOP TEST:
NRC RED PHONE BLUE - M. & 5 COUNTIES WI'IE - PA. BUR. OF RAD Pisir.L. TION YEIHM - MD. & 7 COMPIES GRFEN - MD. DEPT. OF HEAL'lYi AND PA. BRP. ( I t l ( r l
. ___ .- ' ' ' ~
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EP-203-12 EOF Habitability Guidelines + 1 i RM-16, 'l Ping 2A Gamma 120 mR/hr 24 hour stay time prior to reaching Low Alarm 120 mR/hr 24 hour stay time prior to quarterly limit-of 3000 mR . reaching a quarterly limit (d 3000 mR. High Alarm 375 mR/hr 8 hour stay time prior to 200 mR/hr off-scale. Consider initiation,of reaching quarterly limit of 3000 mR. periodic surveys. , , Site Emergency Coordinator should order evacuation of E.O.F. Xe . N/A . Low Alarm 50% of high alarm (2X10-4 uCi/cc) 24 hour stay time High Alarm 10% of maximum value (5X10-4 uCi/cc) 8 hour stay time Site Emergency Coordinator should order evacuation of E.O.F. Note: MPC occupational exposure IX10-5 uCi/cc Beta N/A Low Alarm 50% of high alarm (5X10-9 uCi/cc) Particulate 24 hour stay time High Alarm 10% of maximum value (lX10-8 uCi/cc) i 8 hour stay time Site' Emergency Coordinator should order evacuation of E.O.F. . 4 e Note: MPC occupational exposure 3X10-10 uCi/cc *8 Y" 0 I 131 N/A Low Alarm 50% of high alarm (2X10 ~7 uCi/cc) "* 24 hear stay time $ High Alarm 10% of maximum value (4X10-7 uCi/cc ' 8 hour stay time @ Site Emergency Coordinatpr should order < evacuation of E.O.F. i
, v, Note: MPC occupational exposure 9X10-9 uCi/cc e g 'A ,
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,. Ep-209 -
- CON; ROLLED APPROVED CO M- Tage 1 of 14, Rev. 4
, VOID PREVIOJS ISSUE ,
matth j
- LIS.RICUTIO!
- .
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( SS - SIV.. . 4__ SILAMELPHIA ELECTRIC CD4PANY MR 2 5 lH3 ,,
- Control Rm.. PEACH BOTIO4 (MITS 2 AND 3 - i Station Supor. M MCl PIAN IMPT)NFNI'ING PROCf7URR Office EP-iOS RADIATION tmO'rECTION '1EAM ACTIVATIfM
. PuReass
'Ib define the actions required to activate the 9adiation Protection Team. 'Ihe sub groups of the Radiation Protecticri ' Nam are Field Rurvey, Chemical Ramoling and Analysis, Dosimetry, Bioassay, and Respiratory.
REFERENCFS
- 1. Peach nottom Atomic Power Station Emergency Plan Section Title 5.2.1.5.5 Radiation Protection ' Nam 6.0 Emergency Actions
- 2. NURDG 0654 Criteria for preparation and Evaluation
( of Radiological anergency Resoonse Plans and Preparedness in Support of Nuclear Power Plants. > 3. EP-207P Vehicle Monitorina and Decontamination , APPENDIX EP-205-1 Contacting Radiation Management Corporation -
- EP-205-2 energency 5:xposure Limits (anergency Plan Table 6.1)
./EP-205-3' Offsite Post Accident Sampling Analysis
- C.O.L. for Baboox & Wilcox Lynchburg Research Center EP-205-4 Background Information for Offsite Post Accident Samoling Analysis ACTION LEVEL 4
'Ihe Radiaticri Protection Team or its subgroues shall be activated by the anergency Director if and when he needs their assistance, t regardless of the class of emergency. ,
~~
. ( - FP-205
,- Paq:2 2 of 14, Rev. 4
( PRTAI7f' IONS ,
- l. meam member's exposure should be limited to the administrative guide levels in Appendix EP 205-2, Emergency Fxposure Limits. Team members should control their exposure in accordance with AIARA concepts at all times.
- 2. Vehicles requiring decontamination could oossibly be d* contaminated utilizing appropriate decontamination procedures at any of the following assembiv areas:
a) North Sub Station
~
b) Dresident's Utility Railding (Prm) c) Delta service Building
- 3. Permission of the site Emergency Coordinator is required before decontamination of any vehicles due to large contamination control problem associated with this procedure.
IMEDIA9E ACTIONS 1.0 Emergency Director shall: ( l.1 Direct the Operations HP to assume the role of Interim Radiation Protection Team Leader to:
- 1. Form a Team.
- 2. Initiate surveys & sampling aopropriate to -
the event.
- 3. If the situation permits, discuss the problem with the Interim Radiation Protection 'Ibim Leader so he can -
assess the situation and determine how many team members
. will be necessary for anticioated operations.
l 2.0 Ooeraticns MP shall:
.1..Unan recuest of the Emergency nirector, assume the role of Interim Radiation Protection meam TAader.
2.2 Form a team from qualified oeoole. Mave the team l recort to the Aux. Operations Suoport Center on 116' Elev. turbine bldg. or a location designated by the mergency e Director, such as the anergency Operations Facility at Unit 1. l i
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, Fp-205
. Page 3 of 14, Rev. 4 4
2.3 Assign the assembled personnel to function on the ( following interim groups as necessary to provide 7 suoport to the Emergency Director: Sub Groups Radiation Protection W am Groun activation should be
- imolemented in accordance with: _
Chem. Samoling and Ana- EP 205A lysis Group Radiation Survey Group EP 2059 Field Surveys
- Dosimetry, Bionssay and EP 205C
; Respiratcry Protection l Dose Assessment EP 210 3.0 Radiaticn Protection Team Members shall: -
3.1 Recott to the Aux. Operations Support Center on llr elev. i 1 turb. bldg. or another location as specified by Faergency Director.
^
(' 4.0 Radiaticn Protection %am Leader shall: i 4.1 When notified of an emergency condition renort to the Emergency Operations Facility and coordinate the Radiation Protection ham to provide Emergency Director and 9ite g anergency Coordinator with radiation protection and field - survey status. 4.2 Relieve the Oos HP as Radiation Protection %am Leader. INXLOHJP ACTIONS 1.7) Radiation Protection Nam ,eader shall:
,1.1 nirect team members to assemble the equipment that will
. .bes needed to perform anticipated tasks (surveys, calculations, etc.).
1.2 Coordinate dispatching the survey teams under direction of the Site Bnergency Coordinator or the Emergency Director. 1.3 Prepare Appendix EP-20'5-1, Contacting Radiation Management Corooration (IOC), when requested by the Site Emergency Coordinator. _ l.4 Provide radiation protection team members with periodic plant status changes including significant radiation exposure and __ ( radioactive contamination problems which may affect the functions of the team. 1
._.___.~,____m- -- - -
s '.. _ P 205 [.
- - Page 4 of 14, Rev. 4 .
- l. 5 Use necessary members of the Radiation Protection Team to man
{ Dose Assessnent Board and Comunications in Emergency operations -- Facility.
- 1. 6 Maintain comunications via any available means with the groues after they have been sent to perform their assigned tasks.
1.7 If necessary, utilize the cost accident sampling analysis capabilities of Babcox and Wilcox by refering to Accendix EP-205-3 for proper notifications and EP-205-4 for background information. 2.0 Radiation Protection Team Members shall:
'2.1 obtain emergency equioment stored in the HP&C Ooerations support Center on 116' elev. turbine gldg. or the aneroency operations. Facility as directed by Radiation Drotection Leader.
2.2 verify onerability of the emeroency equipnent asserrbled l in the Aux. Operaticms Support Center on 116' elev. turb. bldg. - cr the Energency Operations Facility. 2.3 Standby and await instructions from the Radiation Protection Team Leader. l O M 9 E. 4 g- -- g,, e s ,- , , , , -,-,--, .,-n,----, , , , , , - , ,o, 7 , e,,v,,-, ,,, ,,,,e,, - - - , - -,,-,,,-rw , - - - - , , - - , , , - , - . , , ava, <mw a.-,m,mm,-- e,e
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( - FP-205
. Page 5 of 14, Rev. 4
( Apprndix EP-205-1
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CDNTACTING RADIATIOT %NAGMFNT CORPORA'rION Phone Number - 215-243-2990
'rhis is (Name) reoresenting the Radiation Drotection ' Nam ~*
of the Peach Bottom Atomic Power Station.
'there has been a release of radioactive material from the Unit (2), (3) plant and your assistance is required in the following areas:
Radiation Surveys ( Low Level, High Level) BETA NELTIPON Deccntamination ( ALPHA, BEIA, GMNA) - Environmental sample analysis Air particulate samples collection / evaluation ( Bioassay Wholebody counting other (soecify below) Acoroach the site from (direction, route, etc.) . Resoiratory protection (is/is not) necessary. Anti-contamination clothing requirements are: full partial (booties, gloves, other) Additicnal "mts:
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( F9-70% l Page 6 of 14, Rev. 4 l 6
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Appendix EP-205-2 EMERGENCY EXPOSURR LIMITS - Projected . Whole Body 'Ihyroid Authorized Function Dose nose By
- 1. Life Saving and Emergency **
Reduction of 75 rem
- 375 rem Director Injury
- 2. Oper'ation of Equipment Emergency **
to Mitigate an 25 rem
- 125 ren Director Emergency
. 3. Protection of Health Emergency and Safety 6f the Public 5 rem 25 rem Director
- 4. Other Emergency 10 CPR 20 10 CPR 20 Emergency Activities limits limits Director
- 5. Re-Entry / Recovery Adninistrative Adninistrative Activities Guide Lines Guide Lines N/A
Reference:
EPA-520/1-75-001 Table 2.1 ( **Such exposure shall be on a voluntary basis e h P f e a R
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^ [* MP-205 Page 7 of 14, Rev. 4
*b APPENDIX .EP-205-3 .
OFFSI'IE POST AOCIDENT SAMPLING ANALYSIS CHBCK-OFF-LIST FOR RA800X AND WIItVX LYNCRRURG RRRFNOI CEPTrPR 4 1 Message: Wis is (Name) reoresenting the Radiation Protection , Team of Peach Bottom Atomic Power Station. %is is a request to provide ' cost ace,ident sample analysis at the Lynchburg Research Center. All inquiries should be directed to (Name) at the following phone ntznber . %e following information is known concerning the samples: Unit Number of samples
- Estimated shipping time
, Method of transportation (air or land) Name of carrier 9 ample 1 2 3 4 i ( Type (liquid, gaseous, cartridge) Measured Radiation Levels
- surface
- 3 feet l Remarks:
Notifications: Emergency Control Officer Work *Iane J. P. Ooran 804-522-5137 804-525-4251 i Alternate Emergency Control Officer l A. F. Olsen 804-522-5174 804-933-2517 - l \ t
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Appendix EP-205-4 EP-205 BACKGROUND INFORMATION FOR OFFsITE Page 8 of 14, Rev. 4 j POST ACCIDENT SAMPLING ANALYSIS., ( . 1.0 , INTRODUCTION ,_ The NRC's " Clarification of TMI Action Plan Requirements," NUREG-0737, specifies requirements which must be met by licensees of comercial nuclear power reactors for post-accident sampling and analysis. To help meet the'se requirements, timely performance of off-site confirmatory and suppleme_ntal analyses is needed. To ensure that the necessary analytical capability would be quickly available if needed, a group of Boiling Water Reactor (BWR) owners has determined that prior arrangements are required. Accordingly, B&W has contracted with the BWR owners group to maintain in a state of readiness the facilities, material, manpower, and procedures necessary to perform off-site post-accident sample analyses. This technical plan prescribes the state of readiness to be maintained in terms of response time and . the scope of analytical services that will be available." (
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s' EP-205 - , Piga 9 of 14, Rav. 4 2.0 LABORATORY REACINESS ( .. B&W will maintain its Radiochemistry Laboratory and Nuclear Counting
- Room, which are located at B&W's Lynchburg Resairch Center in Lynchburg,
' Virginia, in a state of availability that will permit the analyses listed '
in Section 3.0 of this Plan to be completed within twenty-four hours of the receipt of the samples, except as noted in Section 3.0. During an accident situation, B&W will be able to analyze two of each sample type (gas, liquid, cartridge) daily fyr 7 days, and weekly thereafter. 1 To exercise the eculpment'an'd procedurits, practice samples may be
-( t submitted by a participating utility for analysis up to a group maximum
~
of twice per year. The practice analysis'will be performed at the option
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of the utilities. . i
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. '3 , PIga 10 of 14, Rav. 4 ,
x [ ' 00620S0 , ( . ._ 3.0 POST-ACCIDENT SAMPLE ANALYSES B&W will be prepared to analyze three sample types - liquid, gas, and _ cartridge. Liquid samples submitted for analysis will consist of approxi-mately 10 ml of undiluted reactor coolant or suppression pool water. ' Gas samples will be submitted to B&W in 15 m1 gas sample vials and will be at or slightly abcN atmospher'ic pressure. The third sample type will consist of silver zeolite and/or charcoal filter cartridges. . The range of ' analyses to be provided for the post-accident samples is described'below. - 3.1 Gamrna Ray Spectroscopy All sample types will be counted for ganna ray activity with a cali-brated Ge(Li) or intrinsic Ge spectrometer coupled to a multichannel analyzer. For the liquid and gas samples, all ganna rays in the spectrum with a net peak area greater than 5% of the s,pectrum counts within a region of interest consisting of a band *5 times FWHM'about the peak centroid will be identified - and quantified with an accuracy'of better than 20%. With this type of spectral prominence, the detector system will be capable of analyzing liquid and gas samples with isotopic concentrations of as low as .01 microcuries per cc.
~
i The gamma ray spectroscopy analysis of the cartridge samples will identify arid quantify all isotopes emitting gamma rays between 50 and 2000 kev to an accura'cy of 50%. . 3.2 Elemental Analysis _
^
The volun.e percent of hydrogen, oxygen, and krypton will be determined - for each of the gas samples using gas chromatography. The accuracy of the ( analysis will be 20%!for concentrations be'.cw 0.5% and 5% for concentrations - above 0.5%. t i
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EPL2o5 Page 11 of 14, Rev. 4 0062090 ' 3.3 Beta Activity - A gross beta analysis will be performed on each liquid sample. A separa.te analysis for 89Sr and 90 S r will also be performed. Gross beta activity will be measured by liquid scintillation counting. The Sr isot. opes will be chemically separated from all other elements and also counted by liqu.id scintillation. The Sr analysis will require approximately 10 days since the
- method requires that the Sr activity be counted twice. The second count yields the 90Y activity which then allows for the mathematical separa-tion of the 89 Sr and 90S r. Based on our previous TMI experience with high Sr levels, for a ratio of 89Sr to 90Sr of about 10, the accuracy would be 10% for 895r and t255 for 90Sr. As this ratio decreased (89Sr decays off),
the accuracy of the two isotope determinations will reverse. 3.4 Alpha Activity The total alpha activity of each liquid sample will be measured with a
.. gas flow proportional counter. Uranium and plutonium will be separated from
( the bulk of the sample by ion exchange and counted in the same manner as the gross alpha activity determination. An accuracy of *25% is achievable for an alpha activity of 10-6 Ci/ml. - " 3.5 Conductivity The conductivity of.the liquid samples will be measured with a micro- _ conductivity cell over a range of 1 to 10,000 micromhos/cm with an accuracy 6f 10%. Contamination of the sample by dissolved gases, particularly CO2 . makes conductivity measurements of <1 micrombos impractical. I 3.6 .pji The pH of the liquid samples will be measured with a pH probe to an accuracy of at least 0.3 units. The range over which measurements will be made is from a pH of 1 to 13. . s t t
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EP-205 Page 12 of 14, Rev. 4 3.7 Chlorides - The chloride content of the liquid sample will be measured either with a chloride ion-sensitive electrode or an ion chromatograph. The chloride ion-sensitive electrode will provide an accuracy of 10% for concentrations greater than 500 ppb and 50 ppb for concentrations less than 500 ppb. An ion chromatograph may be used if significantly improved accuracy could be obtained.- 3.8 Boron Analysis The boron content of each liquid sample will be measured over a range of 0.1 to 10,000 ppm by one of two methods:
- 1) Formation of a colored complex with carminic acid followed by ,
spectrophotometric measurement of solution absorbance, or
- 2) Titration of the boric acid with standardized NaOH after addition of mannitol.
The actual method used will depend on suspected boron concentration range and the activity of the liquid sample, which determines the volume of solution that can be safely handle,d for the measurement. Boron in the range of 0.1 to 100 ppm will be datermined with an accuracy I of 5%. Baron in the range of 100 to 10,000 ppm will be determined to an accuracy of 1%. -__ 3.9 Items Affecting Exoerimental Results l 319.1 Reagents - The quality of chemical agents used in the analyses will have a direct impact on quality of results. In addition, a sufficient quantity of reagents must be kept on hand to ensure that the analyses can be performed in the time frame prescribed by this plan. 3.9.2 Equipment - As a mi'nimum, the following equipment is required.
- 1) Ge(Li) or Ge gamma ray spectrometer and associated electronics
- 2) Multichannel analyzer and minicomputer for spectral analysis _
- ' 3) Gas flow proportional counter
v
. I' ,
EP-205 Page 13 of 14, Rev. 4 (1062090 i .
- 4) pH meter
- 5) Chloride ion specific electrode and/or ion chromatograph
- 6) Gas chromatograph
- 7) Ion exchange columns
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- 8) Micro-conductivity cell and conductivity bridge
- 9) Spectrophotometer
- 10) Voltmeters
- 11) Miscellaneous' glassware and laboratory supplies Because the intent of this project is to provide analytical results quickly under emergency conditions, the constant availability of the primary equip-ment or of back-ups is essential. Therefore, these instruments will be kept in a state of repair, set-up, and calibration that will ensure sufficiently rapid and accurate post-accident sample analyses. -
3.9.3 Radioactive Standards - Radioactive standards used in instrument set-up and calibration will be sufficiently characterized in terms of isotopic content and disintegration rate to ensure that the radioanalyses will be I accurate to the precision specified in Section 3.0 of this plan. m
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( . 4.0 REPORTS l The Research and Development Division will provide input as re for the preparation of reports to be issued quarterly, commencing f l date. of contract initiation (June 1,1982), for a period of one yea I
. . . . R&DD shall thereafter provide input as required for annual reports out the contract period. These reports will discuss the maintenanc calibration of all equipment as well as the results of any practice submitted during the reporting period.
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- EP-205A.1
, CCH.20LlID A?.20VED COPY- Paga 1 of 25; Rev. 2 VOID PRIVIOUS ISSUE SH/ ADO:tth 1
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Control Rs. PET'H BCFI'IOM UNITS 2 AND 3 m 2; 9 ' St . tion SupaGE%ENCf PIAN IMPLEMWPING PRCX?njw. Office EP-205A.1 OPERATICN OF POST AOCIDENT SAMPLING STATION
~
PURPOSC
'Ihe purpose of this procedure is to provide guidelines for consideration prior to, during and after obtaining samnles from the post accident samoling station following accident conditions.
RM'FR5.7CES
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P&ID M37A, M372, M361, M316, M362 EQUIPMENP Aopropriate Health Physics Survey EquiT2nent
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Air Campler (low volume) Respiratory Protective F/pioment Anti-C Clothing Digital Alarming Dosimetry Gas Vial Sample Tube C- Iodine & Particulate Sample Assembly 14.4 Gas Vials and Caps _-_ Liquid Samole Bottles and Caos 10cc Syringe with Stoplock Silver Zeolite Cartridges 47mm Particulate Filters Small Bottle of Demin Water Large Volume Cask Small Volume Cask Gas Samole Cask - Flashlight Mirror Watch with Secondhand Plastic Bag & Pole to Transport Cartridoes PDECAUTIONS l A. In all steps of this procedure, an ALARA concept is mandatory. 'Ihis procedure orovides some philosophy in pre-planning sampling evolutions for samoles during an - accident. In addition to reviewing this procedure, an AIARA review of the sampling process should be performed _ prior to obtaining the samole. If the samole is not really - needed, and lower dose methods exist to determine the gross data that the samole ~provides, the sample should not be obtained. - B. At no time may NRC exposure limits (either airborne e - -- . - , , - -
EP-205A.1
, Pags 2 of 25, Rev. 2 g or body dose) be exceeded during the surveying for gf samp1.ing or obtaining the sample. If it acpears that ,
an overexposure could reasonably occur when obtaining the sample, do NOT proceed without written NRC approval. PROCE: DURE:
- l. It has been determined that a drywell atmosohere, torus atmosohere, reactor building atmosphere or primary coolant sample is needed from the post accident sampling station.
Make sure before entry into the M-G set rocm that all personnel who will handle a sample have extremity (hands) , dosimetry in place.
- 2. 'no paths are recommended.
A. Entering the normal turbine building 116' plant entrance , up the turbine building stairs to the M-G set room. Time = Approximately 3 minutes. B. Entering the roll up doors on the north end for finit 3 or south end for Unit 2, up the turbine building stairs to the 4-G set room. Time = Acoroximately 3 minutes.
- 3. Have a Health Physics Technician accompany the Chemistry Technician assigned to obtain samoles in order to perform area surveys. Brief Health Physics & Chemistry oersonnel on the route to be taken and '.he time to get to the samole point.
- 4. Health physics eersonnel shall take acorooriate i survey equipnent and protective equipment (e.g.
l SCBA cear, anti-C's, etc.) . Before making entry I to the Power Block, ensure survey equipnent is turned on and calibrated. i Upon entering the Dower Block, the surveyor (s) 5. will note trends in general radiation levels enroute to the samole point. If dose rates exceed 10 R/hr gama or 10 rad /hr beta prior to arriving at the point specified below and upon further investication this dose rate remains stable or increases, exit inmnediately and recort to Health Physics Supervision.
- 6. If the dose rate at any door that has to be opened is greater than 5 R/hr, leave the area immediately and recort to Health Physics Supervision with this information. __
With the dose rates less than 5 R/hr, enter the area {w) but take careful rotice of the dose rates. I l i I l _
E5--2'05 A.1 Pags 3 of 25, Rev. 2 [ (,\ ,
- 7. ?.e following are the times required to obtain samples Drywell or Torus Atmosphere 25 Minutes Reactor Building Atmosphere 10 Minutes Primary Coolant Jet Pumo 20 Minutes RHR 25 Minutes Use the appropriate appendix for the desired sample:
Appendix A.1 14.4m1 gas sample from drywell, torus or reactor building atmosphere. Appendix A.2 Iodine and/or particulate sample from drywell, torus or reactor building atmosphere. Appendix A.3 10cc sample of reactor water and/or dissolved gas sample. Appendix A.4 .lec reactor water sample with 100:1 dilution. .
?.ppendix A.5 Flushing the liquid and dissolved gas system.
Apoendix A.6 Draining the trap, sumo and collector. (- 8. A R'.@ or HP technician will be assigned for the sample collection and analysis.
- 9. Prior to the sample entering the hot lab, any shielding, remote tooling or other protective measure shall be in place and ready to accept the samole.
- 10. Upon introduction of the sample into the hot lab, the sample will be handled in a manner such that it will cause an ALARA whole body dose to personnel involved.
Unnecessary personnel shall not remain in the hot lab.
- 11. Procerly in place and shielded, the sample will be processed renotely (where and when possible).
Careful handling of the sample is mandatory in preoaration for analysis so contamination is not scread, airborne problems are held to a minimum, and a new samole is not required.
- 12. Follening final analvsis of the sample, results shall be reported to appropriate supervision. .
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EP-205A.1. Paga4' of 25, Rev. 2 APPENDIX A.1 14.4 ML CAS SAMDIE (,~.r1 w P9ERFOTISI'JES:
- 1. System lined up in accordance with C.O.L. S.20.1.
- 2. Have shif t line up CAD system for desired samole. -
Sample Unit 2 Unit 3 Position
'1brus 5960A Open 5961A Closed l 5966A 'Ibrus II 9101 Open 59519 Open Torus 4960D Open 4%1D Closed l 49660 'Ibrus II 8101 Ooen 4951B Open -
Uooer 59608 Open Drywell 5961B Closed 5966B Drywell II 9101 Open 59518 Open ( Imer 4960C Open Drywell 4961C Closed 4966C Drywell II I 9101 Open 4951B Open No line up needed for secondary containment samole.
- 3. Have shif t place control room switch AO-8108 on the Unit 2 side or SV-9108 on the Unit 3 I
side to the local position.
- 4. Obtain the key to the control panel power from l Shift Supervision or Chemistry Supervision.
- 5. If heat. trace is desired for the CAD sanple lines or comon gas line, press the heat trace reset button
[ on the control panel in the M-G set room. 'This l will turn on the heat trace system, however to turn l the system off, the breaker OY64 in the reactor ' building must be turned off then on again. Use the heat trace only when absolutely necessary. If heat trace is used wait until the system reaches operating temoerature before taking a sample. . procFDURE: ( '
- l. Orain the system per Appendix A.6.
$ 3 e me a =w4 = 4 +we,e.. e4 em
,-r --- - ,--,m-- w -,,,- -
w-. - - - -
Page 5.of 25, Rev. 2 With the sump drain system switch in the off position i 2. place switch HC-700 (liquid / gas selector) in the gas
.. l t !
pi position. Open N2 bottle valve and regulate to o aoproximately 80 psig. Make sure the gas chiller E-703 is on. Quickly inspect the needle in the gas port to determine that its condition is satisfactory for obtaining a sample.
- 3. Install the gas filter drawer into position. If a _
particulate / iodine samole will be obtained later, make sure that the desired filter cartridges are properly installed in the cartridge retainer.
- 4. 'Ibrn ' switch HC723 (gas samole selector switch) to position 3 if a reactor building atmosphere samole is desired. If a torus or drywell atmosphere samole is desired, turn to position 1 and open the comon gas line isolation valve.
Unit 2 Unit 3 SV8108 SV9108
- 5. Dlace a standard 14.4 milliliter off gas vial into the gas vial positioner, slide the positioner into the gas port. Observe that the bottle status light changes from red to green.
(~ 6. Turn the 10 ML gas sample switch HC-705 to position 2 and circulate gas for a period long enough to assure that the samole lines are flushed out with gas being sampled. The minimum time required is 5 minutes. Be sure that the flow as read by the rotameter thru the samole enclosure window is in the expected range of 25 to 35 SCH4. Record flow and flush duration on data sheet.
- 7. 'Ibrn HC-705 to cosition 3 and evacuate the off gas vial. Record pressure of the wacuated vial PI-708 on the data sheet. Make sure the vacuum in the gas vial reaches a stable minimum reading.
- 8. Turn HC-705 to cosition 4, "Take sample". Make sure that PI-708 does not change. (If pressure changes significantly, it may indicate a system leak.)
- 9. Press the HC-720 button to obtain the sample. Keep button deprecsed until a steady oressure is reached.
l (Anoroximately 5 seconds.) Record pressure from l PI-708 on data sheet. This pressure should correspond - to actual pressure of samole being obtained.
- Record sample temperature TI-724 on data sheet.
( l 10. Turn HC-705 to position 5 " flush system" and flush l
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-m , - - -,
n- - w w w w , s-
EP-205A.1
. Pag 2 6 of 25, Rev. 2 for approximately 1 minute.
G 11. 'Ibrn HC-705 to position 6, 7, and R then straight up to off.
- 12. ' Turn the gas line isolation valve (AO-R108 for Unit 2 or SV-9108 for Tinit 3) to its closed position and HC-700 to off. -
- 13. Wearing cotton liners and gloves, and (observing AIARA practices) remove gas vial keeping it a maximum distance from the individual. Insert vial into gas vial cask. Close and latch vial cask.
. 14. Take the sample to the appropriate lab for further dilution and counting.
- 15. Calculate sample volume at the sample pressure as recorded in step 8. .
Vs = (14.7) (14.4) (T F + 460) (530) (P PSIA)
- 16. Perfacm the drain of trao, sump and collector ,
per Aopendix A.6. Close N2 bottle valve.
- 17. If this is the last sample required, turn all switches to the uoright and "off" position before turning "off" power. Return system valves to normal position. Return key to Shift Supervision l or Chemistry Supervision.
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EP-205A.1 Paga 7 of 25, Rr.v. 2 B () 14.4 ML Gas Samole
- 1. Sample Source Date Time
- 2. Sample Flow FI-725 (scfh) .
- 3. Flush Duration (Min.)
- 4. Absolute Pressure of Vial PI-708
- 5. Final Samole Pressure PI-708
- 6. Sample Temperature TI-724 ( F)
- 7. Calculated Sample Volume (ML)
V= (14.7) (14.4) (T F + 460) (530) (P PSIA) Note: Pressure gauge PI-708 on tinit 2 are in psig while those in finit 3 are psia.
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e EP-2054.1 l Pag 2 8 of 25, Rev. 2
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?.T.O:0IX A.2 IODINE /PARTICUIATE SAMPIE .
1 i PRERE(71I9ITES: i i SAME AS ADPENDIX A.1 viu.uAIRE:
- 1. Drain the system per Appendix A.6.
- 2. With the sump drain system switch in the off position place switch HC-700 (liquid / gas selector) in the gas position.
- 3. Put the desired filter cartridge (s)into the cartridge retainer. Put the cartridge retainer into the gas filter drawer. Wen put the drawer into the sample station and verify drawer position light is green. .
- 4. Occida whether a timed or non-timed sample is decired. If a high activity condition exists, a timed samole should be taken.
5 Ooen i:2 bottle valve and regulate to approximatelv {l 80 osig. Make sure the gas chiller E-703 is on.
- 6. Turn gas samole selector switch HC-723 to desired sample source. Position 1 for torus or drywell and positim 3 for secondary containment.
- 7. Ooen commm gas line isolation valve, if a torus or drywell atmoschere samole is desired.
Unit 2 Unit 3
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l A08108 Sv9108
- 8. Turn the iodine cartridge samole switch HC ~712 to posi. tion 2 and circulate gas for a period long enough to assure that sample lines are flushed out with gas being sampled. Minimum flush time is approximately 5 mintues.
- 9. Be sure flow as read by rotameter is in the range of 25 to 35 SCFM.
- 10. Record the flow FI-725, oressure PI-727, PI-726
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(located at sample station) and temoerature TI-724 (located on control panel) on data sheet. ('
- 11. Wrn HC-712 to cosition 3. We sample gas will l start to flow thru the filter cartridge. On data sheet record PI-727, PI-726, FI-725 and samole duration
I EP-205A.1 . Paq2 9 of 25, Rev. 2 l (.*\ in seconds. ' .
- 12. 'tb take a timed samole, turn HC-704 to Yes position and set timer KC-712 between 0 to 30 seconds. Make sure time is short enough that the activity on the filter will not be unnecessarily high. Observe RI-704 reading to determine if there is a raoid activity buildup. _
'Ihis reading will also include non-absorbing gases. Note whether samoled was timed or untimed on data sheet. Also note timer setting if timed.
- 13. After appropriate time has elapsed for either timed or untimed, turn HC-712 to position 4. A vacuum will be quickly drawn on the system.
- 14. After acoroximately 10 seconds, turn HC-712 to -
pccition 5 which will purge the system with air or nitrogen. Durge for at least 20 seconds or until RI-704 is stable. Record RI-704 on data sheet.
- 15. Rotate HC-712 to up and off position. Turn other '
switches off. Remove filter and cartridge retainer anc out them in plastic bags. Tape bags closed. Put drawer back into sample enclosure. Use a pole or rope to increase distance while transoorting. ( 16. Derform drain of trao, sump and collector following Appendix A.6.
- 17. If this is the last samole reauired, turn all switches to the upright and "off" position before turning "off" cower. Return all system valves to the normal position. Close N2 bottle valve.
Return key to Shif t Supervision or Chemistry Supervision. e W
EP-205A.1
, Page 10 of 25, Rev. 2 l
(S y; Iodine / Particulate Sample * .. l
. 1. Sample Source Date Time I L Orifice size 3.0
- 3. Flush Time in Minutes Minutes
- 4. Sample Flw FI-725 (Not thru Cartridge) (scfh)
- 5. Temoerature TI-724 ( F)
- 6. Dressure PI-726
- 7. Pressure PI-727
- 8. Pressure PI-726 (Critical flow thru cartridge)
- 9. Pressure PI-727 ,
- 10. Flw FI-725 scfh
- 11. Timed Sample - Yes or No
- 12. Flw Duration Seconds
- 13. Radiation Levels RI-704 Note: When critical flow is obtained through the cartridge assembly, a flow of 3.0 liters per minute + 15% is ,
achieved. This is true as long as PI-727 Ts at a minimum-- of 12 inches mercury vacuum.
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EP-205A.1 Paga 11 of 25, Rev. 2
' (.) ATDMIX A.3 IARGE LIGJID SAMPLE AND/OR A DISSOLVED GAS SAMPLE ext.xtuJISI'IES:
- 1. System lined up in accordance with C.O.L. S.20.1. ._,
- 2. Obtain the key to the control panel power from
;l Shift Supervision or Chemistry Supervision.
PIOCEDURE:
- 1. If the RHR line is to be used. Have the shift open the RHR samole line valves.
Unit 2 Unit ~4 AO 8098A AD 9098A A Line AO 8099A AO 9099A
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1 AO 80989 AO 90988 B Line l M 8099B AO 9099B
- 2. Perform the drain and blow out operation per Appendix A.6.
( 3. Open the N2 bottle valve and regulate to approximately 80 psig. l l
- 4. Check that the demin water tank is full.
Open the demin water discharge valve and the nitrogen inlet valve. Verify that the demin ~ l water tank is pressurized to at least 100 psig. [ 5. Open the tracer gas bottle valve and regulate to 2-3 psig. Record pressure. - i 6. Make certain the lead shield drawer is out so that the needles unde.: the sample station enclosure are exposed. Quickly inspect the needles with a mirror and flashlight. Check that the longest part of the' needle is toward the center of the sample vial.
- 7. Remove lead stopper from large volume cask and put a 15 ML sample bottle with an outer aluminum retainer ring and a neoprene cap into the large cask.
Note sample bottle must fit snugly in the holder and be vertically aligned. If necessary, place small - oM uMer samole vial. With cask in fully lowered position, roll cask into position under the sample staticn.
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- 8. With control panel power on and all other switches in the uo and off position, set switch HC-700 to the
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EP-205A.1 1 - Page 12 of 25, R;v. 2
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'4. liquid position, and liquid samole selector switch
{2 HC-626L to position 2 if a jet pump sample is desired " or to position 4 if the reactor valves were set for a RRR sample.
- 9. Push the plunger down which causes the sample bottle to be raised out of the cask and up onto the two needles. Make certain that while positioning the - '
cask on Unit 2 side, the forks are pointing to the right, and on Unit 3 side they must ooint to the left. Note that the bottle in light will change from red to green. (If cask is not aligned properly, lower bottle and reposition cask.)
- 10. Using the hydraulic pump slowly raise the cask, checking for proper alignment. Stop pumping when top cask ring is inside and the large volume cask is just below the bottom of the sample
, station.
- 11. Place the gas vial in the holder and insert into ~
the dissolved gas sample point. Note that the dissolved gas sample light turns green. If it does not, readjust the vial position.
- 12. Make certain that MC-616-1 (small volume sample switch) is in the off position.
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- 13. Turn the liquid samole source selector switch HC-626 to position 1 for jet pumo byoass line sample or 5 for R9R samole.
4 . If RHR sample is desired, close the samole line valves to feedwater sample sink. l Unit 2 Unit 1 . AO 8110A AO 9110A i AO 8110B AO 9110B
- 14. FI-664 on control panel should be aoproximately l 1 gpn. PI-661, 'T'I-660, CI-663, and RI-665 should l start to have meaningful values.
1 i l
- 15. Adjust PCV-627 so that the flow on FI-664 is at '
least 1 gan. Continue this flow for a long enough t period (at least 7 minutes) to be assured that the sample lines are flushed out with liquid being sampled. -
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Note: Record the flow from FI-664 and flush time on data sheet. - ( 16. When flush is completed, turn HC-626 samole source selector switch to position 2 for a jet pump sample or
, position 4 if reactor valves were positioned for a RHR
EP-205A.1 Page 13 of 25, R2v. 2 l {i sample. Adjust FCV-627 for a flow of 0.3 GPM - (to adjust FCV-627 use PCV-627) .
- 17. Turn the dissolved gas and liquid samole system switch HC-601 to position 1 and observe that'P-701 starts and valve CV-622 rotates. -
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i 18.- Wrn swit& HC-601 to position 2. Observe that P-601 starts.
. 19. Record the following on the data sheet:
Flow FI-664 Pressure PI-661 Temperature TI-660 Conductivity CI-663
. Radiation RI-665
- 20. Wrn swit& HC-601 to position 3 to isolate i -
the sample and start the dissolved gas separator. Leave in this position for approximately 10 seconds.
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- 21. Wrn MC-601 to position 4 to inject tracer gas into valve CV-615. When the valve is rotated during the next step the tracer gas trapped in the passage of the ball valve will be inserted in the I- samole flow looo. Leave in this position for approximately 10 seconds. Read and record the tracer gas suoply system pressure so tracer gas can be accurately calculated. The flow of tracer gas should be very srnall so that pressure droos in the line and valves will be insignificant. -
- 22. Note: If it is not desirable to introduce tracer gas, turn HC-601 to position 5 quickly and valve will not rotate. -
1 Wrn HC-601 to position 5. Let some of the dissolved gas separate from the liquid. l l 23. Read and record initial pressure PI-662.
- 24. Wrn HC-601 to cosition 6*. Pump P-601 stops and CV-653 opens relieving liquid loop pressure.
- Note: Do not leave HC-601 in position 6 for more than 5 seconds.
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- 25. Wrn HC-601 to position 7. %is will bring -
the rest of dissolved gas into V-610. Leave in position for 10 seconds. . (. 26. Read and record PI-662 on P-1. Wis will be the approximate pressure of the liquid loco.
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ED-205A.1 Paga 14 of 25, Rev. 2 Bl 27. 'nzrn HC-601 to position 8 for no more than 5 . b seconds (this will open CV-653 again) . Dissolved l gas will rise to hold up cylinder V-610 and then into collection chamber V-662.
- 28. 'nzrn NC-601 to position 9 to get ready to .
take the dissolved gas sample or to relieve the - ' [ collection chamber pressure. Pump P-601 will stop so that if the relieve pressure option is next exercised record PI-662 as P2 on data sheet as this is the pressure of the liquid sample loop.
- 29. 'rb take the dissolved gas sample, switch MC-652 will be used. When HC-652 is turned clockwise to gas sample, the pressure as indicated by PI-662 will decrease while the dissolved gas is drawn into
. samole bottle. 'Purn MC 652 to gas sample and hold for at least 10 seconds until PI-662 is very steady.
'Ihen release HC-652 and it will spring back to center position. Turn HC-652 again to gas samole, v erify equalized pressure and read PI-662. Record the steady '
cressure as P3 reading on the data sheet.
- 30. As an alternate to step 28, when a dissolved gas l sample is not desired, it is only necessary to relieve the gas pressure back to the suppression pool
(- by rotating switch HC-652 counter clockwise to the relieve pressure position and hold it while watching PI662. The pressure will equalize rapidly.
- 31. If a large volume liquid sample is desired, turn HC-601 to position 10. HC-629-1 must be pushed and held for 10 seconds or more for liquid to be drawn into the samole bottle. If a large liquid samole is not desired, turn switch HC-601 to the off position very quickly so that valve CV-620 will rot rotate -
and no radioactive liquid will be in the line ahead of CV-629,
- 32. 'nirn HC-601 to off.
- 33. Imer liquid sample bottle into large cask by pulling up on the plunger handle. Note: Do not turn or twist bottle while it is on the needles '
because the needles will bend.
- 34. Icuer the cask on the cart by relieving hydraulic oil pressure with the small petcick -
handle on the hydraulic cylinder. -
- 35. Slide the lead shield drawer back into the l enclosure to cover opening for the needles. -
(- l 36. Roll the cask out from under the samole station and quickly plug cask. Use the cask
-, w m - e n+ - - - - - . y .y -
9 - - - - -- c- - -- - w w 4 y w -- 7 w ww--w-7w-w--e p yw -
i . , EP-205A.1 Paga 15 of 25, Rev. 2 O' ~
" 'ransport the sample if greater than 100 mr/hr. -
- 37. Open and place gas vial carrying cask near sample station. Remove gas vial positioner from sample enclosure. Keep the vial at maxinum distance from the individual and insert sample -
bottle into the gas vial cask. Close and latch the gas vial cask.
- 38. Perform a flush of the liquid system with switch HC-628-1 per Apoendix A.5.
- 39. If this is the last samole desired, turn all switches to the upright and off posiHon before turning power off and return valves to their normal position. Close N2 bottle valve and tracer gas bottle valve. Return key to Shift Supervision or Chemistry Supervision.
- 40. Take the samples to the appropriate lab for crelysis. Have the dissolved gases analyzed for voltme of H2, 02 and tracer gas. Calculate %
I of H2 and 02 on the data sheet. l e G W l.
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EP-205A.1 Page 16 of 25, Rev. 2 () Large volume Liquid Sample and/or Dissolve Gas Sample ,,
- 1. Sample Source Date Time l la. Tracer Gas Pressure PSIG
- 2. Bypass Flow FI-664 GPM __ .
- 3. Flush Time Minutes
- 4. Sample Flow FI-664 GPM
- 5. Pressure PI-661 PSIG
- 6. Temperature TI-660
- 7. Conductivity Meter Scale CI-663
- 8. Radiaticn RI-665
- 9. Tracer Gas Supply System Pressure PSIG 9a. Initial Pressure P-O PI-662
- 10. Pressure P-1 PI-662
- 11. Stabilized Pressure P2 PI-662
- 12. Sample Pressure D3 PI-662
- 13. v1 H2 (From GC) ml
- 14. v2 02 (from GC) ml
- 15. V2 KR (from GC) ml
- 16. Vol % O2 %
l 02 Kr i Vol % O2 = (V2 .2P ) x (P + 14.7) 17317 V2 Kr
- 17. Vol % H2 %
H2 Kr Vol% H2 = V1 x (P + 14.7) 17317 V2 Kr Note: Dissolved gas cressure PI-662 is in osig for Unit 2 - and psia for Unit 3.
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EP-205A 1 Paga 17 of 25, Rev. 2 APPENDIX A.4 SMALL VOLUMS LIQUID SAMPLE - PRERECUISI'IES:
- 1. System lined up in accordance with C.O.L. S.20.1.
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- 2. Obtain the key to the control panel power from l
Shift Supervision or Chemistry Supervision. PRCA.wu tz:
- 1. If the RHR line is to be used, have the shift open the RHR sample line valves.
Unit 2 Unit 3 AO 8098A AD 9098A A Line AO 8099A AD 9099A AO 8098B AO 90988 B Line ~ AO 8099B AO 9099B
- 2. Perform the drain and blow out operation per Appendix A.6.
- 3. Open the N2 bottle valve and regulate to
(. , approximately 80 psig.
- 4. Check that the demin water tank is full.
Open the demin water discharge valve and the nitrogen inlet valve. Verify that the demin l water tank is pressurized to at least 100 psig.
- 5. Load the syringe with 10cx: of demin water.
Place stopcock on the syringe and load the assembly onto the injection port. -
- 6. Check that the small volume cask is in the cask positioner, and that both are hanging frcrn the hooks below the sample station.
- 7. Renove ' stopper and carrying handle from the small cask by unscrewing it and lifting it out.
Leave stopper near by.
- 8. Put a 15 ML sample bottle with an outer aluminum retainer ring and neoprene cap into a small volume cask. Check that the bottle lifting lever is free to nove up and down. -
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The bottle must fit snugly in the holder and be vertically aligned. If the bottle does not fit snugly, use a small pad of rubber or - ( felt, thick erough to hold vial against the upper yoke of the vial holder. l
EP-205A.1 Pags 18 of 25, Rev. 2
- 9. Make certain the lead shielding drawer is out
(~) so that! the needles under the sample station enclosure are exposed. Ouickly inspect the needles with a mirror and flashlight. Check that the longest part of the needle is toward the center of the sample vial.
- 10. With control canel cower on and all other -
switches in the up and off position, set switch HC-700 to the liquid position and liquid sample selector switch HC-626 to position 2 if a jet pump sample is desired or to position 4 if the reactor valves were set for a RRR sample.
- 11. Swing the cask into position under the samole station and lock the arms of the cask holder so the cask and bottle will remain in position.
. 12. Raise the sample bottle into position on the needles by noving the lever on the ~
side of the cask.
- 13. Screw the lift rod in to hold the sample bottle in the engaged position. Note: if the vial doesn't clear the entry hole, lower the h vial and rotate the small volume cask about 1/8" in either direction. If it still doesn't fit either the liquid vial positioner fixture or liquid tray positioner need adjustment.
Note: The green light for the small volume sample should be on. If the light remains red, unscrew the lift rod, lower the bottle and reposition.
- 14. Turn liquid sample selector switch HC-626 to positicn 1 for a sample from the jet pump line or to position 5 for a sample from the RMR line.
Adjust PCV-627 so that the flow thru ECV-627 is 1 GPM. (See FI-664) Ccntinue this flow thru bypass valve CV-626 for a long enough period to be assured that the samole lines are flushed. The minimum time required to do this is l 7 minutes. Record the flow and flush time on the data sheet.
- 15. After flush is completed, turn switch HC-626 to position 2 (for jet pump samole) -
or position 4 (for RHR samole) . Note that the flow on indicator FI-664 is greatly reduced. Adjust valve FIN-627 for a flow - ( of 0.3 GPM, using PCV-627. I
- 16. Record the following on the data sheet:
. EP-205A.1 l Pag 2 19 of 25, Rev. 2
's Flm/FI-664, Pressure /PI-661, Temperature / .
(L' TI-660, Conductivity /CI-663 and Radiation / " RI-665.
- 17. W rn small volume liauid selector HC-616-1 to "Take Sample" position.
Valve CV-616 will rotate and carry the - ' samole into alignment with the line to the sample bottle. Wait for valve CV-616 light to cane on. l 18. Open the stoccock on the syringe and inject 10 cc of water into the line. Close the syringe and line valves. Remove the
, syringe and fill it with air. Reattach the syringe, open the valves and inject the air, then close the valves and renove the syringe.
- 19. Unscrew the lift rod and lwer the sanole bottle.
- 20. Renove the sample from the cask by using cotton -
liners and gloves. If the sample is greater
' tlan 100 mR/hr, use the lead pig to carry the sample to the Chem Iab.
,. 21. Wrn the switch HC-616-1 to the flush position.
( Make sure there is enough fim by adjusting PCV-627 so that fim through KV-627 is at least 2 GP4. Flush for 5 minutes and/or until RI-665 reaches a mininum. i 22. When the flush is conplete, turn HC-626 - off FIRST and then HC-616-1 to off.
- 23. Perform the drain of trao, sump, and collector foll ming Appendix A.6. -
- 24. 'Ibrn all switches to their normal 'off' position. Turn PCV-627 back to O psig.
Close N2 bottle valve. Return key to Shift Supervision or Chemistry Supervision. O (1 s a 8
- - . - . . - - - - . - _ _ , - - , - - - . - - - .,,,m--, - - , , . , , - - - ~ - - - - ~
EP-205A.1 Page 20 of 25, Rev. 2 O
- Small Volume Liquid Sample T
- 1. Samole Source Date Time
- 2. Bypass Flw FI-664 (gpu) _ ,
- 3. Flush Time Minutes
- 4. Sample Flw FI-664 (ggn)
- 5. Pressure PI-661 (psig)
- 6. Temperature TI-660 ( F)
- 7. Conductivity fieter Scale CI-663
- 8. Radiation RE-665 I
e f \ e l w- ,y y %--m - --
EP-205A.1 Page 21 of 25, Rev. 2 O APPENDIX A.5 FLUSHING 'IHE LICUID AND DISSOLVED T GAS SYS'IEM vh@ISI'IES:
- 1. System lined up in accordance with C.O.L. S.20.1. ~ '
- 2. Obtain the key to the control panel power from l Rhift Supervision or Chemistry Supervision.
PROCEDURE:.
- 1. Open the N2 Bottle Valve and regulate to 80 psig.
- 2. Check that the demin water tank is full. Open the demin water discharge valve and the nitrogen inlet valve. Verify that the demin water tank l is pressurized to at least 100 psig. -
- 3. Make sure-that 107-627 is open b/ adjusting PCV-627 to 15 osig.
- 4. Switch HC-626 must be in position 2 (jet pump)
(. or 4 (RHR) and HC-700 must be in the liquid position.
- 5. Turn the flush system switch HC-628-1 to position 2 which will close the inlet sample lines and start the flush with demineralized water from V-501. Observe that there is a flow per FI-664. -
- 6. After RI-665 shows radiation has decreased significantly, or after 5 minutes, turn switch HC-628-1 to position 3 to flush the V-610 loop. .
Watch RI-665.
- 7. After a few minutes, turn switch HC-628-1 to l position 4 and flush the P-601 loop. Watch l RI-665.
- 8. After a few minutes, turn switch HC-628-1 to position 5 and flush valve CV-615. Watch l RI-665.
- 9. After a few minutes, turn switch HC-628-1 to position 6 and flush the piping station
[ for 3 minutes. .
- 10. 'Ibrn switch HC-628-1 to position 7 for a few
- minutes to flush loop CV-622 again. Watch RI-665. -
! ( l 11. 'Ibrn HC-626 to off FIRST and then HC-628-1
- to off.
L i
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1* EP-205A.1^
.. Page 22 of 25, Rev. 2
- g. .
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- 12. If RI-665 M.id not indicate an acceptable ?-
~
radiation level at any step of the operation, go back and repeat steos 4 thru 8. ;-
- 13. Perform the drain of trap, stmio and ~ t.
collection following procedure listed in Apoendix A.6. ~ 4, [
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APPENDIX A.6 DRAINING TRAP, SO2 AND COLLEC'IOR
- s\ ..
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s '- g g' - i PRERB3ISI'IES: x i '% c 3, '
- l. Systep lined up in aIccordance with C.O.L. S 20.1.
b , 1 y s- . 7'.
- 2. Obtain the key to the control panel power from ~
l Shift Supervisibn or Ccemi(try Supervision.] s t s *- ' % t .- PROCEEXJRE: .
- s. t
- 1. Check that the nitrogen supply valves are oper g~ and that pressure is set'.at 80 psig. ~
- 2. Check that the demineralized flush water tank -
V-501 is full and is pressurized to.at least. 100 psig and that the va'.ves are open to tie ' sample station. ;3 i '
- ;.\-
t -
.s. .
- 3. Check'that 707-627,is open. gIf not open, use the
- knob adjacent to PCV-627 on the control panel to
~ s' have a 15 psi rehding on the gauge.
' J, .
.4. Turn all control panel sd.ti:hes up and off
, and then turn trie control panel pcwer selector switdpto "A" or "B".
- 5. Drain the collecting tink ands stmp\by turn $ng !Nitch HC-715-I cicqwise th' rough Ji Its eight pcnitionne Pause approximately 5 seconds at' each position. ~
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6 Turn all switches to their 'bff' position.
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APP ETIX A.7 POST AOCIDENT SAMPLING S'mTICN GNT!OL SWI'ICHES (e.!- --- _'- .
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EP-205A.1 Paga 25 of 25, Rev. 2
.s APPENDIX A.8 FOENATIC OF hCSWACCIDDff SAMPLE f*i STATIOi .
k ' N2
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CV 721 - CV.719
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~; a P ge 1 of 4, Rev. 1 yg;n un,yIo
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/~- ; Sf- SCVN'd 'cA APR 251933 !
*u COntrC1 E2*-
st tien S*ger. - . - " Offi e ~~~~~~~ - PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 AND 3 EP 205A.Y RETRIEVING AND CHANGING SAMPLE FILTERS AND CARTRIDGES FROM'~~,r' THE DRYWELL RADIATION MONITOR DURING EMERGENCIES PURPOSE: This procedure provides guidelines in retrieving and changing particulate filters and charcoal cartridges (or silver xeolite cartridges) located.at the drywell rad monitor following accident - conditions with major fuel damage. . APPARATUS: Appropriate health physics survey equpment Respiratory protective equipment Anti-contamination clothing Low-volume air sampler . Designated remote handling devices ( Transport containers (shielded) Digital-alarming dosimeters Extr,a rad monitor filter holder Extra rad monitor cartridge holder PRECAUTION: NOTE: A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in preplanning evolutions in changing and obtaining drywell rad monitor filters and cartridges. In addition to reviewing this procedure, an ALARA review of the sampling process should be performed prior to obtaining the filters. If the sample is not really needed, and lower dose methods *
,to determine the gross data that tho samplo provides-exist, the samplo should not be obtained.
B. At no time may NRC exposure limits (either airborne or-body dose) be exceeded during the surveying for sampling or obtaining the sample. If it appears that an overexposure .... could reasonably occur when obtaining the sample, do not ' proceed without written NRC approval. . C
e *. EP 20bA.3 Pcg3 2 of 4, Rav. 1 PROCEDURE: l _ 1. It has been determined that the particulate filter and iodine Q cartridge are required to be changed rat the drywell rad i monitor on 135' elevation of the Reactor Building. 2. Area radiation monitors shall be checked and if the monitors in the area of the drywell rad monitor are indicating greater than 10 R/hr, changing the sample should very possibly not be considered. 3. Have a health physics technician accompany the chemistry technician assigned to obtain samples in order to perform area surveys. Brief health physics personnel on the route to be taken and the time to get to the survey point. ' Attached as appendices are the location of the particulate filter and the iodine cartridge. Survey maps are also provided. NOTE:
- 1. The time to travel from the 116' elevation entrance to the Turbine Building to the drywell rad monitor is approximately four minutes.
- 2. Other routes may be considered. The timos expected would be approximately four minutes for these routes, as well.
4. Health physcis personnel shall take appropriate survey and protective equipment (e.g. SCBA, Anti-Cs, lead carrying container, etc.) Before making entry to the power block, ensure survey equipment is turned on and calibrated.
- 5. Upon entering the power block, the surveyors will noto tronds in
' general radiation levels enroute to the drywell rad monitor. If dose rates exceed 10 R/hr gamma or'10 rad /hr beta prior to arriving at the door leading to Rx 135 and upon further investigation this dose rate remains stable or increases, exit immediately and report to health physics supervision. If dose rates exceed 5 R/hr at the door leading to Rx 135, leave the area immediately and report to health physics supervision.
~
- 6. Survey the area concentrating e3pocially on the particulate filtor
~
pig, lodine cartridge pig and sample lines. Ensure that a low-volume air sample is taken (in tne " breathing zone"). Special nbte of window open readings must be made because of the - ' submersion ai'r dose beta fields. (.. D e
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b 6 O O 1
- kP 205A.3 Page 3 of 4, Rev. 1 I U
NOTEY L' A. It will take approximately two minutes to pull and change both the filter and cartridge. B. Ensure that survey equipment is required when retrieving the samples. C. Consider discarding samples in place at the time of the - accident as'they will likely he too radioactive to count for gamma spectroseqpy. For more meaningful data, a shorter sampling time should be determin*ed for the replacement particulate filter and iodine cartridge.
- 7. . Suggested filter and cartridge change method (This procedure may be changed after an ALARA review.)
(, A. Obtain the extra filter holder and cartridge holder for the drywell radiation monitor. B. Insert a new particulate filter and charcoal cartridge into theso holders. Use silver zeolite cartridges in the place of charcoal to limit the noble gas buildup. Do not use silver zeolite cartridges during drills. C. Obtain two "J" hooks for removing the holders which are presently in service. Use the "J" hooks for transporting the holders at a distance from the body. ! D. At the drywell radiation monitor
- 1. place radiation monitor in purge
- 2. remove thunb screws on holders
- 3. place "J" hook on the "O" ring of the holder
- 4. pull the holder from the pig.
- 5. survey filter or cartridge and remove from area with."J hook if required by HP. I
- 6. 'sIido new holder into the pig 7.- repeat steps D(3) to D(6) for the other holder
- 8. replace one thumb screw in each holder
- 9. return radiation monitor to service
- 10. exit the area.
i ( 8. Consideration of expected dose rates from the samples must also ' j be considered. In this regard, the time to take the filter k and cartridge to the hot lab versus shielding the sample must be considered. The personnel who will obtain shall be briefed on all alternatives and will provide input into practical methods of remotely handling the samples. 1
s 0 EP 205A.3 Page 4 of 4, Rev. 1 9. {, A RWP filter and shall be assigned cartridge evolution.for th'e retrieval and changing of the by all personnel handling the sample. The.RWP shall be followed 10. If:'the samples are too'" hot" for gamma spectroscopy, they will be brought to the hot lab to await. final disposition. Any shielding, remote hand'1ing devices or other protective measure shall arrival. be in place and ready to accept the samples prior to their 11. After the samples are properly stored, responsible supervision sha. discuss and decide upon final disposition.
- 12. If the samples are able to be analyzed for gamma spectroscopy, thea particulate in manner suchfilter thatand iodine cartridge shall be processed the detector does not becomo contaminated.
13. Following to appropriate finalsupervision. analysis of the sgmple, results shall be reported 9 ( e 0
- j e
9 O ,
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9
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i e EP 205A.3 Appendican e EP 205A.3 APPENDICES
'm 1
A. _ Photographs of sample points. Original photographs arc
- kept on file with Hoalth Physics Supervision.
B. Plant layout maps. " - C. Survey maps. i e 8 e
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rP 205A.3 Apperaci*
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EP-2MA.7 CONIROLLED APIE0VED @ijil%DHLPHIA ELECTRIC COMPANY Paga 1 of 10, R
, VOID PREVIOJS ISSUEPEACi l BOTTOM UNITS 2 6 3 DIS RIBUTION: EMERGENCY FLAN IMPLEMEhTIN PROCEDURE
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p~ EP-205A.7p QMAINING 'mE TODINF/AND. TE SAMPIFA Ccatrel E:FROM.'HE MAIN S' PACK AND ROOP VENTS . Et tien gJUJDVING MI'IDOTP GJNDITIONS Ogi.e i i PURPOSE: -
'Ihe purpose of this procedure is to provide some guidelines prior to, during, and after obtaining iodine and particulate samples from the roof vents and main stack following accidnet conditions with major fuel damage.
APPARA'IUS: Appropriate Health Physics survey equipnent Air Sampler (low volume) Respiratory Protective Eqtaipnent Anti-C Clothing
, Digital Alarming nosimetry Sampling Filters and Holders Transportation Centainers (as appropriate)
Tungs and Rod (4' long) PRFI%UTION: f A. In all steos of this procedure, an ALARA concept is mandatory. 'Ihis procedure provides scrne philosoohy in preplanning sampling evolutions for roof vent and main stack effluents for iodines and particulates during an accident. In addition to reviewing this procedure, an AIARA review of the sampling process should be performed prior to obtaining samples. If a sample is not really needed, and lower dose methods to determine the gross data provided by the samples exists, the sample stould not be obtained. B. At no time may NRC exposure limits (either airborne or body does) be exceeded during the surveying for sampling or obtaining the samples. If it apoears that an overexposure could reasonably occur when obtaining the sample, do NCTP proceed without written NRC approval. PIOuwut<t;:
- 1. It has been determined that it is necessary to obtain the Yodine and particulate samples frcun the main stack or roof vents.
- 2. 'the route of transport reominended is as follows (m '
for the roof vents: eg ge-3e g e=$4w ewse - eowwe mo me w e =oge 4 -
EP-205A.7 Paga 2 of 10, Rev. 1 , l l Enter the normal plant entrance 116' or the-I? roll-up doors at north end (Unit 3) or l South end (Unit 2) .' Take the turbine building staircase from 116' to 165', - then take the reactor building stairs to 234', to the entry door at the refuel floor. Time = approximately 10 minutes.
- 3. Have a health physics technician accompany the chemistry technician assigned to obtain samoles in order to perform area surveys. nrief Health Physics personnel on the route to be taken and approximate times to get to the sample points. Attached as appendices are the locations of the sampling points, survey maps are also provided. ,
- 4. Health Physics eersonnel shall take appropriate survev equipnent and protective equitment (e.g. MSA SCRA gear) . Before entry into the areas, ensure that survey equirment is functional and calibrated.
- 5. While obtaining survey data, should general area radiation levels enroute to sampling locaticns exceed 10 R/hr and remains stable or
( increasing, exit innediately and report to Health Physics Suoervision. If dose rates exceed 5 R/hr gamna or 5 rad /hr beta within the 234 change room or 5 R/hr on ecntact with mains tack door, leave the area and report to HP supervision.
- 6. If dose rates are less than above limits, i
proceed to survey sampling system with particular interest being dose rates general area, contact sample holder in service and dose rates on sample lines. MME: Expect whole body submersion dose rates from noble gases. Take special note of window open readings in general area readings. -
- 7. Suggested filter and cartridge change method
('this procedure may be changed after an ALARA review). A. Obtain the extra filter / cartridge holder. Two - extra filter / cartridge M1ders are required for a roof vent change. Consideration should be given to use of cnly one sample point for {, the roof vent release point. _ p B. Before entering containment, insert a new
~
' EP-205A.7 Paq) 3 of 10, Rev. 1 particulate filter and charcoal cartridge
- h. into each holder. Use silver-zeolite cartridges in the place of the charcoal to limit the roble gas buildup. Do not use silver-zeolite cartridges during drills.
C. At the sample station:
- 1. Bypass the filter holder which is in service.
- 2. Have rod and tongs at hand andopen the front door of the samoler remaining at a distance as far as possible.
- 3. With rod, lower the sampler and with the tongs, reach in and renove the cartridge frca the system and place .
it inside the transfer' cask.
- 4. Place lid on transfer cask.
- 5. Insert a new cartridge holder into the sampler and nove the cam in the opposite direction and close the door.
- 6. Put the rod through the transfer cask and put pi'ns in place.
- 7. Return filter system to normal flow path.
- 8. Transoort transfer cask to analysis site.
( WE:: Transfer cask, rod and tongs'will be at sunple site.
- 8. Take the sample to the appropriate lab where analysis will be performed. Report the results to the aoprocriate supervision.
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5:P-205A.7 Page 4 of 10, Rev. 1
,,, EP-205A.7 AIP m DICES A Plant Layout Maps B Survey Maos 0
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, APPENDIX C,
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EP 205A.12
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APR 2 51M3 C atrcl En. - St tien Supor. -. Cffi ae PHILADELPHIA ELECTPJC COMPANY 4 PEACH BOT'IOM UNITS 2 & 3 EP 205A.12 - SAMPLE PREPARATION AND ANALYSIS OF HIGHLY RADIOACTIVE PARTICULATE FILTERS AND IODINE CARTRIDGES PURPOSE: i i The purpose of this procedure is to provide some guidelines for consideration t.uring ::mple preparation (sample reduction) and isotopic analysis of highly radioactive p.trticulate filters and iodine cartridges following accident conditions with major fuel damage. APPARATUS: k-Appropriate Health Physics survey equipment Air Sample r (low volume) Respirator protection equipment if required Anti-C clothing Digital - alarming Dosimetry i Appropriate lead shielding Whatman 452 filter paper i Cork borers or metal punch 14.4 ml off gas vials with septums Plastic tape [ Filter tower for Whatman 452 filters (25 mm) Cartridge purging system Supply of nitrogen (bottled) or breathing air (bottled) PRECAUTIONS: A. In all steps of this procedure, an ALARA concept is mandatory. This procedure provides some philosophy in pre-planning for sample preparation and analysis of highly radioactive samples. In addition to reviewing this procedure, an ALARA review of the sample preparation methods should i be performed prior beginning preparation (sample reduction) . If an analysis is not really.needed or a lower dose method is possible to j obtain the same data, do not perform the analysis. l B. At no time may NRC exposure limits (either airborne or body dose) be exceeded during the sample preparation and analysis. If it appears that
' {} -
an overexposure could reasonable occur during sample preparation or analysis, DO,NOT proceed without written NRC approval. al f (
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EP 205A.12
, , Page 2 of 4, Rev. 2 l
n D PROCEDURE: *
- 1. Obtain the survey data obtained when the sample was taken and transported to the Chemical Lab. Brief Health Physics personnel on the samplo preparation (if required) and analysis to be performed.
- 11ealth Physics Supervision shall determine air sampling requirement.
- 2. Health Physics personnel shall monitor dose rates during the sample preparation and analysis. Based on their analysis stay times shall .
be determined. During sample preparation and analysis, extremity doses should be limiting. However, whole body exposure shall also be considered. Extremity dosimetric devices shall be worn. An RWP shall be assigned to this activity.
- 3. Sample preparation shall be done in a ventilation hood or other ventilated area where respiratory protection equipment is not re-quired if possible.
- 4. Consider the use of tongs or other remote tooling during sample preparation.
- 5. Determine the contact dose rate from the particulate filter and the charcoal cartridge. If the contact dose rate is == 200 mrem /hr the sample may be analyzed directly by the Geli analysis on the 3 cm or 30 cm shelf. Check the dead time while placing the sample in the
(' counting cave. Samples with > 30% dead time may be counted but do not exceed 50% dead time.
- 6. Samples with contact dose rates y200 mrem /hr shall be analyzed by only counting a small portion of the original samples or by purging the nobles gas from the cartridge (for iodine sampling cartridges only)by step 13. After purging, if the dose rato is still > 200 mrem /hr, reduce the sample size. Lead shielding shall be considered for use while removing smaller samples. At a minimum lead bricks stacked around the sample shall be used. Monitor the dose rate to the hands during sample preparation.
! 7. Particulate filters with contact dose rates of > 200 mrem /hr may be analyzed by punching out a small area from the center of the filter. This may be done with a metal punch or a cork borer (rubber stopper cutter). The punched area shall be dissolved with nitric acid and placed in a 14.4 ml off-gas bottle for gamma isotopic analysis. Before analysis the off-gas vial shall be capped with a rubber septum ' and wrapped with saran wrap to prevent spread of contamination. The original activity on the filter can be determined by multipling the total activity measured in the off-gas vial by the ratio of the l total area of the filter to the punched area. Check the dead time j while placing the sample in the counting cave. Samples with h 30% dead time may be counted but do not exceed .50% dead time. Samples 1 50% dead time require further reduction in area. l 8. Iodine cartridges with contact dose rates of>.:00 mnem/hr after purging the noble gas may be analyzed by core boring or removing i j { - a small section (or volume) from the center of the cartridge. to remove a uniform core of charcoal or silver zeolite from the Try i cartridge. Weigh the amount of filter material removed. Mount this materia: in sample geometry (Whatman 452 filter on a card)a dose equivalent. Tr.nsrcr this material to a Whatman 452 filter with a filter tower. DG .M use water or any
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other solvent to' transfer the material. Weigh the amount of material 1 on the Whatman 452 filter. Place the Whatman filter and material on
- G ,
a ca.rd and cover with plastic tape. Count this Geometry on the 3 cm shelf. Check the dead time while placing the samples in the counting _ cave. Samples with > 30% dead timo may be counted but do not exceed - ]' 50% dead time. Samples > 50% dead time require further reduction of volume. The original activity of the cartridge can be .detesmined j by multipling the total activity measured on the Whatman 452 filter by the ratio of the weight of a cartridge to the weight of material
- on the Whatman filter.
i
- 9. Consider the use of more elaborate shielding during sample preparation if dose rates merit its use.
P
- 10. Before actual sample volume reduction is performed at least 3 dry runs using clean filters and cartridges shall be made. An AIARA Review shall also be done. Based on these dry runs and the AIARA Review changes to sample volume reduction procedures shielding or -
equipment shall be made to minimize exposure. Health Physics super-vision shall also review the possibility of not performing the sample volume reduction and analysis at all.
- 11. Consider shorter sampling times so that the filter and cartridges may be analyzed directly. During accident condition this may require that grab samples be taken periodically instead of continuous sampling.
- 12. Use silver zeolite cartridges in the place of charcoal cartridges to _
reduce the noble gas interference during isotopic analysis. The use I of silver zeolite will allow samples which contain more I-131 (as compared i to charcoal) to be counted with less dead time. Do not use silver zeolite cartridges during drills.
- 13. Samples with high noble gas backgrounds can be flushed to reduce the noble gas interference by the following method:
l' a. Setup the purge system as shown in Figure HP0/CO-127-1 in a low background area where the release of noble gas would not present a personnel exposure or equipment (counting room) ! problem. , b. Load the filter holder as shown in Figure HP0/CO-127-1. Place j- the " hot" side of the cartridge toward the quick-disconnect. l' Hold the cartridge in place with a filter backing ring but do not use a particule filter. Place the filter holder on the quick - i disconnect. Flow nitrogen or breathing air through the cartridge at the t c. same flow rate as used for sampling for two hours or less. After purging stop purge flow and remove cartridge. Repeat j step 5 through 12, 4 i
- 14. Consideration shall be given to the final disposition of the samples, -
the' remainder of the original sample and the waste produced.
- 15. Samples and the remainder of the original sample which are kept for e
additional analysis shall be stored in an appropriate location based b 3 [ on-their dose rate and radiological hazard.
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, Q/ ; Control EP.. ._ PFACH UNITS 2 AND 3 i . -- St tidD SW Et. 52E.tn9CY PIAN,.Ivi.FMWI'ING PROCTMJRR' *
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@-E05R RADIATION Sf1TU7EY GTKTP9 'n
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PURPOSE ; y, 4 I ! Q,s ' 1b define the actions of,the Radiation Survey Groups. t REFr.Rfwys V ' 49
, ,f
- 2. Pe h Tbttom Atomic Powe Station Emergency Plan .~
t secticry -,
'"itle
- 5. 2.1.' 9. % 1 Field Surveys S
'S.2.1.5.7.2 S Plant surveys ;
;- ,_.x ..
- 2. Health physics ooerating/ Chemistry operating Pro 5edures
' .1 a 3 ,
r.- Number Pitld ' i <
-3 \4 s 5 ..
-- L' HPO/CO-4 Radiation witW,Fermits
, 3 ., , - -
HPO/Cl>-8 Decontd1tirdt',lonT of 'baols and Eqtiipnent c' 5
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HPO/CO-ll EstabMphirri 'and,Postirh
'Radiolo;icallyl Controlled Areas 3 , , sN HPO/CO-60 -
Field Ue.cf Eberline Ion s Chamber Model 10-1 Radowl
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HPO/CO-62
!N FieldJTc8 of Eberline GM l Detector Model E-400 i , ;X
. HPO/CI)-63 ' Field Use of Eberline Contam-
.I ination port, itor Mcdel RM-14
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HPO/CO-64 ;- (?1eldU[h(.,fEberlineRM-14and
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.'HP-210 Probe as a Field Scaler
,. k HPO/CO-65 Field Use f a Iow volume
-" Portable Air Sxnpler
- HPO/CO-67 $ Field Use of Eberline SAM-2 for t -
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EP-205B
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en 3. NURMG 0654 criteria for Preparation and QJ Evaluation of Radiological
;
- Emergency Response-Plans and Preparedness in Support of Nuclear Dower Plants.
APPENDICIE EP-205B-1 Onsite Survey Data Sheet EP-205R-2 Emergency Exposure Limits (anergency Plan Table 6.1) I ACTION LEVEL
'the Field Survey Group will be activated as necessary by the Radiation Protection Team Leader. 'The Dlant Survey Group will be activated as '
necessary by the Personnel Safety Team Leader.
- PRFTAI1TIONS
.the group member"s exposure should be limited to the l.
' administrative guide levels in Appendix EP 2059-4, Emergency Exposure Limits. Team members should control their exposure in accordance with ALARA concepts at all times.
- 2. If the equinnent in use during a survey fails or
( malfunctions, it must be repaired or replaced; otherwise, the survey team shall retreat to a safe area until the equipment is reolaced or repaired.
- 3. When conducting field surveys from inside a vehicle, readings must be taken with the probe outside the vehicle.
- 4. Requirements of HPO/CD-4, Radiation Work Permits, are not applicable.
[ _ IM EDIATE ACTIONS 1.0 Personnel Safety Team Leader shall: l 1.1 Report to the 75C (3rd floor finit one) . 1.2 Acpoint a Plant Survev Group Leader to direct Plant Survey Squads and assist with In-olant Radiation Surveys. I 1.3 Instruct the Plant Group Leaders in the areas to be surveyed. l 1.4 Instruct the Plant Group Leaders to report the progress and results of the surveys on a periodic ('. basis via the " operator" radios which they will carry with them when they are dispatched frcm - the Emergency Operations Facility to make surveys. L - -
EP-205B { Page 3 of 7, Rev. 4 s. b', l.5 Appoint a group member to stav in the 'rechnical l Support Center and establish and maintain comunications from 'lant Aurvey Groups in order to record survey data for anse assessment purposes. 2.0 Plant Survey Group Leader shall: 2.1 Report to the Aux. Osc (Unit 2 ' Turbine Building El . 116') . 2.2 Disoatch squads to survey areas in the plant and on-site. A squad consists of 2 H.P. 'Dechnicians 'B' or contractor "resconsible" technicians. 2.3 Post areas as necessary to prevent the spread of , contamination and accumulation of large doses of radiation to operating personnel. 2.4 Relay the results of the surveys to the Personnel Safety ' ream Leader and the Control Rom.
- 2.5 Provide plant survey group members with sufficient olant status of radiation and contamination hazards to allow them to maintain radiation and contamination exposure to within approved levels.
L 3.0 Plant Survey Group Members shall: 3.1 Report to the Aux. OSC (Tinit 2 'nzrbine Building El . 116') . 3.2 Obtain necessary ecuiment for cor. ducting the surveys assigned by the Plant Survey Group Leader in Step 2.1. Equipnent can be obtained from emergency kits in the Emergency Operations Facility or from normal storage location of HP portable instruments. Obtain a sufficient number of data forms (EP-205R - Appendix 1) . 3.3 Check that equignent is functior.al before leaving for surveys. Additionally, ensure you possess the proper personnel dosimetry and pocket dosimeter is zeroed, prior to leaving to conduct surveys. . 3.4 Conduct surveys when directed to do so 17/ the Plant Survey Group Leader. Fill out appropriate sections of Appendix EP 2058-1. 3.5 During transit to specified areas, observe the energized survey instruments for changes above background levels. Reference level'is waist high
< frm the ground.
3.6 Use the GM survey meter to scan close to ground
EP-205B Paga 4 of 7, Rev. 4 c s, surfaces to detect deposits of contamination, k,/ , obtain shielded and unshielded readings to dernrmine Beta /Gama ratio. 3.7 Report data to the Plant Survey Group Leader via
" operator" radios or best available comunications method.
3.8 Air samples are to be taken to count room facilities either at Units 2 and 3, .tinit 1, or RMC Van. 3.9 Frisk before leaving any area which may be contaminated. 4.0 Radiation Protection Team Leader shall: 4.1 Rerjort to ,'EC during an alert or the TOP if activated. l 4.2 Aapoint a Field 9urvey Group Leader to direct Field Survey Squads and assist with Field Radiation
. Surveys.
4.3 Instruct the Field Group Leaders in the areas to be surveyed. 4.4 Instruct the Field Group Leaders to report the progress and results of the surveys on a periodic basis via the " operator" radios which they will carry with them when they are dispatched fra the Faergency Operations Facility to make surveys. 4.5 ADpoint a group member to stay in the Emergency Operations Facility and establish and maintain comunicaticms from Field Survey Groups in order to record survey data for dose assessment ourposes. 5.0 Field Survey Group Leader shall:- 5.1 Report to the TDP (second floor Unit One) . g 5.2 Disoatch squads, to monitor areas offsite, as designated by the Radiation Protection Team Leader. A squad consists of one H.P. Technician 'B' and one driver. l 5.3 Maintain comunications with ss ey teams via operator i radios. I 5.4 Analyze and relay the collected survey data to the Radiation Protection Team Leader. . 6.0 Field 9urvey Group Members shall: 6.1 Report to the TOF (seccnd floor Unit One) . (~ ' l 6.2 Acquire eauirnent & maps as the situation requires from the anergency Operations Facility. Ensure you carry l' t i _ . _ - . . . . _ _ . _ _ - . _ _ . _ _ . - - , - - . . _ . . _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ -
EP-205R
, Page 5 of 7, Rev. 4
, proper personnel dosimetry for the surveys you are to Q1 perform and pocket dosimeters are zeroed prior to leaving to conduct surveys. Ocerator radios are located in.the Communication Room of the Fmergency Operations Facility.
6.3 Inform senior ranking Security officer of vehicle license plate number of field survey vehicles and personnel assioned to those vehicles. During transit to the specified areas, observe the energized survey instruments for changes above background levels. Reference level is waist high from the ground. 6.4 Conduct surveys as assigned by the Field Survey Group g Leader. (Fill out appropriate portions of Appendix EP 205B-1.) rise rM survey meters to scan close to ground surfaces to detect deposits of contamination. Obtain shielded and unshielded readings to determine Reta/Gama ratio. All air samples taken should be counted in the field. Refer to HPO/Ot}-60 thru 67 for methods to take the various field samples required. 6.5 Tipon completion of the surveys, return the vehicle to a credetermined area (preferably the Delta Service Building) for possible decontamination. 6.6 Survey the vehicle and decontaminate in accordance with HPO/OO-8, Decontamination of Tools and I- Equianent, as necessary. If the vehicle was contaminated, inform the Field Survey Group Leader. 6.7 Report data to the Field Survey Group Leader via " operator" radios. 6.8 Frisk before leaving any area which may be contaminated, mLLON-UD ACTION 9 1.0 Radiaticn Drotecticn *eam Leader and Personnel Safety Team Leader shall: __ l.1 Analyze survey data and relay this data to the Site Emergency Coordinator and Dose Assessment Group Leader (if activated) and the Emergency Director. l 1.2 Provide the survey teams with appropriate information as to plant status and expected radioactive " plume" movement which may affect the activities of the teams. Advise team members to , be cognizant of " plume" and to move to edge of plume after data is collected. (Maximum advantage should be made of time, distance I and shielding in accordance with ALARA considerations) . 2.0 Field Survey Group Members shall: f'- 2.1 In case of failure of crimary communications radics, locate the nearest comerchl (pay) telephone and pass infor,mation via this secondary means of comunications.
- e. .
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'U A T E - TIME - SURVEY BY-ARE A (Location)
H E ASON - Instrument Type Range or Model Number Serial Number
- R ADI ATION -
SETA GAMMA NEUTRONS TOTAL MnAo.sa Ma wa - u n E Mis a . MnEM,wn. l DISTANCE i L. '
!2! ,
38 l5 Instrum:nt Type Type of Samplers and Serial Number Rtnge or Model Number brial Number Type of Counting Instrument 6 Serial Number CONTAMIN ATION - - AIRBORNE - Total Volume N Time AVER AGE FLOW R ATE COUNTER B ETA-G AMM A ALPw A ITEM ceufico em2 opurico cm2 sT ART . STOP - FT3/ MIN. EFF. ISOTOPE (S) GROSS COUNTS
,g COUNTING TIME MIN.
9 l G A OSS COUNTS / MIN B ACK CROUNo f CPM) I~~ NET lf CPM
*MICROCURIESiCU8iC CENT.
l'! l (SPECIFIC ACTivlTYl uCi/CC
"* MPC Functions = MPC 1131( )
NET CPM SCALER EF F a FILTER EFF.s A AE A FR ACTION a VOLUME (FTh = 6.28 a to !7EM ARKS / AREA DI AGRAM - Specify Activity Based on Gamma Spectroscopy (Computer printout) C
J EP-205B Page 7 of 7, Rev. 4 APPENDIX EP ?.058-2
*'s Emergency Fxposure T.imits Projected Whole Rody tyroid Authorized Function nose nose _Bv
- 1. Life Saving and Reduction 5hergency**
of Injury 75 rem
- 375 rem Director
- 2. Operaticn of ,
Equianent to Mitigate.an Emergency ** Dnergencv 25 rem
- 125 rem Director .
- 3. Protection of Health and Safety of Emergency the Public 5 rem 25 rem Director
- 4. Other Emergency 10 CFR 20 10 CPR 20 anergency Activities limits limits Director
- 5. Re-Entry /
Recovery Administrative Administrative Activities Guidelines Guidelines N/A
Reference:
EPA-52n/1-75-001 Table 2.1
**such exposure shall be on a voluntary ' oasis l
i () I _
, EP-?.07
., CONIROLLED A?? ROVED COP't. Page'l of 5,_Rev. 5
.. VOID PFCVIOvS ISSUE GG:
DISTRIBUTION:, M . . . .. . fA,e MK 2 a 1983
. <" SS - SE . C.h,. W @'[, A C COMPANi[
Qi Control H WITS 2 AND 3 :- St: tion Su;:n . _ PLAN IMDIFMNI'ING Phuc; *' Office EP-207 PERSONNEL SAPMIY 'IEAM ACTIVATION PURPOSE -
'Ib define the actions necessary to activate and assemble the Personnel Safety 'Peam. The personnel safety team performs the functions of Rearch and Rescue, First Aid, personnel and Vehicle Monitoring and Decontamination and Plant Survey.
i<.tme2CF9
- 1. Deach Bottom Atomic Power 9tation Emergency Plan Section 'Pitle 5.2.1.5.7 Perscnnel Safety 'Deam -
- j. 6.7.1.1.4 Evacuation, Reassembly, and Accountability
- 2. Health Physics Ooerating/Chemistrv Operating Procedures Number Title HPO/CD-6 Personnel Contamination Survey Techniques HPO/CO-7 Personnel Decontamination Procedure RPO/CD-8 Decontamination of '1bols and Equiment HPO/CO-14 Identification and Control of Tools and Equiment in Controlled Areas. _.
- 3. NUREG 0654 Criteria for Prenaration and Evalu-ation of Radiological Emergency Response Plans and Precaredness in Succort of Nuclear Power Plants.
~
APPENDIX EP-207-1 Emergency Excosure Limits (Emergency Plan Table 6.1) PCTION LEVEL
'The Emergency Director or Interim Emergency Director shall activate the Personnel Safety Team at his discretion. .
(- O
.- }
I ' EP-207 Pagn-2 of Si Rev. 5 PRECAUTIONS . . (*r:j '~
- 1. Team member's exposure should be limited to the -
administrative guide levels in Appendix EP 207-1, Mnergency Exposure Limits. 'Ihe Emergency Director. shall approve any team member exceeding Peach Bottom quarterly exposure limits. Personnel safety team members shall control their own exposure - in accordance with AIARA concepts. . DELDIA'IE ACTIONS
, 1.0 anergency Director or Interim Emergency Director shall:
1.1 Designate a Plant Operator to asstune the role of Interim Personnel Safety Team Leader and direct this person to assemble the Interim Personnel Safety Team from available resources. . 1.2 Inform the Interim Personnel Safety Team Leader of the reason for the team being activated. 1.3 Instruct the Interim Personnel Safety Team Leader to assemble the Interim Personnel Safety Team in the Operations Support Center on 1.35' elev. turb. bldg. or the Control Room, if the 135' elev. Ocoratials Support Center is not habitable, for instructions (or as directed by the Energency Director or Interim Emergency Director). 1.4 Call the Personnel Safety Team Leader. If the situation permits, discuss the problem with the Personnel Safety Team Leader so he can assess the situation and determine how many team members will be necessary for anticioated - operations. If site evacuation has occurred, the personnel safety team leader and alternate will be stationed at the designated assembly area (either North Substation or PUR) . 2.0 Interim Personnel Safety Team Leader shall: 2.1 Assign available oersonnel from the Operations Support Center or main control room to the required Personnel Safety Team Sub-groups to carry out applicable portions of the f611owing procedures as necessary. EP 207A Search and Rescue EP 207C First' Aid EP 207D Personnel Monitoring and Decontamination (Assembly
. Area) l EP 205B Radiation Survey Group - Plant Surveys 3.0 Interim Perscnnel Safety Team Members shall:
4 3.1 Follow the directions of the Interim Personnel Safety - Team Leader. 4
?.
. _ = .- . . ._
EP-207 Paga 3 of 5, Rev. 5 4.0 Persainel Safety Team Leader shall: , E/ 4.1 Report to the Technical Support Center and coordinate with Personnel Safety Team to provide Emergency Director with site radiological data / personnel injury / contamination status and site evacuation status. 4.2 Utilize necessary members of the Personnel Safety Team to -- . man Site Radiological Status Board and Ccmunications in the Technical Support Center. - 4.3 Ensure' personnel Safety Team members available at assembly areas (HP&C OSC on 116' elev. turb. bidq and designated evacuation assembly area). 4.4 Assign team members to functional groups as necessary in acr ordance with the following procedures: Search and Rescue EP 207A First Aid EP 207C Personnel Monitoring and Decontamination EP 2070 _ Vehicle and Evacuee Control EP 207E Vehicle Decontamination Procedure EP 207F
; Radiation Survey Group - Plant Surveys EP 205B
-[
4.5 Designate Group Leaders for the functional groups { formed. 4.6 Direct team members to assemble the equipment that will be needed to perform anticipated tasks (surveys, calculations, etc.) 4.7 Maintain comnunications via any available means with the groups after they have been sent to perform their assigned tasks. 4.8 Provide Plant Survey team members with periodic plant - i status changes including significant radir.tMn exposure and radioactive contamination problems which may affect the functions of the team. l 4.9 Coordinate disoatching the Plant Survey Team under di'rection of the Emergency Director. l 5.0 Personnel Safety Team Members shall: l - 5.1 Report to the areas designated by the Interim Personnel - Safety Team Leader or Personnel Safety Team Leader as quickly as possible. - r t 5.2 Obtain emergency equipment stored in the HPAC Ooerations Support Center on 116' elev. turbine bldg. or the Emergency l (' Operaticns Facility as directed by the Personnel Safety ~ l Team Leader. l* t
. . . _ _. - . __ ~ _ ,._.- . . . _ _ . . . . - _ _ _ . , , _ _ _ _ . , _ , _ - . . . _ . _ _ _ _ . . . _ . . _ - . . . . _ . . _ . . . _ _ _
-o .
EP-207 Page 4 of 5, Rev. 5 i ',
- v 5.3 Verify ooerability of the emergency equianent assembled '."
in the HP&C Operations Support Center on 116' elev. turb. b1dg. or the Emergency Operations Facility. 5.4 Follow the directions of the Interim Personnel Safety Team Leader or the Personnel Safety Team Leader. . 9 9 o e e O l i I I.
.- EP-207 Page 5 of 5', Rev. 5
~
l Aopendix EP 207-1 {g Bnergency Exposure Limits- ,, Projected I Whole Body 'Ihyroid Authorized Functicn Dose Dose By
.l. Life Saving __ .
and Reducticn Emergency ** ofInjury 75 rem
- 375 rem Director
- 2. Operation of Equipnent to Mitigate an Emergency **
Dnergency 25 rem
- 125 rem Director
- 3. Protecticn of Health and Safety of the Emergency Public 5 rem 25 rem Director
- 4. Other '
Emergency 10 CFR 20 10 CFR 20 Emergency Activities limits limits Director
- 5. Re-Entry /
Recovery Administrative Administrative ( Activities Guidelines Guidelines N/A
Reference:
EPA-520/1-75-001 Table 2.1
**Such exposure shall be on a voluntary basis G
=
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- PP 4U lt.;
I Page l' of 6, 3 Con; ROLLED dyn0CD COP?-
, , yoID PREVI0;S IbSJ:.
DIS;'RIBUTION: ' g gg 4 - 4; ad - - - - (~%; YSa-S+
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A C COMPANY g"gn2;ct.___3 a e m uNIs 2 AND 3 - office g g g .f g g a g p g EP-207C FIRST AID - . PURPOSE - 2 define the actions of the Personnel Safety Team First Aid / Search and Rescue Group regarding first aid. iwrueNGS
- 1. Peach Dottom Atomic Power Station FJnergency Plan Secticm Title ,
5.2.1.5.7 Personnel Safety Team 6.9.2 Decontamination and First Aid 7.1.10 First Aid and Medical Facilities
- 2. NURDG 0654 Criteria for Preparation and Evaluation
(- of Radiological Emergency Response Plans < and Preparedness in Supoort of Nuclear Power Plants.
- 3. ED-311 Handling Personnel with Serious Injuries, Radio-active Contamination Exposure or Excessive Radiation
~
Exposure, Emergency Director Functions. APPENDIX EP-207C-1 Injured Dersonnel Reoort Form EP-207C-2 First Aid Equipnent Locations in Power Block ACT' ION LEVEL
'Ihe First Aid phase of the First Aid / Search and Rescue Group will be activated whenever a personnel injury is classified as an Unusual Event and at any other emergency action level as determined by the Emergency Director. Also, EP 207A, Search and Rescue, shall be imolemented in conjunction with this orocedure.
PRECAUTIONS
- 1. Life-saving first aid treatment has priority over deccntaminaticn or treatment for radiation exposure.
(.-
- 2. Minimize radiation exposure and avoid group member
~ _ . . ----_.
i EP-207C l Pa.qa 2 of 6, Rev. 3 l ccntaminaticn as much as practical. (*'.)
- 3. If gross external contamination is found, internal -
contamination should be suspected.
- 4. Any material remtwed from a contaminated person shall be recovered and used for isotopic analysis.
- 5. 'Ihe First Aid / Search and Rescue Group Leader, will - -
maintain contact with the Personnel Safety Team Leader at the designated assembly area.
- 6. Objects causing contaminated wounds should be recovered or smeared for isotopic identification, if possible.
- 7. 'Ihe Emergency Director will approve any team member exceeding Peach Bottom quarterly exposure limits.
- 8. If First Aid Team is unable to move injured person, local ambulance assistance must be utilized.
I!HEDIA'IE ACTIONS 1.0 Personnel Safety Team Leader shall: 1.1 Assign members from the Personnel Safety Team at the designated assembly area to form First Aid / Search and Rescue ( Group (s) . Each group shall consist of at least three members; one must be multimedia qualified, one must be first aid-qualified, and one must be a Health Physics Technician. All should be familiar with the plant. 1.2 Appoint the most qualified oerson of the group to be , the First Aid / Search and Rescue Group Leader and to carry out Section 2.0 of this procedure. 1.3 Obtain exposure limit from the Emergency Director for - this activity. If subsequent first aid operations are necessary, the Emergency Director will adiust the radiation exposure unit accordingly. 1 l.4 If outside medical help is necessary, request the
- Emergency Director to contact the necessary help as described in Section 4.0 of this procedure. ; 1. 5 Arrange for inventory and restock the first aid kits, if necessary.
j i 1.6 Make necessary calls (as per EP-209) to arrange for ambulance or hospital services, j 2.0 First Aid / Search and Rescue Group Leader shall: l (. 2.1 Determine the extent of the injury and direct adminis-tration of first aid. See attached Appendix EP-207C-2 T T^iL~. J . _~7
- T " : L- :r::: -.._ - . , - - -. - .--
'EP-207C
,'Page 3.of.6, Rev. 3 for listing of first aid equipnent icication in the plant.
g Insure objects causing contaminated younds are recovered or v_ . - smeared for isotopic identification, if possible. - 2.2 Report to the Personnel Safety Team Leader the extent of the individual's injuries and re,- x4 supplementary medical actions as necessary (i.e., hospitalization) . Complete Appendix EP 207C-1 (if possible) and attach to injured person prior to shipping in ambulance. -- 2.3 Direct the First Aid / Search and Rescue Group to transport the injured person to a site first aid facility, if practicable. i Iccations: . .
- 1. Radwaste Building, elevation 135'
- 2. Outside the Security fence, along the fence just north of the circulation water pump house (Site Medical Dispensary).
3.0 First Aid / Search and Rescue Group members shall: _ l 3.1 Administer first aid, as necessary. NOIE: If cm tamination is suspected, survey the injured area. If contamination is found, go to step 3.4 ( of this procedure. 3.2 Perform a radiation and contamination survey of the person and subsequently the area. 3.3 Transport the injured person to a Site First Aid , Facility if practicable. i 3.4 Perform the following if contamination is suspected on the injured person. .. 3.4.1 Wear necessary anti-contamination clothing ~IF PRACTICABLE. NOIE: IF THE INJURY IS SEVERE, IMEDIATE MEDICAL
, TREA'IMENT IS OF 'IHE HIGHEST PRIORITY AND RADIOLOGICAL CONTROLS ARE SECONDARY.
3.4.2 Administer appropriate first aid, being careful to limit the spread of contamination and limit personal exposure. . 3.4.3 Prepare the person for transportation by " covering the contaminated area with a protective wrap. 'Ihis may require covering the stretcher and placing the person on the stretcher and wrappino (' , the cover around the person or wrapping the in3ury l in protective wrap. (Avoid excessive wrapping to
.. + - . . .,
.~
EP-207C
-Page 4 ofc6, Rev. 3 g prevent dehydration of the person).
3.4.4 Transport the injured person to the Site First Aid . E Facility for treatment by the Site Physician's Assistant or local physician. NOPIE: If the injured person is going to be transported to an offiste medical facility 2 , it may not be feasible to bring the person to the First Aid Facility, instead move the person to a safe place which is easily accessible for the transfer to a vehicle. 3.5 Recover any ccntaminated articles of clothing that may have been removed from the person for isotopic analysis. 4 4.0 Site Physician's Assistant or his designee shall: 4.1 Provide guidance to the First Aid / Search and Rescue Group as much as practicable through the Personnel Safety Team Leader. - 4.2 Prepare the Site Melical Dispensary or radwaste building (elev.135') first aid facility for receiving injured perscnnel. 4.3 Under directicn of the Emergency Director call the f following offsite agencies for assistance, as necessary: (See EP 209, Appendix N for additional telephone numbers, if needed. Ambulance Service: - Delta-Cardiff Fire and Ambulance Company (Telephone No. 1-452-5111) Hospital-Contaminated Injured Personnel: Harford Memorial Hospital .. (Telephone No. 1-301-939-3575) Hospital-Injured Personnel-No Contamination York Hospital or Harford Hospital NOIE: Nhen contacting offsite agencies, give them the following information. a) Number of injured persons j b) Estimated Time of Arrival (Hospitals only) c) Nature of trauma f- d) Whether individual (s) contaminated or not. - me k. 1
~ + - .... . .
,ye e-
. EP-207C
'Page 5 of.6, Rev. 3 APPENDIX EP 207C-1
- I
- l. FIRST AID /SFARCH AND RESCUE GROUP ,,
I INJURY REPORT FORM
~
(PREPARE IN DUPLICA'IE) l l Inj'ured Person's Name
~ '
Me Harshaw Badge No. or Social Security No. Male Female . Type and locaticn of Injury Radioactive Ccntamination Yes No Level Iccaticn ( Radiaticn Exposure Estimate . Where did injury occur Prepared by First Aid Group Leader Signature Group Members . . t If practicable forward original, with the person, to the * ' Site First Aid Facility or Hospital as appropriate.
- n. -
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, EP-207C
'Page 6 of.6, Rev. 3 APPENDIX EP-207C-2
(?) . t-V FIRSFAID REEA'IED EQUIPMENT IN POWER BIDCK , First Aid Stretchers Kits Blankets
- ~
Unit 2 Rx Bldg Elevator Stairwells 116' Elev X X X 135' Elev X X X 165' Elev X X X 195' Elev X X X 234' Elev X X X Unit 3 Rx Bldg Elevator Stairwells 116' Elev X X X 135' Elev X X X 165' Elev X X X - 195' Elev X X X* 234' Elev X X X Turbine Bldg Elevator 116' Elev X - 135' Elev X 150' Elev X 165' Elev X Turbine Bldg Laundry Room 116' Elev X X X Radwaste Bldg Medical /Decon Room 135' Elev X* X Diesel Gen Bldg (Each Room) X Emergency Cooling Tower X 2SU Switchgear Bldg X 3SU Switchgear Bldg X ,
- 2 Orthopedic stretchers located here.
NOIE: 1/2 mile rays (emergency flashlights) are located just outside door to Unit 2 side of main control room in cabinet.
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pg .j e[g,g 7 SS - SSV All ELECTRIC COMDANY N V;.c Control Ea. .- PEW W7T'IOM INIm9 2 AND 3 Station Saper.. Office GEENCY PIAN IMDLEMENTING 990CErX1RR EP-207D UTACUATICN A9SEMRLY GRorIn - PURPOSE 2 define the actions of the Personnel Safety Team personnel Evacuation Assembly Group. RF5'ERENCES
- 1. Peach Rottom Atomic power Station Emergency plan 9ecticn Title -
6.7.3 Contamination Control Measures 5.2.1. 5.7 Personnel Safety Team 6.7.1.1. 5 Mcnitoring of Evacuees 5.2.1.5.7.3 Evacuation Assembly Groun (
- 2. Health Physics Operating / Chemistry Ooerating Procedures Number Title HPO/CD-5 Selection and use of Anti-Contamination .
Clothina HPO/CO-6 Personnel Contamination Survev Techniques
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HDO/CO-7 Personnel Decontamination Drocedure MPO/CO-8 Decontamination of mools and Equianent HPO/CO-100 Health Physics Guides used in the Control of Exposure to Radioactive Material
- 3. NUREG 0654 Criteria for precaration and Evaluation of Radiological Emergency Response Plans in Runcort of Nuclear Power Dlants.
- 4. EP-207E Vehicle and Evacuee Control Procedure
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- 5. EP-207F Vehicle Decontamination Procedure ADPENDIX _
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* ** EP-2070 , .Paqs 2 of 4, Rev. 3 e
(h ACTION N . g.- . Activate the Evacuation Assembly Grouo whenever the Personnel Safety Team Leader deems their services necessary and the event is classified as an Unusual Event, Alert, Site Emergency or General Emergency.
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PRfrAUTIONS .
- 1. When mcnitoring someone for contamination, do not contaminate the probe by allowing it to came in contact with the person's body, clothing, or hair.
- 2. Personnel Mcnitoring areas should have a background level less than 300 cm and preferably less than 100 cm.
IW4EDIATR ACTIONS - 1.0 Personnel Safety Team Leader shall: 1.1 Assign the necessary members from the Personnel Safety ' Team located at the assembly area to form Evacuation Assembly Groues. 1.2 Apcoint the most qualified person of the group to be the Evacuation Assembly Group Leader and to carry ( out Section 2.0 of this crocedure.
- 1. 3 If necessary, apooint several team members to monitor or decontaminate personnel and vehicles evacuated frm the plant and to the assembly area.
2.0 Personnel Monitoring and Decontamination Group Leader shall: 2.1 Direct the group members to obtain necessarv equip- - ment and supplies for personnel monitoring and decaitamination. (Equiment can be obtained from the Technical Support Center, Emergency Operations Facility, North Substation, PUB, or Delta 9ervice Building. 2.2 Set up a monitoring area as close to the problem area or assembly area as practicable. 2.3 Direct the frisking of personnel. 2.4 Inform the Personnel Safety Team Leader if any one is contaminated. Apoly Guidance of HPO/CD-100 for significant ccntaminaticn. -
- 2. 5 Record ccntaminated person's name and group affiliaticn. -
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- 2. 6 Direct deccntaminaticn as deemed necessary
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EP-2070 Page 3 of 4, Rev. 3 (, in accordance with HPO/OO-6 and 7. - - 3.0 Personnel Monitoring and Decontamination Group Members shall: 3.1 Obtain personnel decontamination equignent, per the Personnel Monitoring and Decontamination _ , Group Leader, for performing monitoring and decontamination operations. 3.2 Proceed to the area designated to be the monitoring area and, using the frisker, take a background contamination level reading. If the reading is greater than 300 can, inform the group leader and await his decision whether to set up the monitoring station in this area or to choose another area with a lower background level. 3.3 Set up a monitoring station:
- 3.3.1 Set up a contamination control point (e.g., step off pad, radiation rope). '
3.3.2 Using rad-tace or rad-roce, set uo boundaries to direct the personnel to the steo-off pad and to control the scread of mntamination. (' 3.3.3 Provide empty containers near the ste W ff pad for receiving contaminated objects. 3.4 Direct the people to be monitored toward the contamination control point. 3.5 Direct each person to remove anti-contamination clothing . using HPO/CO-5 Steo 3.0 as a guide. l 3.6 Frisk the hands of the person to be nonitored. If the' - hands are not contaminated let the person frisk himself, per HPO/CO-6. 3.7 If the person's hands are contaminated, frisk the rest of the body and bottom of shoes. If no other contamination is found, direct the person to put on anti-contaminaticn cotton gloves and to go to one of the decontamination areas listed below. If other parts l of the body are found to be contaminated, direct the person to put on anti-contaminated clothing, as necessary, to prevent the spread of contamination. See HPO/CO-7, Personnel Decontantination. i l Priority for decontamination shall be given to personnel found to have the highest levels of contamination. Any personnel susoected, or known, to have ingested / inhaled radioactivity - ( shall be given a whole ba3y count to assess ,their internal exposure. See HPO/CO.-7, Personnel Decontamination. t l sw -- - * - r M- M e "m-"m-'w--'-- -E- "-'7"-"----- ------'M ~~- - ' " - - r -'--- -
- ' EP-2070
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Paga 4 of 4, Rev. 3 (7,, PERS0hWEL DNTINATICN MAS *
- 1. RADWAS'IE BUILDING, ELEVATICN 135' ' '
- 2. ' PRESIDENT'S UTILITY BUILDING (PUB)
- 3. NOR'IH SUB S'IATION
- 4. DELTA SERVICE BUILDING
- 5. UNIT 1 948:RGENCY CENIER (lST Ff40R).
3.8 Direct personnel to deposit contaminated articles in the, containers provided. 3.9 Direct the personnel who have been frisked and are
" clean" to a clean area. ' Itis may require sending
, pecole home who have evacuated the site. 3.10 Disassemble the contamination control point when the monitoring operations are complete. Seal the containers with rad-tape for later transport to the radwaste building.
. Properly mark containers as to contents and radiation levels. Return monitoring and decontamination equipnent ..
to proper locations. ( 1 l 9 S t
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.. ,4 po_7)n CON. ROLLED APPROVED COPY- Page 1 of 3, Rev 'O VOID EEEVI0sS ISSUL *tth DISTRIBUTION:
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'Ib define the actions of the nose Assessment Wam.
References:
Deach nottom Atomic power Station Emergency plan Section 5.2.1.5.6 and 6.6.1 ED 316 Cumulative Poculation Dose calculations EP 317 Determination of Protective Action Recomendations EP 318 f.iquid Release nose Calculations - Water EP 119 r,iquid Release nose Calculations - Fish Ep ~425 Methodology for tising the Centainment Radiation Monitor Oose Rate vs. Time Curves to Estimate Source Wrm Available for Release EP 209 Acpendix P - 9taffing Augmentation Anoendix: ( EP 205t>-1 tbse Assessment Procedures t. Application Action Level:
'The Dose Assessment Team shall be activated by the Emergency Director.
Imrmdiate Actions: 1.0 Dose Assessment %am Leader shall: 1.1 Upon notification of an alert or above condition, activate team members, assign emergency roles and direct them to recott to mF. 1.2 Droceed to mP (second floor finit' 1) . 1.3 Establish contact with the Rite Pmergency coordinator (or Emergency Director under Alert condition) . 1.4 Initiate calculations as necessary, see Appendix I. 1.5 tipon completion of EP 316 calculations, imnlement FP 317, Determination of Drotective Action Recomendations. 2.0 Dose Assessment W am Members shall:
. . EP-210 page 2 of 3, Rev. 0 2.1 rheck supply of data and work sheets and calculators.
2.2 Establish data acquisition mode; i.e., 'rv monitors
.- or direct link to control room.
- k. .l 2.3 Perform calculations as directed.
2.4 Calculate inteorated and croiected dose and post on status board.
?K7TE: 9tatus Board keeoer will post board and transmit copies of status board data to "MC and HO MSc.
Follow fin Actions: 1.0 Dose Assessment Nam Leader shall: 1.1 Coordinate with the Radiation Protection 'neam Imader to obtain field survey and chemistry samoling and analysis data.
- 1. 2 Keep Emergency nirector, site Emergency Coordinator,
- and Health Physics and Chemistry Coordinator informed of dose projections.
1.3 Establish contact with Pennsvivania nureau of Radiation protection and Maryland Division of Radiation Control reoresentatives in the FJOF and keep these agencies informed. ( l.4 Participate in me briefings and provide current dose assessment and protective action information. 2.0 Dose Assessment %am Members shall: 2.1 Continue to refine calculations as new data becanes available. 6 0 a , e - . - ~ - - . p -- -- - - , , -.,-v.- , - , , - -
- 3 Pagn 3 of 3, Rev. 0
, , DOSE ASSESSM5NI' PRIEnrJRES APPLICATION Inaut Radiological Data Apolicable Procedure
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y. k Normal range EP 316 Manual or
- monitor release rate Ccrnputer Methdd to determine dose High range mmitor EP 316 Manual Method release rate to determine release rate for Manual or Ccrnouter Method Containment rad EP 325 mcrtitor dose rate to estimate release rate for Manual or Ccm: cuter Method Particulate filter and EP 316 Manual or Iodine cartridge Computer Method to data estimate dose. (2) fIse
. Manual Method to determine deoosition concentration.
Field survey - I-131 EP 316 to estimate or cencentration thyroid dose commitment rate. Liquid Release data EP 318 and/or EP 319 as necessary. General Notes:
- 1. Dose Model is crimary calculation method when in operation.
- 2. EP 316 " Rapid" calculations are conservative and assume normal ficw conditions, predetermined wirdspeeds and turbulence classes.
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' - pp_73n CON.BOLLED APIROVED COPY- Daq2 1 of 3, Rev.'O VOID EEEVlags ISSUE .tth DISTRISUTION:
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- Office EP-210 nose Assessment Team Purcose:
'Ib define the actions of the nose Assessment ' ream.
Deferences: Deach nottom Atomic Dower Station Faercency Dlan Section 5.2.1.5.6 and 6.6.1 FP 316 Cumulative PorMlation Dose Calculations EP 317 Determination of Protective Action Recortmendations EP 318 r.iquid Release nose Calculations - Water EP 119 r.iquid Release nose Calculations - Fish EP ~425 Methodology for tising the Containment Radiation Monitor Oose Rate vs. 'Pime Curves to Estimate Source
' Nrm Available for Release EP 209 Aapendix P - 9taffing Augmentation Anoondix:
EP 2050-1 Dose Assessvent Procedures & Application Action Level:
'The Dose Assessment Team shall be activated by the Emergency Director.
Immediate Actions: 1.0 Dese Assessment ' ream I4ader shall: 1.1 Upon notification of an alert or above condition, activate team members, assign emergency roles and direct them to recort to mF. 1.2 Proceed to mP (second floor ITnit 1) . 1.3 Establish contact with Gw Site Emercency coordinatcr (or Emergency Director under Alert Condition) . 1.4 Initiate calculations as necessary, see Appendix I. 1.5 Upon completion of EP 316 calculations, imnlement EP 317, Determination of Drotective Action Recommendatims. O 2.0 Dose Assessmene 'r eam Memsere she11:
' EP-210
. Pagn 2 of 3, Rev. 0 2.1 check supply of data and work cheets and calculators.
2.2 Establish data acquisition mode; i.e., 'N monitors en or 6irect link to control room. G 2.3 Perform calculations as directed. 2.4 Calculate intearated and orojected dose and post on status board. NOIT.: 9tatins Board keeoer will post board and transmit copies of status board data to '"T and MO ESC. Follow Up Actims: 1.0 Dose Assessment Nam Leader shall: 1.1 Coordinate with the Radiation Protection W am Leader to obtain field survey and chemistry samoling and analysis data. - 1.2 Keep Emergency Director, Site Emergency Coordinator, and Health Physics and Chemistry Coordinator informed of dose projections. 1.3 Establish contact with Pennsvivania Rureau of Radiation protection and Maryland Division of Radiation control reoresentatives in the EF and keep these agencies informed. ( l.4 Participate in FDP briefings and provide Current dose assessment and protective action information. 2.0 Dose Assessment %am Members shall: 2.1 ccntinue to refine calculations as new data beccmes available, aw . 9 O
s.
, Paqs 3 of 3, R:;v. 0 DOSE ASSESSMEm' P90CEntJRES APPLICATICN g Incut Radiological Data Apolicable Procedure C
k.% ' Normal range EP 316 Manual,or mcnitor release rate Ccrnputer Method to determine dose High range ntnitor EP 316 Manual Method release rate to determine release rate for Manual or Comcuter Method Containment rad EP 325 7' mcnitor dose rate to estimate release ratt for Manual or Comouter Method Particulate filter and EP 316 Manual or Iodine cartridge Computer Method to data estimate dose. (2) rise s Manual Method to *
' determine demsition concentration.
Field survey - I-131 EP 316 to estimate er cencentration thyroid dose conmitment rate.
' Liquid Release data EP 318 and/or EP 319 as necessary.
s General Notes:
- 1. Dose Model is crimary calculation method when in operation.
- 2. EP 316 " Rapid" calculations are conservative and assume normal flow conditions, predetermined windspeeds and turbulence classes.
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