ML20027D197
| ML20027D197 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/30/1982 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18087A543 | List: |
| References | |
| PROC-820930-01, NUDOCS 8211030073 | |
| Download: ML20027D197 (232) | |
Text
{{#Wiki_filter:- No. 108 U.S. NRC, Dir. of NRR Washington, D.C. 20555 Mr. S.A. Varga, Chief, Oper. Reactors BRil, Div. of Licensing SALEM GENERATING STATION EMERGENCY PLAN EMERGZNCY PLAN PROCEDURES INDEX SEPTEMBER 30, 1982 SECTION I - ON-SITE PROCEDURES REV. NO. EP I-0 Accident Classification Guide . . . . . ................. 2 Fart 1 Radiological - Part 2 Operational Part 3 Fire / Natural / Security Part 4 Miscellaneous Flow Chart ...... . ........................ 0 EP I-1 Notification of Unusual Event /Significant Event . ............ 2 FP I-2 Alert . . . ..... . . ........................ 2 EP I-3 Site Area Emergency . . . ........................ 2 EP I-4 General Emergency . . . . ........................ 2 EP I-5 Personnel Emergency . . . ........................ 1 EP I-6 Radioactive Spill . . . . ........................ 1 EP I-7 Station Fire .... . . ........................ 1 EP I-8 Personnel Accountability ........................ 1 EP I-9 Search and Rescue Operations . . . . . ................. 1 FP I-10 Conducting an Inventory of Emergency Equipment ............. 1 EP I-11 Communications Equipment ........................ 1 EP I-12 Site Evacuation . . . . . ........................ 1 EP I-13 Post Accident Low Pressure Injection Monitoring . ............ I EP I-14 Initiation of Recovery Operations . . . ................. 1 b EP I-15 Stable Iodine Thyroid Blocking . . . . ................. 1 EP I-16 Peca11 of Evacuated Site Personnel . . ................. 1 EP I-17 Radiation Protection - Emergency Action . . . .............. 1 EP I-18 Operations Support Center Activation . ................. 1 EP I-19 Activation / Evacuation of the Technical Support Center . . . . . . . . . . 1 SECTION II - OFF-SITE PPOCEDURES EP II-1 Emergency Reeponse Manager Preparation to Assume Responsibilities . ... 1 EP II-2 Site Support Manager Preparation to Assume Responsibilities . . ..... 1 EP II-3 Radiological Support Manager Preparation to Assume Responsibilities . .. 1 EP II-4 Notification of Corporate Emergency Response Personnel . . ....... 1 EP II-5 Emergency Paging of Corporate Emergency Response Personnel ....... 1 EP II-6 Of f-Site Administrative Support . . . . .............'.... 1 EP II-7 Testing of Emergency Procecure EP II-4 ................. O
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B211030073 821014
.PDR F ADOCK 05000272 1 f3 Rev. 4 l PDR 1
_- .m_ _ _ _ _ , - - ~ ~ _ . - - . - - _ . - _ . . . - - - . - _ - - , - . . _ _ - - . - - - - - - - - -
SECTION III - SECURITY EMERCENCY PROCEDURES REV. NO. PP III-l Opening of the Technical Support Center . . . . . . . . . . . . . . . . . 0 EP III-2 Opening of the Emergency Operations Facility .............. 0 i EP III-3 Personnel Accountability ........................ O FP III-4 Site Evacuation - Security Support ................... O EP III-5 Emergency Vehicle Support . ....................... O SECTION IV - RADIATION PROTECTION /CNEMISTRY EMERGENCY PROCEDURES EP IV-101 TSC Initial Response . . ........................ 1 EP IVe102 Control Room Initial Response . ..................... 1 EP IV-103 Control Point Initial Response ..................... 1 EP IVe104 TSC Evacuation . . . . . ........................ 1 EP IV-105 Control Point and Equipment Evacuation ................. 1 EP IV-106 ALARA Task Review and Emergency Exposure Authorization ......... 1 EP IV-107 Radiation Monitor Evaluation ...................... 1 ] EP IV-108 Frotective Action Recommendations . . .................. 2 EP IV-109 Plume Tracking by Helicopter ...................... 1 EP IV-110A Field Monitoring by TSC ........................ 2 (
\
FP IV-110B Field Monitoring by EOF EP IV-111 Effluent Dose Calculations O 2 EP IV-112 Emergency Operations Facility - Radiological Assessment . ........ 0 EP IV-113 Computerized Dose Calculations ..................... 2 EP IV-114 Computerized Dose Calculations on Programmable Calculator . ....... 0 EP IV-115 Personnel and Vehicle Survey ...................... 1 J EP IV-ll6 Fire Brigade Escort . . . ........................ 1 EP IV-Il7 Re-Entry Team Radiation Protection ................... 1 EP IV-ll8 Righ Activity Sample Analysis . ..................... 2 EP IV-119 Personnel Decontamination . ....................... 1 EP IV-120 Equipment Decontamination . . . . . . . . . . . . . . . ......... 1 EP IV-121 Containment Atmosphere Remote Sampling ................. 1 EP IV-122 Emergency Staffing Guide ........................ 1 EP IV-201 Radiation Protection Senior Supervisor Response . ............ 1 l EP IV-202 Chemistry Senior Supervisor Response .................. 1 EP IV-203 Administrative Assistant Response . ................... 1 EP IV-204 Short Term Environmental Response . ................... 1 EP IV-205 Material and Instruments Supervisor Response .............. 1 FP IV-206 Dosimetry-Counting Room Supervisor Response . .............. 1 , EP IV-207 Rad Waste Supervisor Response . ..................... 1 EP IV-208 Dose Assessment - ALARA Supervisor Response . .............. 1 EP IV-209 In-Plant Supervisor Response ...................... 1 EP IV-210 Procedures-Training Supervisor Response . ................ I h EP IV-211 Radiation Protection Communications Cuide . ............... 1 EP IV-212 Radiation Protection Emergency Inventory Control ............ 1 EP IV-301 Interim Post Accident Primary Coolant Sampling ............. 2 EP IV-302 Emergency Sampling Procedure for the Plant Vent . ............ 1 2 of 3 Rev. 4
SECTION V - ENGINEERING DEPARTMENT EMERGENCY PROCEDURES REV. NO. EP V-1 Notification of Engineering and Construction Department . ........ 0 EP V-2 Corporate Engineering Support Manager Response (CHERC) ......... O FP V-3 Site Engineering Support Manager Response (EOF) ............. O FP V-4 Corporate Engineering Team Leader Response (CHERC) ........... 0 1 EP V-5 Corporate Quality Assurance Department Response (CHERC) ......... O EP V-4 Site Ouality Assurance Department Response (EOF) ............ 0 EP V-7 Site Engineering Team Leader Response (TSC) ............... O EP V-8 Methods De83rtment & Engineering Department Divisional Representatives Responr" fCHERC) . . . ........................ O SECTION VI - PLAN ADMINISTRATION EP VI-l Revision and Approval of Plans and Procedures . ............. 1 EP VI-2 Distribution of Plans and Procedures .................. 0 EP VI-3 Review of Plans and Procedures ..................... 0 EP VI-4 Procedures Format . . . . ........................ O EP VI-5 Conduct of Drills and Exercises . . . . . . . . . . . .......... 1 i SFCTION VII - PUBLIC INFORMATION t EP VII-l Public Information Notification . ............-......... O FP VII-2 General Manager - Information Services Response . ............ O EP VII-3 Public Information Manager Response . .................. 0 EP VII-4 Public Information Technical Liaison Response . ............. 0 EP VII-5 Public Information Technical Assistant Response . ............ O EP VII-6 Internal Information . . ........................ 0 EP VII-7 Media Relations . . . . . . . . . . . . . . . . . . . .......... O EP VII-8 Emergency News Center Activation /Pulbic Information Coordinator Re sponse . . . . . . . ........................ O ADDFNDUM Addendum 1 Master Phone List . . . ........................ 3 Addendum 2 Supplementel Station Status Checklist ................. 1 FICUPES Figure 1 EDO Checklist . . . . . . ........................ 1 Figure 2 Communications / EOF Manning Board .................... 1 Figure 3 Operational Status Board ........................ 0 Figure 4 Post Accident RMS Assessment Data . ................... 1 O Figure 5 Area / Process RMS Data . . ........................ O rigure 6 offsite Dose Summary . . ........................ 0 3 of 3 Rev. 4
EP IV~108 EMERGENCY PROCEDURE EP IV-108 PROTECTIVC ACTION RECOMMENDATIONS ACTION LEVEL Declaration of an emergency at the Alert level or higher. , RESPONSIBLE INDIVIDUAL The Radiological Support Manager (RSM) has overall responsibility for this procedure. Until the RSM is operational at the EOF, the requirements of this procedure may be met by the Shift Radiation Protection Technician or the Dose Assessment /ALARA Supervisor under the direction of the Radiation Protection Engineer. , NOTE () Only the individual with the emergency coordinator function may make the decision to notify state and local authorities of off-site Protective Action Recommer.dations. ACTION STATEMENTS
- 1. The Senior Shift Supervisor /EDO, upon determination that a radiological incident is in progress, shall contact the Shift Radiation Protection Technician or the Dose Assessment /
ALARA Supervisor to initiate dose assessment.
- 2. Dose assessments shall be calculated based on data supplied by the plant effluent monitors and measured data from the field teams. This l calculation shall be performed by the Shift Radiation Protection Technician in the TSC or
/N by the RSM in the EOF when the EOF is l U operational.
I 1 of 27 Re v. 2
m 6
\
EP IV-108 () ACTION STATEMELt.
- 3. The dose rates or projected doses shall be compared to l the Protective Action Recommenda-tions (Attachment 1),and the Evacuation Time Estimates for' areas near the site (Attachment 3). Additional' predetermined criteria for protective action are presented in Attachment 4.
- 4. The RSM or the Dose Assessment /ALARA Super-visor shall provide the Senior Shif t Supervisor /EDO with Protective Action Recommendations prior to activation of the EOF. The RSM shall provide protective action l recommendations to the Emergency Response Manager when the EOF is activated.
O ATTACHMENTS
- 1. Off-Site Protective Action Recommendations For The Public
- 2. Emergency Wbrker Exposure Criteria
- 3. Evacuation Time Estimates
- 4. Predetermined Protective Action Recommendations l NOTE Fo rwar ! .;, p?.eted forms to the Nuclear Emergency Planning Enginecr. Attach other completed EP's or attachments used.
s_ [ x 2 of 27 Rev. 2
EP IV-108 Signature Page Prepared By: .b Reviewed By: - [ /d TW [' Department Head Date Reviewed By: ] qa P-/o-T 3-- Nuclea[ Emergency Planning /E ngineer Date l Reviewed By: 93h StationOualityks 'rance Review 'Date (if require 'ee EP VI-SORC Meeting No.: ' M M f ~
, bate l Approved By: /[(7 I f/>3/ V General Managdr - Salem Operations Date' l Approved By:
9 J [Z_ Manager - Nuclear Site Protection Date l 1 l { O 3 of 27 Rev. 2
O O O ~ EP IV-108 Attachment 1 OFF-SITE PROTECTIVE ACTION RECO!!MENDATIONS (PAR) GUIDELINES FOR TIIE PilBLIC T. IF RELFASE DTIRATION CAN BP PREDICTED WIIOLE BODY TilYROID PAR DOSE DOSE Children & Women (millirem) (millirem) Adults of child bearing age
<500 <3000 NONE NONE ,
500-1000 3000-5000 SilELTER *
- SIIELTER*
- 1000-5000 5000-25000 SilELTER EVACUATE ***
>5000 >25000 EVACUATE EVACUATE a
o t II. IF RELEASE DURATION CANNOT BE PREDICTED
- l N WilOLE RODY TIIYROID DOSE RATE DOSE RATE Children & Women (millirem /hr) (m illirem/hr ) Adults of child bearing age
<125 <750 NONE NONE 125-250 750-1250 SiiELTER*
- SilELTE R *
- 250-1250 1250-6250 SIIELTER EVACUATE ***
>1250 >6250 EVACUATE EVACUATE '
NOTES.
- D0SE PATE PAR's assume 4 hour integrated dose with 2 hours response time and 2 hour minimum evacuation time. These must he reevaluated periodically. l Protective action is not required at these levels, however, states may issue an i advisory to seek shelter and await further instructions.
W Pecommendation to evacuate must also be based on environmental (e.g., weather, etc.) :p !
$ and other af fecting conditions. ,
g su N O m D tt H
9 EP IV-108 O'sj Attachment 2 ATTACHMENT 2 EMERGENCY WORKERS EXPOSURE CRITERI A WARNING CRITERIA ARE FOR RADIATION EXPOSURE TO VOLUNTEERS ONLY. EMERGENCY EXPOSURE AUTHORIZATION REQUIRED, EXPOSURES ARE TO BE "ONCE IN A LIFETIME". LIFE-SAVING NON-LIFE-SAVING Authorized Exposure: 75 rems Authorized Exposure: 25 rems whole body whole body O Any and all actions necessary to Repair or operation of equipment save or preserve life, including necessary to mitigate a situation but not limited to: which has or may have the potential to cause projected off-site doses which would require Removal of injured personnel protective action. First Aid Personnel decontamination Corrective actions necessary to Ambulance services prevent plant safety status from Medical treatment further deteriorating or to effect significant improvement in plant safety status. Corrective actions necessary to cause significant reductions in in-plant radiological hazards. 5 of 27 Rev. 2
EP IV-108 O Attachment 3 ! ATTACHMENT 3 O EVACUATION TIME ESTIMATES for Areas Near the Site of: SALEM AND HOPE CREEK i NUCLEAR GENERATING STATIONS prepared for , PUBLIC SERVICE ELECTRIC AND GAS COMPANY prepared by PAPFONS BRIFCFFPPOFF QUADE & DOUGLAS, IMC. O February 27, 1981 6 of 27 Re v. 2
Attachment 3 TABLE 1 RELATIONSHIP BETWEEN EVACUATION SECTIONS AND EVACUATION PLANNING AREAS EVACUATION' SECTIONS EVACUATION PLANNING AREAS A 1 B 1, 3, 15, 17 C 1,2,3 D 1, 3, 4, 5, 15, 17, 19 E 1, 2 , 3,5,6,7 F 15 G 8, 9, 15, 16 H 9, 10, 15, 17 I 8, 9, 12, 13, 15, 16, 18 J 9, 10, 11, 12, 14, 15 K 1, 15 L 1, 2, 3, 8, 9, 10, 15, 16, 17 M 1 through 19 O 7 of 27 Re v . 2
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- 4 180 Section F g Sa!em Generating Stations Hope Creek Generating Stations I
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-; . ~ . .. _ .. EP IV-108 E ATTACHMENT.3 i
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,l Planning Areas . Evacuation Time Estimates Figure 14 360* Section L
$- Salern Generating Stations Hope Creek Generating Stations Rev. 2 19 of 27
EP IV-108 ATTACHMENT 3 M / '
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l Rev. 2 20 of 27
O O O TABLE 2 SALEM /IIOPE CREEK NUCLEAR GENERATING STATIONS EVACUATION TIME ESTIMATED (1)
(NIGilT SCENARIO)
TRAVEL TIME FOR TOTAL EVACUATION TIME (2) SPECIAL EVACUATION NOTIFICATION TIME GENERAL POPULATION FOR GENERAL POPULATION FACILITIES (3)
SECTION IIOURS : MINUTES WITil AUTO WITIIOUT AUTO WITil AUTO WITIIOUT AUTO SCllOOL OTilERS(4)
A : 05 :20 --
- 45 -- -- --
R : 45 :35 --
1:40 -- --
2:45 C : 45 :35 1:35 1:40 2:40 -- --
D : 45 :35 1:50 1:40 2:55 --
2:45 E : 45 3:05 4:10 2:10 -- --
1:25 P : 45 -- -- -- -- --
2:05 G : 45 :20 --
1:25 -- --
2:20 o
m II : 45 :25 2:15 1:30 3:20 --
2:20 I : 45 :50 2:25 1:55 3:30 --
3:30 J : 45 :45 2:55 1:50 4:00 --
2:05 K : 45 :20 --
1:25 -- --
2:05 L : 45 :35 2:15 1:40 3:20 --
2:20 M : 45 3:05 4:10 4:10 5:15 --
3:30
- Site Emergency
- 45 3:05 4:10 4:10 5:15 --
3:30 (1) Table revised from original report (2-22-81) to reduce notification tirae as per NUREG 0654 and current notification capabilities.
(2) Includes general population mobilization time of 20 minutes.
$ (3) Includes dispatch time, loading time, an roadway travel time where applicable. $
4 (4) Special Facilities in Sections B, D, F, G, II , J include Delaware River and Delaware Bay.
0 For O special facilities other than the river and the bay, it is assumed that notification will occur $
within 15 minutes and that mobilization and evacuation will begin immediately thereaf ter. @
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I
O O O TABLE 3 SALEM /ITOPE CREEK NUCLEAR GENERATING STATIONS EVACUATION TIME ESTIMATES (1)
(DAY SCENARIO)
TRAVEL TIME FOR TOTAL EVACUATION TIME (2) SPECIAL EVA Ctl ATION NOTIFICATION TIME GENERAL POPIILATION FOR GENERAL POPULATION FACILITIES (3)
SECTION HOllPS : MINIITES WITII AUTO WITiiOUT AUTO WITil AUTO WITIIOUT AUTO SCIIOOL OTilERS A : 05 2:10 --
2:35 -- -- --
B : 45 2:15 --
3:20 --
- 30 2:20 C : 45 2:15 2:40 3:20 3:45 :30 --
D : 45 2:35 1:50 3:40 2:55 1:45 2:45 E : 45 3:50 5:10 4:55 6:15 4:45 1:25 P : 45 -- -- -- -- --
2:05 G : 45 :20 --
1:25 -- --
2:20
" II : 45 :25 2:15 1:30 3:20 --
2:20 S I : 45 1:50 3:15 2:55 4:20 2:00 3:30
" J : 45 1:40 3:30 2:45 4:35 2:10 2:05 K : 45 2:10 --
3:15 -- --
2:05 L : 45 2:15 2:40 3:20 3:45 :30 2:20 M : 45 3:50 5:10 4:55 6:15 4:45 3:30 Site Emergency : 45 3:50 5:10 4:55 6:15 4:45 3:30 (1) Table revised from original report (2-27-81) to reduce notification time as per NUREG 0654 and current notification capabilities. l (2) Includes general population mobilization time of 20 minutes.
- o (3) Includes dispatch time, loading time, an roadway travel time where applicable. $
" if a
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O O O TABLE 4 SALEM /IIOPE CREEK NUCLEAR GENERATING STATIONS EVACUATION TIME ESTIMATES (l)
(ADVERSE WEATilER CONDITIONS)
TRAVEL TIME FOR TOTAL EVACUATION TIME (2) SPECIAL EVACIIATION NOTIFICATION TIME GENERAL POPULATION FOR GENERAL POPULATION FACILITIES (3)
SECTION IIOURS : MINUTES WITII AUTO WITIIOUT AUTO WITil AUTO WITIIOUT AUTO SCIIOOL OTilERS(4)
A : 05 3:30 --
4:15 -- -- --
B : 45 3:40 --
4:45 --
- 30 2:20 C : 45 3:40 3:30 4:45 4:35 :30 --
D : 45 3:55 2:40 5:00 3:45 1:40 2:45 E : 45 6:20 7:40 7:25 8:45 7:15 5:05 F : 45 -- -- -- -- --
2:05 U G : 45 :20 --
1:25 -- --
2:20 R II : 45 :25 2:15 1:30 3:20 --
2:20 w I : 45 2:55 4:30 4:00 5:35 2:50 4:25 J : 45 2:30 4:25 3:35 5:30 2:55 2:05 K : 45 3:30 --
4:35 -- --
2:05 L : 45 3:40 3:30 4:45 4:35 :30 2:20 M : 45 6:20 7:40 7:25 8:45 7:15 5:05 Site Emergency : 45 6:20 7:40 7:25 8:45 7:15 5:05 (1) Table revised from original report (2-27-82) to reduce notification time as per NUREG 0654 and l current notification capabilities. l (2) Includes general population mobilization time of 20 minutes.
$ (3) Includes dispatch time, loading time, and roadway travel time where applicable. E 4
(4) Special Facilities in Sections B, D, F, G, II, J include Delaware River and Delaware Bay. For $
special facilities other than the river and the bay, it is assumed that notification will occur [
a within 15 minutes and that mobilization and evacuation will begin immediately thereafter. $
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1 i
I EP IV-108
() Attachment 4 ATTACHMENT 4 PREDETERMINED PROTECTIVE ACTION RECOMMENDATIONS DIRECTIONS: If any of the following cases occur, immediately convey the protective action recommendations as required to State / County officials via the " Initial Contact Message Form: (Attachment No. 1 of EP I-4). These recommenda-tions shall be made in parallel with that which may have already been made in accordance with Attachment 1 of this procedure. Cases I through IV consist of probable combinations of 2 or more fission product ,
boundary failures (Core, RCS, Containment failure).
The specific plant conditions indicating these failures are:
DEGRADED CORE A. 5 or more core exit thermocouples indicate greater than 1200*F 9E B. 2 or more wide range hot leg RTD's indicate greater than 700*F AND C. One of the following:
- 1) Rapidly diverging 4 T 9E
- 2) No 4 T(Th-Tc = 0) 9E
) 3) R - 31A or 31B Of fscale 24 of 27 Rev. 2
EP IV-108 Os Attachment 4 LOSS OF CONTAINMENT INTEGRITY A. Containment H2 concentration greater than 4%
93 B. Indication of Containment pressure greater than 47 psig and increasing (2/4) 93 C. The following:
- 1) Indication of Containment pressure greater than 23.5 psig and increasing (2/4)
AND i
() 2) There are less than 3 Fan Coil Units available, with only 1 Containment Spray train capability l
OR i
i
- 3) There are less than 5 Fan Coil Units available, with no containment spray train capability 1
l l
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l 1
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25 of 27 Re v. 2 i
---- . - . . .. ,,- -,-- ,. -,_.-- -.. , ,, .-,n.- . - . - - . - - . - . - . - - _ . - . - , - . , . . - - - . . . - , , - - - - - - - -
EP IV-108 O Attachment 4 LOSS OF COOLANT A. R-21 indicator greater-than 20 R/HR, and 2 of 4 of the below listed monitors reading offscale:
- 1) R2
- 2) R7
- 3) R10A
- 4) R10B 93 B. Inadequate sub-cooling, as indicated by P-250 strip-chart recorder or manual calculation and the plant in model 1, 2, or 93 C. Potential, Unisolatable steam line break outside of containment with indication of a primary to secondary leak in the affected generator.
23 D. Either of the following:
- 1) 2 out of 5 Fan Coil Unit Drainage Alarms Actuate SE
- 2) Indication of Containment pressure greater than 4.0 psig (2/4)
AND BOTH OF THE FOLLOWING:
- 3) Containment Sump level greater than 81'3" O AND
- 4) There is no indication of an In-containment steam line break 26 of 27 Rev. 2
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EP IV-110-A'
[ h EMERGENCY PROCEDURE knd/ EP IV-110-A FIELD MONITORING COORDINATED BY TSC ACTION LEVEL When requested by the Senior Shift Supervisor /EDO.
RESPONSIBLE INDIVIDUAL A. Radiation Protection Technician.
LIMITS OF AUTHORITY
- 1. Exposure in exccas of 10CFR20.101 shall be approved in accordance with EP IV-106.
- 2. Re-entry into areas with suspected dose rates >100 mR/hr shall be approved by the Radiation Protection Engineer / Senior Shift Supervisor /EDO.
t
- 3. Change-out of the air samples or TLD's at the environmental monitoring stations requires the approval of the Radiation Protection Engineer and Maplewood Research and Test Lab. l
- 4. Issuance of Potassium Iodide (KI) tablets requires the approval of the Senior Shift Supervisor /EDO.
l ACTION STATEMENTS
- 1. Upon the request to initiate an Emergency Radiation Survey obtain and record the following information (from the Control Room Liaison):
a) Wind Direction (towards)
() (from) 1 o f 41 Rev. 2
EP IV-110-A ACTION STATEMENTS (continued) b) Areas or locations to be surveyed:
c) Plant conditions which may affect the safety of the survey team or the survey results.
d) Enter team composition on Attachment 1,
" Emergency Team Assignments".
- 2. Provide the TSC with the names of the team members assembled at the Control Point.
l O
{ 3. Log each team member's name, badge number, dosimeter number, and dosimeter reading on the Dosimeter Log (re-zero dosimeters if necessary). Record the dose, time, and date on each Dosimeter Card. Any subsequent dosimeter resets should be recorded on the Dosimeter Card and Dosimeter Log (Attachment 2).
- 4. Field survey teams (s) will be dispatched to appropriate locations by a radio communicator within the TSC.
- 5. Quickly brief the team leader on the incident and provide him/her with the following information from Step 1.
a) Wind direction from (meter reading +180' =
l
() direction toward).
2 of 41 Re v. 2
- - _ . . . . - . _ ~ ._ . _ . . . _ .
, EP IV-110-A ACTION STATEMENTS (continued) b) Areas or locations to be surveyed.
c) Plant conditions which may affect the safety of the survey team or the survey results.
- 6. If it is suspected that the survey team will be i exposed to significant quan>ities of radio-iodine, see Procedure'EP I-15 for use of stable iodine.
NOTE Approval of the Senior Shift Supervisor /EDO, acting on advice from the Radiation Protection Engineer must be obtained prior to distribution of Potassium Iodine (KI) tablets.
- 7. Ensure each team member has adequate protective j clothing as required for the specific situation.
i 3
- 8. Assign a name to each team before dispatching vehicles. Use numbers for Field Team designations (e.g., team one, team two, etc.). Keys for vehicles are located in the Administration Building and the TSC. A key for the Emergency Van is also located at i
l the Control Room.
s
- 9. If the assigned vehicle is not equipped with
- emergency equipment, obtain the necessary materials s
from one of the following locations:
( \1 )
! a) Control Point '
i -
b) TSC )
c) Emergency Van d) EOP 1
, l O
3 of 41 Re v. 2 9 _ .. ,
3
ACTION STATEMENTS (continued)
NOTE The minimum items required include:
- 1. Air Sampler
- 2. Dose Rate Meter
- 3. Count Pate Meter
- 4. SAM-2 or equivalent counting equipment (every g 3 team need not have a SAM-2)
- 5. Particulate Filters
- 6. Charcoal or Silver Zeolite Cartridges
- 7. '.'ommunications Equipment (if not in vehicle)
- 10. Dispatch each survey team to the appropriate survey vehicle. Perform a communications check between the vehicle, control point and the TSC.
O NOTE If the vehicle is not radio-equipped, instruct the team to obtain a portable radio from security at the Main Gate.
- 11. While one team is performing the radio communications check, the other team member sf.ould be performing an operational check of all emergency equipment. If the emergency equipment kit is equipped with a SAM-2 assay meter, set up instrument for warm-up and stabilization as per instructions (see Attachment 4 for instrumentation instructions).
- 12. Proceed to the first survey location (Attachment 5
, contains maps and directions to some sites which may be used). Insure the team is continuously monitoring O .
l L 4 of 41 Rev. 2 l
l
EP IV-110-A
() ACTION STATEMENTS (continued) the radiation levels with a Beta / Gamma Survey
- instrument. Document the survey results on the Survey Maps and/or the Emergency Survey Log (Attachment 3). Inform the TSC of any significant fluctuations in the survey results.
- 13. Upon arrival at the first survey location, initiate an air sample. Record the start times and the i
initial flow rate on the Emergency Survey Log.
I Specific instructions on surveys to be performed will be provided to the team from the Control Point or TSC. r
- 14. Special consideration should be given to current O meteorological conditions when directing the field monitoring teams for plume tracking. This is especially necessary if wind speeds at Artificial 4
Island are less than five miles per hour, for frequent wind shifts, if inversion conditions exist, or if back-up meteorological data is used from the Wilmington Airport or some other off-site facility.
f Field teams should await instructions from the i
radio communicator at the TSC or EOF (if activated) regarding plume tracking.
i l
l NOTE i The maximum flow rate is 2 SCFM for charcoal and 2 SCFM for Silver Zeolite cartridges.
t O
5 of 41 Re v. 2
( ACTION STATEMENTS (continued)
- 15. During the collection of the air samples, monitor the radiation levels and record the results on the Emergency Survey Log. Inform the TSC of the survey results while waiting for the air sample to finish collecting.
- 16. Refer to Section V of the Instrument Instruction (Attachment 4) for the operation of the SAM-2.
Perform Steps 6 through 8g.
i
- 17. Upon completion of the air sample collection, count the samples per Steps 8k - 9 of the SAM-2 operational instructions (Attachment 4). Document the results on the Emergency Survey Log. All samples shall be labeled with pertinent information and retained for future analysic. Remain in plume only to collect Os sample and perform surveys. Count samples in as low a background as possible.
NOTE Samples should be checked for excessive dose rates. All samples with a dose rate greater than than 100 mR/hr should be stored in a remote, shielded corner of the vehicle.
- 18. Inform the TSC of the survey and air sample results.
- 19. For counting of charcoal or zeolite cartridges, repeat Steps 8j - 10 of the SAM-2 instructions (section V of Attachment 4) for each survey location.
6 of 41 Rev. 2
EP IV-110-A i ACTION STATEMENTS (continued)
- 20. If the radio shou d fail, see the Communications Section of this procedure (directly before signat ure sheet) for phone number of the TSC, Control Point, EOF and Control Foom.
- 21. Upon completing the assigned survey request additional instructions from the TSC. If surveys are to be terminated:
a) Log each team member's final dosimeter reading, the return time and the net exposure on the Dosimeter Log and the Dosimeter Cards.
b) Inform the TSC that the team is back on-site.
c) Direct the team to return the equipment to the proper storage locations.
, d) If appropriate, have the air samples analyzed for isotopic content.
- 22. Debrief the TSC on the survey results.
ATTACHMENTS
- 1. Emergency Team Assignments
- 2. Dosimeter Log
- 3. Emergency Survey Log Sheet
- 4. Instrument Descriptions
- 5. Survey Locations and Maps COMMUNICATIONS SSS TSC Control Room 1 Control Room 2 Control Point EOF-(RSM)
Radio Radio No un.- No I ~~'
l k D ..
- (; ::f =:
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[ W. --
;,l
; extensions on ,7lcc ; . .f 7 of 41 Rev. 2 i
EP IV-110-A Prepared By: #d/
Reviewed B --' fa f 7-
. [ Department Head Date Re iewed By: [ of b # I 9- / d-ft'--
Nuclear E k ency Planning Eng[neer Date Reviewed By: M I Station Ouality Ashd 'nce Review Date SORC Meeting No.: f O /
[ ate /
Approved By: // 8,904 2t w 9/b3/W General M'anagbr - Salem Operations Date O Approved By:
Manager - Nuclear Site Protection 9,
Date N 8 of 41 Rev. 2
9 i
EP IV-110-A
/s\
Nj ATTACHMENT 1 EMERGENCY TEAM ASSIGNMENTS TEAM CODE TEAM MEMBERS ORIGINAL ASSIGNMENT TIME OUT TIME IN ONE OR ALPHA TWO OR BRAVO O
- THREE OR DELTA l FOUR OR FOXTROT DENOTES TEAM LEADER l
l
(N, V
9 of 41 Rev. 2 l
l
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EP IV-110-A ATTACFMENT 3 l
,,_ EMEPGENCY SURVEY LOG SHEET f P._ 3 DFSIGNATION t
TEAM MEMBERS:
INSTRUMENT SERIAL NUMBERS:
TFLETFCTOP PRM-4 RADECO PIC-6 E-520 P O-2 SAM-2 SIP SAMPLF CALCULATION pCi/cc = Net Counts _Per_ Minute _
(cuoic teet)(2.832 x 104 cmJ/ftJ)(2.2 x 100 dpm/pC1)(Detector EFF)
TYPE OF FILTFR (P) (SZ) (C) (P) (SZ) (C) (P) (SZ) (C) (P) (SZ) (C)
LOCATION GAMMA DOSE FATF cA DOSE RATE SAMPLF DATE SAMPLF START TIME SAMPLE STOP TIME 4t AVG. FLOW RATE l VOLUME (ft3) 1 COUNT DATE l COUNT TIME NCDM*
fEFF = DPM l
2.2 x 106 = pCi
#t3 = pCi/ft3 j _.832 x 104 = pCi/cm3
- NCPM = Gross CPM - Background CPM at Analysis Location.
P = Particulate, SZ = Silver Zeolite, C = Charcoal l Rev. 2 l 11 of 41 l
~~
l l
EP IV-110-A O ATTACHMENT 4 INSTRUMENT OPERATION INSTRUCTIONS I. OPERATION OF RO-2 (JUNO TYPE ION CHAMBER) SURVEY METER A. DESCRIPTION The Eberline RO-2/RO-2A is a 3" diameter air filled ion-chamber survey meter. It has four linear ranges; RO-2: 0-5, 0-50, 0-500 and 0-5,000 mR/hr; RO-2A: 0-50, 0-500 ml/hr and 0-5, 0-50 R/hr.
The RO-2 and RO-2A utilize 3 and 4 NEDA 1604 (9 volt) batteries respectively. Its energy response is linear from 0.05 MeV to 6 MeV and can be operated in a temperature range of -40*F to +140*F. The detector's outer wall is 200 mg/cm2 and the inner wall is 7 mg/cm2 ,
B. GENERAL INSTRUMENT CHECKOUT
- 1. Turn the function switch to BATT 1 and then to BATT 2 positions.
O The meter should read above the BATT cutoff line in both cases.
- 2. Turn the function switch to ZERO position. Check that the meter reads zero. If not, set it to zero with the ZERO knob. (The zero setting of the instrument may be checked in any radiation field by merely selecting the ZERO position.)
- 3. Set the function switch to the desired range of operation. Wait 10 seconds for full meter response. The switch position selected is the full scale reading of that range. ,
~
C. TO PERFORM A DOSE RATE SURVEY
- 1. When measuring beta or low energy gamma or X-ray emissions, cpen the sliding beta shield on the bottom of the case and face the bottom of the instrument toward the radiation source. To open or close'the shield, depress the friction release button on the left
() side of the case and manually move the slide or let it fall due to gravity. When the shield is open, protect the thin face against l damage. -
12 of 41
l EP IV-110-A
() Attachment 4
- 2. Hold RO-2 waist level (approximately 1 meter above ground).
- 3. Hold meter steady and note open window and closed window readings.
- 4. Pecord reading, location, date and time.
II. OPERATION OF PIC-6A ION CHANGER SURVEY METER A. DFSCRIPTION The Eberline PIC-6A is a 1/2" diameter, 30 mg/cm2 walled, gas filled ion chamber, portable survey meter. It has 6 logarithmic ranges: 1-10, 10-100, and 100-1000 mR/hr plus 1-10, 10-100 and 100-1000 P/hr. It utilizes a 2 NEDA type 604 batteries (9 volts) and weighs about 3.3 pounds. Its energy response is linear from 0.8 to approximately 6 Mev, and it can be operated from -10' to
)
+140*F.
B. GENERAL INSTRUMENT CHECKOUT
- 1. Turn the function switch to BATT. The meter should read in the BATT OK region.
l 2. Set the function switch to the desired range. A single rotary switch selects the range to respond in either the mR/hr range or the R/hr range.
- 3. Wait 10 seconds for full meter response.
C. TO PERFOPM A DOSE RATE SURVEY
- 1. Hold PIC-6A at waist level (approximately 1 meter above ground).
l 13 of 41 Rev. 2 i
EP IV-110-A Attachment 4
- 2. Hold meter steady and note closed window reading.
- 3. Fold meter steady and note open window reading.
- 4. Record readings, location, date, and time.
III. OPERATION OF E-520 GM TURE SURVEY METER A. DESCRIPTION The Eberline E-520 is an external GM tube probe plus internal tube portable survey meter. The external GM tube has 4 linear ranges of 0-0.2, 0-2, 0-20, and 0-200 mR/hr. It utilizes two "D" batteries and weighs approximmately 4-1/2 lbs. Its energy response is linear from 0.2 to 2 Mev. With alkaline or NiCd batteries, it can be operated from -40* +140*F. The external detector outer wall is O' approximately 200 mg/cm2 and the inner wall is 30 mg/cm2 An external speaker is available for use with this meter.
B. GFNERAL INSTRUMENT CHECKOUT
- 1. Turn the function switch to BATT. The meter should read in the BATT OK region.
- 2. Set the function switch to one of the five sensitivity ranges.
! 3. Wait 15 seconds for full meter response.
C. TO PFFFOPM A DOSE RATE SURVEY NOTE This GM tube survey meter may saturate (and read zero) in a l radiation field in excess of 1000 R/hr.
14 of 41 Rev. 2
1 EP IV-110-A Attachment 4
(}
NOTE The high range detector (0-2000 mR/hr) is located in the i meter case and not in the hand held probe.
- 1. Hold E-520 at waist level (approximately 1 meter above ground) .
- 2. Hold meter steady and note closed window reading.
- 3. Hold meter setady and note open window reading.
- 4. Record readings, location, date, and time.
IV. OPERATION OF THE HIGH VOLUME AIR SAMPLER (H-709V)
A. DESCRIPTION O
The H-709V is a 110 VAC, 2-28 CFM variable flow, high volume air sampler. The sampler is designed to accept a 2-inch filter paper for particulate sample collection and a CESCO charcoal, or Silver Zeolite cartridge for Iodine 131 sampling.
B. TO OPERATE AIR SAMPLER
- 1. Place the Iodine cartridge and a filter paper into the filter holder. Attach the filter housing to the sampler.
- 2. Plug the sampler into a 110 V outlet and turn it on. Insure the flow meter is operating by tapping lightly on the flow meter housing. Switch the sampler power switch to the variable position for a 2 inch sample.
O 15 of 41 Rev. 2
EP IV-110-A
) Attachment 4 4
- 3. Obtain a 40 cubic foot sample; approximately 2 CFM for 20 minutes. l NOTE Smaller volume samples may be requested by the EDO. Sampling times should be adjusted accordingly.
- 4. Observe flow rate during sample. Record air flow, duration of sampling time, and location where sample was taken.
- 5. Place cartridge and filter paper into separate envelopes and mark each envelope with the following information:
Emergency Station No.: Date:
Sample Start Time: min. Sample Stop Time min.
Sample Flow Rate: ft /3 min. Tech.
Record sample data on the Emergency Survey Log Sheet (Attachment 3).
V. OPERATION OF SAM-2 DUAL SINGLE CHANNEL ANALYZER (with 2" x 1/2" NaI crystal)
A. DESCRIPTION l
j The Eberline SAM-2 is a lightweight (7 lbs.) two channel gamma spectrometer which is stabilized to correct automatically for gain l
changes (caused by temperature changes, etc.). It can read out each channel independently or the sum or difference of both channels on either a scaler or ratemeter. It will operate from either a 110 volt AC outlet or its own 8 pound battery pack. It O
1 O
16 of 41 Re v . 2 i
l
EP IV-110-A Attachment 4 utilizes a 2" x 1/2" Sodium Iodide crystal which, with its lead shield collar, weighs about 8 pounds. This counting system is designed to operate from 32*F to 140*F. It has both a preset timer and a manual timer. It is fused for both AC and DC operation.
CAUTION The sodium Iodide probe is fragile and should be handled with care. The Sodium Iodide probe should not be taken through rapid temperature changes, it may crack if brought from 30* to 60* without some thermal wrapping to slow down temperature equalization.
B. OPEPATION
^3 1. Utilize a gamma survey meter (low range) to find as low a background area as practicable (0.5 mrem / hour) in which to perform the counting functions. If background is greater than 0.5 mrem / hour, provide shielding as necessary.
- 2. Plug cord into 115 VAC, 60 Hz power source or connect to battery power through BATTERY connector (pin 1 negative, pin 2 positive).
- 3. Connect detector.
- 4. Turn power switch to ON and, if battery pack isused, insure BATT OK light is on. Allow the instrument to warm up for at least 10 minutes. A 20 minute warm up period or longer will provide optimum stability.results.
- 5. Set controls as follows:
17 of 41 Rev. 2
EP IV-110-A
) Attachment 4 a) STABILIZER-ON (rear of instrument) b) H.V. ADJUST - P.00 (or at least 1/3 of the way onto the high voltage plateau) c) Both THRESHOLDS - 10.00 d) Both IN-OUT to OUT e) DISPLAY - ON f) TIMFD-STOP-MAN - STOP g) CH1 to +, CH2 to OFF
- 6. Press RESET-START switch. The display should be all zeros.
- 7. Operation Check a) Set TIMED-STOP-MAN switch to TIMED b) Set COUNT TIME IN MINUTES switches to 1 and X.1. Press
() .
PESET-START switch. Unit should stop counting after 6 seconds, registering 4500-8500 counts (no background).
c) Under the above conditions, the rate meter should read 45000 to 85000 counts per minute.
R. Counting Iodine-131 a) Care must be taken not to contaminate the detector with samples. The face of the detector may be covered with a thin plastic sheet.
b) Set thresholds and windows, for botn channels, to the values posted on the instrument case.
c) Set CH1 switch to "+" and CH1 window to "IN".
d) Set CH2 switch to " " and CH2 window to "IN".
e) Set COUNT TIME to 1 minute (1 and X1). Set COUNT to " TIMED".
f) Press START button.
'\.
18 of 41 Rev. 2 I ._ _
EP IV-110-A Attachment 4 g) Count background for one minute. If background is greater than 500 cpm, provide additionaly shielding (if practicable). If the number is less than zero, as evidenced by a series of nines, then minor adjustments of the Channel 2 window will correct this, usually clockwise to increase the Count.
h) Place a Ba-133 source on the face of the detector and press the reset-start button for one count.
- 1) Using the formula: cpm 1.2 and the results from h, source dpm determine the efficiency. This number should be + 10% of the I-131 EFF posted on the SAM-2 case.
NOTE
-') 1.2 is a correction factor to allow for the difference s/ in energy abundancies between Ba-133 and I-131.
j) Femove the source and count background for 5 minutes (set count time to 5 and X1), record this value.
k) Place saran wrapped samples on detector face and make 5 minute counts (divide by 5 and get cpm), record these values.
- 1) Carefully mark and save all samples for later laboratory evaluation. Wrap samples in clean saran wrap or equivalent (e.g., surgical gloves) for storage. If sample is to be saved it must be properly identified and a log kept of sample information (Attachment 3 should suffice). -
lO 19 of 41 Rev. 2
EP IV-110-A
() Attachment 4 Samples should be stored in a suitable area which will not cause s significant change in background radiation levels. If sample causes a high radiation area to be formed in the immediate area, then a suitable storage area should be used (e.g., lead bricks in rear of vehicle).
Af ter delivering sample s to EOF, the samples should be stored in a locked storage area.
- 9. Calculate Airborne I131 activity as follows:
a) Divide the Net cpm (background subtracted) by the efficiency factor from step i above to get a reading in dpm.
b) Multiply the reading (in dpm) obtained in 9.a above, by 4.5 x 10~7 uci/dpm to obtain a reading in uCi.
c) Multiply the sampling time (minutes) times the sample flow rate (ft /3 min) times 2.832 x 10-4 cc/ft3 to find the total
. CSl sample volume (in cc).
d) Divide the total I131 reading of step 10.b above (uci) by the total sample volume (in ec) found in 10.c above to get total activity in uCi/cc.
e) Record the following information:
Emergency Station No. Date/ Time Sample Counted Il31 Activity: uCi/cc Date/ Time Sample Taken r
- 10. Refer to Figure 4-1 to obtain thyroid dose rate.
l
- 11. Alternate Method Refer to Table 4-1 to determine a quick estimate of concentration and thyroid dose rate based on an assumed efficiency.
- 12. Communicate SAM-2 results and derived dose rate to TSC.
- O 20 of 41 Rev. 2
, - - , - . - - - - - - m- - - , - - - , - -
EP IV-110-A Attachment 4 VI. OPERATION OF PNC-4 PORTABLE NEUTRON COUNTER A. DFSCPIPTION The Eberline PNC-4 has a BF3 detector with cadmium shield and moderator for use in detecting fast or slow neutron radiation. The count rate is read out over four decades (500, SK, 50K and 500K cpm) using two separate meter movements. The instrument requires five standard "D" size batteries. Within the instrument is a moderator consisting of parafin wax encased in a cadmium sheath. Total weight of the instrument is about 12 pounds.
B. GENERAL INSTRUMENT CHECKOUT
- l. Turn switch to BATT check position. The left pointer
(
(black) should read in the green area.
- 2. Release switch and it will spring return to the ON position.
C. TO PEPFORM A DOSE RATE SURVEY
- 1. To detect fast neutrons, the detector must be inserted into the " moderator" and to detect slow neutrons the detector must be out of the " moderator".
- 2. If possible, use a beta-gamma survey meter when performing neutron surveys as a precaution.
- 3. Hold the PNC-4 at waist level-(approximately 1 meter above ground).
O 21 of 41 Rev. 2
EP IV-110-A O- Attachment 4
- 4. To read the meter, simply read whichever of the two pointers is on scale. The black pointer is read up to SK cpm, above which it disappears from view and the red pointer comes on scale.
- 5. Watch the pointer long enough to obtain the average reading for fast and slow neutrons, as required.
- 6. Record the readings, location, date and time.
VII. OPERATION OF PRM-4 PULSE RATE METER A. DESCRIPTION The Eberline PRM-4 pulse rate meter is used for the detection Os of beta and gamma radiation. The count rate is read out over four decades (200, 2K, 20K and 200K cpm) using two separate meter movements. The instrument requires five standard "D" size batteries. Total weight of the instrument is 5.25 pounds.
R. GENERAL INSTRUMENT CHECKOUT
- 1. Turn the switch to the BATT check position. The lef t pointer (black) should read in the green area.
- 2. Release seitch and it will spring return to the ON position.
C. TO PEPFORM A DOSE RATE SURVEY O
V 22 of 41
l 1
EP IV-110-A
(
Attachment 4
- 1. Using the HP-240 probe detection of gamma radiation is done with the sliding window closed. To detect beta, simply open the sliding window.
- 2. Hold the PRM-4 at waist level (approximately 1 meter above ground).
- 3. To read the meter, simply read whichever of the two pointers is on scale. The black pointer is read up to 2K cpm, above which it disappears from view and the red pointer comes on scale.
- 4. Watch the pointer long enough to obtain the average reading.
O 5. Record the readings, location, date and time.
VIII OPERATION OF THE GENARAC (6330) PORTABLE ALTERNATOR A. DESCRIPTION The GENERAC 6330 Portable Alternator is a revolving field single phase alternator rated at 115 VAC, 60 cycles, 13 amps, 1500 watts. The alternator is driven by a 4 cycle, single cylinder, 3.5 horsepower gasoline engine. The unit itself is light-weight and can be moved by one person and is easily handled by two persons.
B. GENERAL CHECKOUT
- 1. Check the alternator and engine in the technical manuals attached to the unit.
23 of 41 Rev. 2
O EP IV-110-A Attachment 4 C. ALTERNATOR OPERATION
- 1. Operate the GENERAC 6330 Portable Alternator engine unit as outlined in the technical manuals attached to the unit.
IX OPERATION OF THE EBERLINE RM-14 COUNT RATE METER WITH PROBE (HP-210)
A. DESCRIPTION The Eberline Radiation Monitor (RM-14) is a count rate meter which is commonly employed as a frisker at control points when used with a pancake type probe. For use as a count rate meter, an HP-210 pancake probe is employed. This instrument can be used to count particulate filter samples, charcoal or silver zeolites for Il31 concentration determination. It should be noted that the gamma efficiency of the HP-210 probe is significantly less than that for the' RD-19 probe (SAM-2) . The HP-210 can also detect the beta emissions from I-131, however, the minimum detectable activity for l I-131 using the HP-210 probe is considerably greater than that obtained using the SAM-2/RD-19 instrumentation. It should also be noted that the RM-14/HP-210 is incapable of discriminating between different energy isotopes. The use of silver zeolite for sample collection does improve this condition.
B. GENERAL INSTRUMENT CHECKOUT
- 1. Energize the RM-14 by plugging the power cord (which exits the instrument chassis at its rear) into a 120 VAC supply. Then switch the five (5) position rotary switch from "off" to one of the three (3) counting ranges (X1, X10, X100).
() 2. Connect the HP-210 probe detector using its coaxial cable to the terminal at the right hand corner of the face of the instrument.
24 of 41 Rev. 2
EP IV-110-A Attachment 4
- 3. Place the rotary switch to the "X10" position, flip on the test toggle switch to on (located on back of instrument chassis), the count rate should rise to 3600 cpm + 10%. If the instrument "on test" reads in this range, the instrument should be in good working order.
- 4. When operating with batteries (no AC power available), turn rotary switch to "BATT" position to see if battery charge is
, within proper charge range (indicated on instrument scale).
C. COUNT PATE METER OPERATION
) 1. Using sample holder or generally applied counting geometry, record background count rate.
- 2. Using check source (use gamma emitting check source, e.g.,
() Co-60), read and record count rate.
j
- 3. Sample Type: Particulates: Place the filter in the holder or preferred geometry, then read and record count rate. allow instrument reading to stabilize for approximately 5 to 10 seconds. Then read and record count rate. Charcoals and Silver Zeolites: Place the cartridge into the sample holder or preferred geometry, place the probe onto the cartridge, read, and record count rate.
To calculate the concentration, use the following formulas:
Particulate Filters:
1 uCi/cc = Net cpm x (1.6E-11) x Efficiency sample volume in ft3 Cartridge Filters:
uCi/cc = Net cpm x (1.6E-11) x 1 sample volume in ft3 efficiency
_ __ _ _ . . _ _ - . ._ _ _ 2 5_ o f . 4. l __ _ _.
N j EP IV-110-A Attachment 4-PSE&G FIELD SURVEY TEAM DATA IODINE DOSE RATE CALCULATION a) Sector and distance b) Time of sample c) Field team name d) Instrument eff. (demical)*
e) DPM above background f) Sample volume (ft3}
g) (e) + (f)x(1.6E-11)**x(1/eff)= uCi I-131/cc h) Child thyroid dose rate from graph mrem /hr Ef ficiency obtained from calibration sticker on instrument.
The default value for efficiency is 0.025 (1/ef f = 4 0 )
** 1.6E-11 = (4.50 E-7 uCi/dpm) x (3.53E-5 cubic feet /cc) uCi/cc IODINE-131 If
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EP IV-110-A Attachmant 4 1
TABLE 4-1 REM DOSE TO THYROID FOR 1 HOUR EXPOSURE 9AM-2 eps uCi/cc* Infant Non-Occu-and pational Working Above Background (assuming I ft3 and 2.5% off) Child Teen Adult Adult 1 x In5 6.4 E-5 118 108 87 131 5 x 104 3.2 E-5 59 54 44 65 1 x 104 6.4 E-6 12 11 9 13 5 x 103 3.2 E-6 6 5 4 7 1 x 103 6.4 E-7 1.2 1.1 0.9 1.3 5 x In2 3.2 E-7 0.6 0.5 0.4 0.7 l'
1 x 102 6.4 E-8 0.12 0.11 0.09 0.13 l 50 3.2 E-8 0.06' O.05 0.04 0.07 in 6.4 E-9 6.01 0.01 0.01 0.01
*To correct for actual sample volume divide tabulated uCi/cc value by the actual volume in cubic feet.
e 1
27 of 41 Rev. 2 l
EP 110-A Attachmnnt 5 ;
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EP IV-110-A Attachment 5 ATTACHMENT 5 ON SITE EMERGENCY MONITORING LOCATIONS Location Description . ,e N-S1 420; N, on inner access road N-S2 750' N, secgrity road inside fences N-53 1500' N, Hope Creek Unit 1 Turbine Building (center of east side on ground)
NNF-S1 400' NNE, NW corner SNGS Unit 2 Turbine Building (on ground)
NNF-S2 850' NME, SNGS North Fence Vehicle Access Gate NNE-S3 2075' NNE, SE corner Hope Creek Change House NE-S1 600' NE, inner access road, NE intersection N E-S2 1150' NE, SW corner SNGS 42 Warehouse NF-S3 1825' NE, SW corner Hope Creek parking lot for trades FNE-S1 450' ENE, NE corner SNGS Administration Building FNF-S2 1360' ENE, inside site security fence at NE corner of switchyard E-SI 400' E, SE corner SNGS Cafeteria E-S2 1300' E, SE corner switchyard, outside security fence ESE-S1 500' ESE, sidewalk 150' N of Unit 1 Guardhouse (at Hose Station) i FSE-S2 1020' ESE, Guardhouse to SNGS employee parking lot s ESE-S3 1960' ESE, access road on outermost parking lot fence SE-S1 160' SE, closest outside entrance to HP control point (next to il ' Unit Steam Mixing Bottle)
SF-S2 560' SE, NW corner of SNGS Main Guardhouse SE-S3 1060' SE, SW corner of permanent visitors Center SF-S4 1100' SE, "Second Sun" barge (when in port)
SSE-S1 360' SE, NW corner of TSC S-S1 360' S, NW corner of B Building I S-S2 825' SE, NE corner of Circ Water Intake Structure SSW-S1 250' SSW, Chemistry ' trailer SSW-S2 560' SSW, on security fence halfway between N end of Circ Water Intake and S end of Service Water Structures I SW-S1 490' SW, NE corner of Service Water Structure WSW-S1 440' WSW, 150' N of 11S1 on access road W-S1 510' W, security access road, due W of a point midway between the two Containment Buildings, W of S end of A Building WNW-S1 690' WNW, inside NW corner of security fence at right angle (inside fence)
NW-S1 600' NW, inside security fence, 275' from NW corner of fence (near river)
NW-S2 1340' NW, Hope Creek Structure, SW corner Hope Creek Road NNW-S1 600' NNW, inside security fence, 500' from NW corner of fence NNW-S2 2400' NNW, SE corner of Hope Creek Material Test Lab i
. 2 29 of 4]
EP IV-110-A ATTACHMENT 5.
OFFSITE EMERGENCY MONITORING LCCATIONS j .. 4 % y ,
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(% EP IV-110-A Attachment 5 ATTACRMENT 5 ,
k
] OFF SITE EMERCENCY MONITOREX2 STATIONS a EMERCENCY
- s SECTOR MILE A2Mtmi ,SNCS ENV. _OLD NEW LOCATION 1 5.8 73/4' 1F1 1 N7 Ft. Elfsborg, across from Gold Course 1 9.6 3551/2' None N10 Ft. Mott, Ft. Mott Rd., S end 1 10.5 10' 1C1 None N20 Rt. 499 0.2 mi. S of Hook Rd.
Richmonde Dairy 2 4.4 20' 2E1 None NMES : Fara 2 5.8 24 1 /2' 2 NNE7 Ft. Elsborg & Anwellbury Rd. s 2 8.7 242 /2' 2F2 7 NNE10 Salem Test Lab 2 7.4 26' 2FS Mone NME10a Salem Migh School 2 10.3 28' None NNE20 Salem County Hospital f 3 3.8 4? 1 /8' None NE4 End of Poplar St.
3 4.1 49' 3E3, None NES Farn 3 5.1 51.5' 3F2 4 NE7 LAC 3 5.8 39' 3 NE7e Mill St. & Han. Sridge-Ouinton Rd.
3 8.8 49' 8 NE10 Water Works Road, Quinton ,
(0.2 mil N of 3F3) 3 10.8 44 1 /2' None- NE20 Corner Clancey & Quaker Neck Rd.
4 3.7 66* ,. 4D2 None ENE4 Alloway Creek Neck Road 4 4.1 59* ! 5 EM ES Alloway Creek Neck Road 4 5.9 62 0/2' Mone ENE7 Hermersv111e, Dilks Store, Red Light 4 R.6 67' None ENE10 Woodmere, Corner Harmersville Pecks i Corner Rd., & Jerico Rd.
4 10.5 72' h None ENE20 Pecks Corner, Rt. 49 & Harmersville Road ,
p 5 0.9 90* 551 62 El split in Site Access Rd., Hope Creek-Salem Y*
\v/ 3.5 5 80* , 5D1 6 E4 Pole CCC) G-68 SP10-40, Air Sampler *
$ 6.5 84 1 /2' 5F1 9 E7 Canton, main intersection 5 12.6 99* None E20 Shiloh, main intersection Rt. 49 &
Bank A 6.4 104' 6F1 None ES E', Stowe Neck Rd.
6 8.1 102' 10 F3$10 Cur Tree Corner 6 11.3 lin' 12 E3E20 Creenwich, 0.7 mi. S of center of town on Cohansey Creek 7 8.8 128' 7 F2 11 S!10 ' Bayside 't i '
7 11.4 125' None SE20 Ragged ' Island
- 8 9.6 161* , None SSE10 Woodland Bench, At. 6 at Del. Bay 8 14.5 168'
- None SSE20 Rt. 9 at Whitehall Neck 9 4.2 188* 9El None L$ Tailor's Bridge Spur Rd.-end 9 5.8 179' None 510 Broadway Meadow 9 8.8 176' None $20 Whitehall Crossroads i 10 3.9 203' 10D1 105 SSW4 Taylors Bridge Spur Rd.*
- 10 5.4 19R1/2' 10F1 None SSW7 Rt. 9 intersection in 8.9 203' None SSW10 Walker, Rt. 9 ,
10 11.6 198' 1001 None SSW20 Smyrna, Rt. 13 & Rt. 6 corner k .
11 4.9 218' 11E2 None SW5 Taylors Bridge, Rt. 9 11 6.0 235' 11F1 i None SW7 Taylors Bridge - \
11 R.9 231' ' No+e ' SW10 Point Breeze Fork, Rt. 13 & 896 11 12.3 225' None SW20 Dexter Corners
*Also environmental air location
' ) '
s Rev. 2 l
31 oft 41 1
---e.-- p. , - - p - - - - . - ., .- - - . , , - - ,m.,
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EP IV-110-A Attachment 5 AffACMMENT 5 OFF SITE ENERGENCY NONITORING STATIONS (continued)
SFCTOR w!LP AtMUTH SNCS ENV. OLD NEW LOCATION 12 4.4 258' 12E1 None NSW5 W omas Landing 12 6.0 256' None WSW7 Matthews Corners (off Rt. 9) Rt. 299 12 7.7 241' 106 WSW10A Pine Tree Corners, Rt. 13 12 9.4 241' 12F1 None WSW10 Townsend Elementary School 12 11.9 262* None WSW20 Intersection 1.5 mi. West of Townsend Cemetary 13 4.2 275' 1321 103 W5 Rt. 9 Appoquimimink River, Icth.14b 13 4.0 266' 13r2 107 W7 odessa, 2 b1ks. E of Rt. 13 on Rt. 299
, 13 9.9 165' 13r1 104 W10 Middletown, Icth. Assoc
- Ndqtre.
13 11.3 263' None W20 Rt. 299, 1.5 mi. W of Middletown 14 3.4 296* 14e1 102 WWW4 Bayview, Coast Guard Station Cate 14 4.1 296' Mone WWW5 Rt. 9 (90' turn), 0.7 mi. W of Bayview 14 6.7 294* 14F2 None WNW7 Boyds Co ner, Rt. 13 14 a.5 291* Mone WNW10 Cedar I.ane 14 11.4 297' None WNW20 Summit Bridge (Town not bridge) 15 3.8 318' None NW4 Augustine Beach (0.2 mi. S), Rt. 9 15 5.5 314' 15F3 None NW7 Biddle Corner Intersection, Port Penn Rd.
15 8.4 314' None NW10 S end St. Georges Bridge, Rt. 13 15 11.5 311' Mone NW20 Rirkwood, Delaware la 4.2 330' 16El 101 NNWS Port Penn Sewage Plant
- 16 5.9 337' None NNW7 Rt. 9 at Wooden Bridge 16 8.1 343' 100 NNW10 Delaware City, Of fice of Energ.
Planning i la 12.3 333' None NNW20 Rt. 13, Rt. 301 Fork l
ls
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(
32 of 41 Rev. 2
EP IV-110-A ATTACHMENT 5 -
i O ' '
$TATION LOCATIONS E 1 H. 'TF STAT 1086 NE7 I -
N7 UTIUTY ME S25440 385-1 A ',
BT- -45 KEY a SWtVEY STATION d = TRA8000ftSS40N TWR.
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EP IV-110-A ATTACHMENT 5 O
STAT 1000 LOCAT!ONS STATIONS 5 TO SALEM \ [/
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KEY a SURVEY STATION Of E4
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g SALEM STA.
O Rev. 2 34 of 41
EP IV-110-A ATTACHMENT 5
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SElo sToPUGHT E7 POLE ACE 996 L224 NE N
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O Rev. 2 35 of 41 l .
EP IV-110-A ATTACHMENT 5 O
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36 of 41 Rev. 2
i EP IV-110-A ATTACHMENT 5 O
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37 of 41 "
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37 of 41 Rev. 2 l
EP IV-110-A Attachment 5 f-~ DIRECTIONS
( j STATION N7
- 1. Proceed to Hancock's Bridge intersection.
- 2. Turn left and proceed 1.6 miles to Elsinboro turnoff.
- 3. Turn left on Elsinboro cutoff.
- 4. Follow road 1.7 miles to fork.
- 5. Take Right fork and proceed 0.2 miles to fork in road.
- 6. Take left fork and proceed 1.5 miles to Elsinboro intersection.
NOTE: Pole will be located left side of intersection.'
Pole No. S25440 383-1 STATION NNE7
- 1. Proceed to Hancock's Bridge intersection.
- 2. Turn left and proceed 1.6 miles to Elsinboro turnoff.
- 3. Turn left on Elsinboro cutoff.
() 4. Follow road 1.7 miles to fork.
- 5. Take right fork and proceed 0.2 miles to second fork. This is location of Station A2.
NOTE: Pole will be loated directly across intersection.
Pole No. BT-324-65.
STATION NE7a
- 1. Turn left at Hancock's Bridge intersection towards Salem.
- 2. At 1.6 miles from intersection you pass the Elsinboro cutoff, disregard and proceed towards Salem.
- 3. Station 83 is 0.2 miles from Elsinboro at intersection.
NOTE: Pole I.D. is on the salem side of intersection.
. STATION NE7 l
- 1. Proceed down access road from main gate to Hancock's Bridge intersection (6 miles).
() 2. Turn left at Hancock's Bridge intersection and proceed 0.5 miles and turn left to fire station.
38 of 41 Rev. 2 l _ __. - _. - - _ - _ _ _ - -_. _
EP IV-110-A Attachment 5 DIRECTIONS (continued)
O STATION ENE5
- 1. Proceed from main gate, down access road, for 5.4 miles. '
- 2. At curve, pull off to left side on old road and locate Pole No.
ACE S-29844 (36).
STATION E4
- 1. From main gate, proceed 4 miles on access road.
- 2. Pole is located on left hand side of the road just past turn.
- 3. Pole has white air monitor box attached. Pole is No. GCCO G068 SP10-40.
STATION NNE10
- 1. Proceed out access road to Hancock's Bridge intersection.
- 2. Turn left and proceed 4.7 miles to light on Route 49.
- 3. Continue through light 0.5 miles to the end of the road.
- 4. Turn left and proceed two traffic lights.
- 5. At third traffic light (Anchor Hocking), turn right and proceed 0.2 miles to substation.
NOTE: Substation is located on the right hand side of the road.
We do not have a key for substation.
STATION NE10
- 1. Proceed down access road to Hancock's Bridge intersection.
- 2. Continue through the intersection 0.3 miles and take the left cutoff.
- 3. Proceed straight through stop sign 2.6 miles.
- 4. At second stop sign, turn left.
- 5. Proceed 2.5 miles to Route 49.
2
- 6. Turn left on 49 and proceed 0.1 miles to traffic light.
- 7. Turn right at light and proceed 0.2 miles to Water Works Road.
- 8. Turn right at Water Works Road.
! 9. Proceed 0.3 miles to pumping station on right.
39 of 41 Rev. 2
EP IV-110-A Attachment 5 g DIRECTIONS (continued) b NOTE: Pole is located in front of pumping station. Pole No.
S29335.
STATION E7
- 1. Proceed down access road to Hancock's Bridge intersection.
- 2. Go through the intersection and keep bearing to your right towards Harmersville (1 mile).
- 3. At the blinking light (Harmersville intersection), turn right towards Canton.
- 4. Station #9 is 2.4 miles on the right on Harmersville-Canton Road.
NOTE: Pole is located on the right.
Pole No. ACE 996 L224.
STATION ESE10
- 1. Proceed down access road to Hancock's Bridge intersection.
() 2. Go through intersection and keep bearing to your right towards Harmersville (1 mile).
- 3. At blinking light (Harmersville intersection), turn right towards Canton.
- 4. 5.3 miles down the Harmersville-Canton Road you will come to the Gum Tree intersection (Station #10).
NOTE: Pole is located by the tree at the intersection on the right.
Pole No. ACE 12410.
STATION SElO i 1. Proceed down access road to Hancock's Bridge intersection.
- 2. Go through intersection and keep bearing to your right towards Harmersville (1 mile).
- 3. At blinking light (Harmersville intersection), turn right towards Canton.
- 4. 5.3 miles down the Harmersville-Canton Road, you will come to the Gum Tree intersection.
O)
I i
(, 5. Take the far right cutoff for 2.8 miles to Mill Road.
40 of 41 Rev. 2
EP IV-110-A DIRECTIONS (continued)
(}
STATION SElO (continued)
- 6. Turn right and Mill Road is 0.4 miles at a fork.
- 7. Take left fork,0 3 miles to a second fork.
- 8. Take left fork, again proceed 0.5 miles to another intersection.
4 Turn left at intersection and proceed 1.2 miles to another intersection.
- 10. Turn right again and proceed 0.5 miles.
NOTE: Station is located 5 poles from the water. Pole No. 15547.
STATION ESE20
- 1. Proceed down access road to Hancock's Bridge intersection.
- 2. Go through the intersection and keep bearing to your right towards Harmersville (1 mile).
- 3. At blinking light (Harmersville intersection), turn right towards Canton.
4 At 5.3 miles on the Harmersville-Canton Road, you will come to the Gum Tree intersection (Station #10).
- 5. Take the middle road of the intersection 4.9 miles to Greenwich.
- 6. At Market Lane in Greenwich, turn right and proceed 0.7 miles to the intersection (Station #12).
- 7. Pole is located at the intersection on the right.
Pole No. B-19518.
O 41 of 41 Rev. 2 '
EP IV-110-B EMERGENCY PROCEDURE EP IV-110-B FIELD MONITORING COORDINATED BY EOF ACTION LEVEL When requested by the Emergency Response Manager or Radiological Support Manager (RSM).
PFSPONSIBLE INDIVIDUAL A. Radiological Assessment staff member as designated by RSM.
LIMITS OF AUTHORITY
- 1. Exposure in excess of 10CFR20.101 shall be approved in accordance with EP IV-106.
O
- 2. Re-entry into areas with suspected dose rates >100 mR/hr shall be approved by the Padiological Support Manager (RSM).
- 3. Change-out of the air samples or TLD's in the environment at stations requires the approval of the Radiation Protection Engineer or Radiological Emergency Manager and the Maplewood l
Research and Test Lab.
l 4. Issuance of Potassium Iodide (KI) tablets requires the approval l of the Radiological Support Manager.
I I
ACTION STATEMENTS
- 1. Upon the request to initiate an Emergency Radiation Survey obtain and record the following briefing information (available from a Radiological
() Assessment staff member):
a) Wind Direction (towards)
(from) 1 of 26 Re v. 0
-___i . _ . . .-_ _. . . _ _ _ _ ._ _ ___ _ _
EP IV-110-B
() ACTION STATEMENTS (continued) b) Areas or locations to be surveyed:
c) Plant conditions that may affect the safety of the survev team or the survey results.
d) Enter team composition on Attachment 1, " Emergency Team Assignments".
- 2. Provide the Radiological Assessment staff member with the names of the team members assembled at the EOF.
(Copy of " Emergency Team Assignments" will suffice).
- 3. Log each team member's name, badge number, dosimeter number, and dosimeter reading on the Dosimeter Log (Attachment 2), re-zero dosimeters if necessary. Any dosimeter readings and subsequent dosimeter resets should be recorded on the Dosimeter Log.
- 4. Field Survey Team (s) will be dispatched by a radio communicator within the REM office of the Emergency Operations Facility.
i
- 5. Brief each team leader on the incident and provide him/her with the following information from Step 1.
a) Wind direction from (meter reading +180* =
direction toward) 2 of 26 Rev. o
() ACTION STATEMENTS (continued)
EP IV-110-B b) Probable areas or locations to be surveyed.
c) Plant conditions that may affect the safety of the survey team or the survey results.
- 6. If it is suspected that the survey team will be exposed to significant quantities of radio-iodine, see Procedure EP I-15 for use of stable iodine.
NOTE Approval of the Emergency Response Manager, acting on advice of the Radiological Support Manager, must be obtained prior to taking of Potassium Iodine (KI) tablets. The tablets are issued prior to departure from the EOF.
- 7. Ensure each team member has adequate protective clothing as required for the specific situation.
- 8. Assign a name to each team before dispatching vehicles. Use phonetic alphabet names for field team
! designations (e.g., alpha team, bravo team, foxtrot l team, etc.).
- 9. Each Field Survey team will be provided with emergency equipment in kits and vill be issued dosimeters and TLD's separately (separate issue for each individual).
I NOTE The minimum items required include:
- 1. Air Sampler O- 2. Dose Rate Meter
- 3. Count Rate Meter
> 4. SAM-2 or equivalent counting equipment i
l Rev. 0 3 of 26
_ _ _ - ~ - _ __ _
) ACTION STATEMENTS (continued)
- 5. Particulate Filters
- 6. Charcoal or Silver Zeolite Cartridges
- 7. Communications Equipment (if not in vehicle)
See Attachment 5 for check-off list of Equipment.
Field Team must check equipment inventory before being despatched to the field.
- 10. Dispatch each survey team to the appropriate survey vehicle. Perform a communications check between the vehicle and the EOF.
NOTE If the vehicle is not radio-equipped, instruct the
-) team to obtain a portable radio from Security at the entrance to the EOF.
- 11. While one team member is performing the radio communications check, the other team member should be performing an operational check of all emergency i equipment (see Attachment 4 for instrument instruc-l tions). If the emergency equipment kit is equipped with a SAM-2 assay meter, set up instrument for warm-up and stabilization as per instructions.
- 12. Proceed to the first survey location (maps and directions to some probable survey sites can be found
. in Attachment 5 to EP IV-110-A). Insure the team is continously monitoring the radiation levels with a Beta / Gamma Survey instrument. Document the survey results on the Survey Maps and/or the Emergency Survey
- s. Log. Inform the EOF of any significant fluctuations in the survey results.
4 of 26 Rev. 0
EP IV-110-B ACTION STATEMENTS (continued)
NOTE Indicate beta / gamma survey data location by significant intersections or landmarks for data points not located at designated sampling locations.
- 13. Upon arrival at the first survey location, initiate an air sample, unless otherwise directed. Record the start times and the initial flow rate on the Emergency Survey Log (Attachment 3). Specific Instructions on surveys to be performed will be provided to the team from the EOF.
- 14. Special consideration should be given to current meteorological conditions when directing the field
)
s/ monitoring teams for plume tracking. This is especially necessary if wind speeds at Artificial Island are less than five miles per hour, for frequent wind shifts, if inversion conditions exist, or if backup meteorological data is used from the Wilmington Airport or some other offsite facility. Field teams should await instructions from the radio communicator at the EOF regarding plume tracking.
NOTE The maximum flow rate is 2 SCFM for charcoal and 2 SCFM for Silver Zeolite cartridges.
- 15. During the collection of the air samples, monitor the radiation levels and record the results on the Emergency Survey Log. Inform the EOF of any new survey
() results while waiting for the air sample to finish collecting.
5 of 26 Rev. 0
EP IV-Il0-B
) ACTION STATFMENTS (continued)
- 16. Refer to Section IV of the Instrument Instruction (Attachment 4) for the operation of the SAM-2.
Perform Steps 6 through 8j.
T
- 17. Upon completion of the air sample collection, count the samples per Steps 8k - 9 of the SAM-2 operational instruction (Attachment 4). Document the calculations on the Emergency Survey Log. All samples shall be labeled with pertinent information and retained for future analysis. Remain in plume only to collect sample and perform surveys. Count samples in as low a background as possible.
NOTE O
k- / Samples should be checked for excessive dose rates.
Any samples with a dose rate greater than 100 mR/hr should be stored in a remote, shielded corner of the vehicle.
- 18. Inform the EOF of the survey and air sample results.
l 19. For counting of charcoal of zeolite cartridges, repeat Steps 8j - 9 of the SAM-2 instructions (Section IV of Attachment 4) for each survey location.
- 20. If the radio should fail, see the Communications Section of this procedure (directly before signature sheet) for phone number of the EOF, Control Point, TSC
, and Control Room.
l i
6 of 26 Rev. 0
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s EP IV-110-B T
ACTION STATEMENTS (continued)
- 21. Upon completing ths assigned survey request additional instructions from the EOF. If surveys are to be terminated:
a) Log each team member's final dosimeter reading, the return time and the net exposure on the Dosimeter Log and the Dosimeter Cards.
b) Inform the EOF when the team has arrived back at the EOF.
i c) Direct the team to return the equipment to the proper storage locations both within the kits and lockers, i
d) If appropriate, have the air samples analyzed for
, isotopic content. '
1
- 22. As soon as possible, debrief the Radiological Assessment l Staff member on the survey results. j l
ATTACHMENTS
- 1. Emergency Team Assignments '
1
- 2. Dosimeter Log
- 3. Emergency Survey Log
- 4. Instrument Descriptions i
- 5. Check-off list for Offsite Teams COMMUNICATIONS SSS TSC Control Room 1 l FE3Io Control Room 2 Control Point EOF-(REM)
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7 of 26 Rev. 0 E
EP IV-110-B Prepared By: [bj/,
e Peviewed By: , (T\ @g 9 \b & 'L i Department Head lDate '
Pe iewed By: M 9 /)--S a -
NuclearbergencyPlanningEdineer Date Reviewed By: , 7384-StationOualityAs[ uran Review [ Da'te (i re red e VI )-
SORC Meeting No.: 6 b 'I l , M M hate l Approved By: /// [b N General Manager - Salem Operations Date Approved By: $ b Manager - Nuclear Site Protection Date l
8 of 26 Rev. 0
EP IV-110-B O
FIGURE 1 EMERGENCY TEAM ASSIGNMENTS TEAM CODE TEAM MEMBERS ORIGINAL ASSIGNMENT TIME OUT TIME IN ONE OR ALPHA TPU OR RFAVO TFREE OR DFLTA FOUR OR FOXTROT
- DENOTES TEAM LEADER l
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EP IV-110-B ATTACHMENT 3 EMERGENCY SURVEY LOG SHEET Ts fur S DFSIGNATION TEAM MEMBERS:
INSTRUMENT SERIAL NUMBERS:
TELFTECTOR PRM-4 RADECO PIC-6 E-520 RO-2 SAM-2 AIP SAMPLE CALCULATION pCi/cc = Net Counts _Per_ Minute _
(cubic teet)(2.832 x 10* cm3/ftJ)(2.2 x 100 dpm/pC1) (Detector EFF)
TYPE OF FILTER (P) (SZ) (C) (P) (SZ) (C) (P) (SZ) (C) (P) (SZ) (C)
LOCATION MMA DOSE RATE
-;TA DOSF RATE SAMPLE DATE SAMPLE START TIME SAMPLE STOP TIME ot AVG. FLOW RATE VOLUME (ft3)
COUNT DATE COUNT TIME NCPM*
FFF = DPM 2.2 x 106 = uCi t3 = uCi/ft3
-2.832 x 104 = uCi/cm3
*MCPM = Gross CPM - Background CPM at Analysis Location.
P = Particulate, SZ = Silver Zeolite, C = Charcoal 11 of 26 Rev. O
g~g EP IV-110-B ATTACRMENT 4 INSTRUMENT OPERATION INSTRUCTIONS '
I. OPERATION OF RO-2 (JUNO TYPE ION CHAMBER) SURVEY METER A. DESCRIPTION The Eberline RO-2/RO-2A is a 3" diameter air filled ion-chamber survey meter. It has four linear ranges; RO-2: 0-5, 0-50, 0-500 and 0-5,000 mR/hr, RO-2A: 0-50, 0-500, 0-5,000 and 0-50,000 mR/
h r. The RO-2 and RO-2A utilize 3 and 4 NEDA 1604 9 volt batteries respectively, Its energy response is linear from 0.05 MeV to 6 MeV l
and can be operated in a temperature range of -40*F to +140*F. The detector's, outer wall is 200 mg/cm2 and the inner wall is 7 mg/cm2, B. GENERAL INSTRUMENT CHECKOUT
- 1. Turn the function switch to BATT 1 and then to BATT 2 positions. The meter should read above the BATT cutoff line in both cases.
- 2. Turn the function switch to ZERO position. Check that the meter reads zero. If not, set it to zero with the ZERO knob. (The zero setting of the instrument may be checked in any radiation field by merely selecting the ZERO position.)
l
- 3. Set the function switch to the desired range of operation. Wait 10 seconds for full meter response. The switch position selected is the full scale reading of that range.
l C. TO PERFORM A DOSE RATE SURVEY
- 1. When measuring beta or low energy gamma or X-ray emissions, open the sliding beta shield on the bottom of the case and face the s,. bottom of the instrument toward the radiation source. To open 12 of 26 Rev. 0
EP IV-110-B O Attachment 4 or close the shield, depress the friction release button on the left side of the case and manually move the slide or let it fall due to gravity. When the shield is open, protect the thin face against damage.
- 2. Hold RO-2 waist level (approximately 1 meter above ground) .
- 3. Hold meter steady and note open window and closed window readings.
- 4. Record reading, location, date and time.
II. OPERATION OF PIC-6A ION CHAMBER SURVEY METER A. DESCRIPTION '
O The Eberline PIC-6A is a 1/2" diameter 30 mg/cm2 walled, gas filled ion chamber, portable survey meter. It has 6 logarithmic ranges:
1-10, 10-100, and 100-1000 mR/hr plus 1-10, 10-100 and 100-1000 R/
h r. It utilizes 2 NEDA type 604 batteries (9 volts) and weighs about 3.3 pounds. Its energy response is linear from 0.8 to approximately 6 MeV, and it can be operated from -10'F to +140*F.
l B. GENERAL INSTRUMENT CHECKOUT
- 1. Turn the function switch to BATT. The meter should read in the BATT OK region.
- 2. Set the function switch to the desired range. A single rotary switch selects the range to respond in either the mR/hr range or the R/hr range.
- 3. Wait 10 seconds for full meter response.
i O
13 of 26 Rev. 0
EP IV-110-B Attachment 4 C. TO PERFORM A DOSE RATE SURVEY
- 1. Hold PIC-6A at waist level (approximately 1 meter above ground).
- 2. Hold meter steady and note closed window reading.
- 3. Hold meter steady and note open window reading.
- 4. Record readings, location, date and time.
III. OPERATION OF E-520 GM TUBE SURVEY METER A. DESCRIPTION The Eberline E-520 is an external GM tube probe plus internal tube portable survey meter. The external GM tube has 4 linear ranges of O 0-0.2, 0-2, 0-20, and 0-200 mR/hr. It utilizes two "D" batteries and weighs approximately 4-1/2 lbs. Its energy response is linear from 0.2 to 2 MeV. With alkaline or NiCd batteries, it can be operated fron -40'F to +140*F. The external detector outer wall is approximately 200 mg/cm2 and the inner wall is 30 mg/cm2 An external speaker is available for use with this meter.
B. GENERAL INSTRUMENT CHECKOUT
- 1. Turn the function switch to BATT. The meter should read in the
! BATT OK re'gion, i
- 2. Set the function switch to one of the five sensitivity ranges.
1
- 3. Wait 15 seconds for full meter response.
14 of 26 Rev. 0 I
EP IV-110-B
() Attachment 4 C. TO PERFORM A DOSE RATE SURVEY NOTE This GM tube survey meter may saturate (and read zero) in a radiation field in excess of 1000 R/hr.
NOTE The high range detector (0-2000 mR/hr) is located in the meter case and not in the hand held probe.
- 1. Hold E-520 at waist level (approximately 1 meter above ground).
- 2. Hold meter steady and note closed window reading.
O 3. Hold meter steady and note open window reading.
- 4. Record readings, location, date and time.
IV. OPERATION OF SAM-2 DUAL SINGLE CHANNEL ANALYZER (with 2" x 1/2" NaI crystal)
A. DESCRIPTION The Eberline SAM-2 is a lightweight (7 lbs.) two channel gamma spectrometer which is stabilized to correct automatically for gain changes (caused by temperature changes, etc.). It can read out each channel independently or the sum or difference of both channels on either a scaler or ratemeter. It will operate from either a 110 volt AC outlet or its own 8 pound battery pack. It utilizes a 2" x 1/2" Sodium Iodide crystal which, with its lead O
15 of 26 Rev. 0
EP IV-110-B
\ Attachment 4 shield collar, weight about 8 pounds. This counting system is designed to operate from 32*F to 140*F. It has both a preset timer and a manual timer. It is fused for both AC and DC operation.
CAUTION The Sodium Iodide probe is fragile and should be handled with care. The sodium Iodide probe should not be taken through rapid temperature changes, it may crack if brought from 30' to 60* without some thermal wrapping to slow down temperature equilization.
B. OPERATION
- 1. Utilize a gamma survey meter (low range) to find as low a back-ground area as practicable (0.5 mrem / hour) in which to perform
{>y the counting functions. If background is greater than 0.5 mrem / hour, provide shielding as necessary.
- 2. Plug cord into 115 VAC, 60 Hz power source or connect to battery power through BATTERY connector (pin 1 negative, pin 2 posilve).
- 3. Connect detector.
- 4. Turn power switch to ON and, if battery pack is used, insure BATT OK light is on. Allow the instrument to warm up for at least 10 minutes. A 20 minute warm up period or longer will provide optimum stability results.
- 5. Set controls as follows:
a) STABILIZER-ON (rear of instrument) b) H.V. ADJUST - 8.00 (or at least 1/3 of the way onto the high voltage plateau).
7-(./
16 of 26 Rev. 0
\
\ EP IV-110-B
() Attachment 4 c) Both THRESHOLDS - 10.00 d) Both IN-OUT to OUT e) DISPLAY - ON f) TIMED-STOP-MAN - STOP q) CH1 to +, CH2 to OFF
- 6. Press RESET-START switch. The display should be all zeros.
- 7. Operation Check N
~
a) Set TIMED-STOP-MAN switch to TIMED. 3 b) Set COUNT TIME IN MINUTES switches to 1 and X.1. Press RESET-START switch. Unit should stop counting after 6 seconds, registering 4500 - 8500 counts (no background).
c) Under the above conditions, the rate mete'r should read 45000 to 85000 counts per minutes. k O
- 8. Counting Iodine-131
/
a) Care must be taken not to contaminate the detector with samples.
The face of the detector may be covered with a thin plastic
\
sheet (i.e., saran wrap, etc.) and fastened with a rubber band.
b) Set thresholds and windows, for both channels,'to the values
~
posted in the instrument case. ,
c) Set CH1 switch to "+" and CH1 WINDOW to "IN".
d) Set CH2 switch to " " and CH2 WINDOW to "IN".
e) Set COUNT TIME to 1 minute (1 and X1). Set COUNT to "TlMED".
f) Press START button.
g) Count background for one minute. If background is greater'than 500 cpm, provide additional shielding (if practicable). If the number is less than zero, as evidenced by a seriestof nines, then minor adiustments of the channel 2 window will correct 1
this, usually clockwise to increase the count and counter-
) clockwise to decrease the count.
i -
17 of 26 Rev. 0 1
\
t w r i
iS l
b l
EP IV-110-B
/
V) Attachment 4 h) Place a Ha-133 source on the face of the detector and pres the
; reset-start button for one count.
ll. i) Using the formula: cpm 1.2 and the results from h, determine source dpm I
the efficiency. This number should be + 10% of the I-131 EFF posted on the SAM-2 case.
NOTE 1.2 is a correction factor to allow for the difference in energy abundancies between Ba-133 and I-131.
j) Remove the source and count background for 5 minutes (set count time to 5 and X1), record this value.
k) Place saran wrapped samples on detector face and make 5 minute
') counts (divide by 5 to get cpm), record these values.
- 1) Carefully mark and save all samples for later laboratoary evaluation. Wrap samples in clean saran wrap or equivalent (e.g., surgical gloves) for storage. If sample is to be saved it must be properly identified and a log kept of sample information (Attachment B should suffice).
NOTE Samples should be stored in a suitable area which will not cause a significant change in background radiation levels.
If sample causes a high radiation area *O he formed in the immediate area, then a suitable storage un 3hould be used (e.g., lead bricks in rear of vehicle). After delivering samples to EOF, the samples should be stored in a locked
, storage area.
O V
18 of 26 Rev. O
_b _ .--- --
EP IV-110-B
() Attachment 4
- 9. Calculate Airborne Il31 activity as follows:
a) Divide the Net cpm (background subtracted) by the efficiency factor from step i abcVe to get a reading in dpm.
b) Multiply the reading (in dpm) obtained in 9.a above, by 4.5 x 10-7 uCi/dpm to obtain a reading in uCi.
' c) Multiply the sampling time (minutes) times the sample flow rate (ft3 / min) times 2.832 x 10-4 cc/ft3 to find the total sample volume (in cc).
d) Divide the total I131 reading of step 9.b above (uCi) by the total sample volume (in ec) found in 9.c abo, to get total activity in uCi/cc.
e) Record the following information:
Emergency Station No. Date/ Time Sample Counted I131 Activity: uCi/cc Date/Tme Sample Taken
- 10. Refer to Figure 4-1 to obtain thyroid dose rate.
(
- 11. Alternate Method Pefer to Table 4-1 to determine a quick estimate of concentration and thyroid dose rate based on an assumed EFF.
- 12. Communicate SAM-2 results and derived dose rate to TSC.
V. OPERATION OF TFF EBERLINE RM-14 COUNT PATE METER WITH PROBE (HP-210)
A. DESCRIPTION The Eberline Radiation Monitor (RM-14) is a count rate meter which is commonly employed as a frisker at control points when used with a pancake type probe. For use as a count rate meter, a HP-210 pancake probe is employed. This instrument can be used to count particulate filter samples, charcoal or silver zeolites for I-131 concentration determinations. It should be noted that the gamma O efficiency of the HP-210 probe is significantly lers than that for the ED-19 probe (SAM-2) . The HP-210 can also detect the beta emissions from I-131, however, the minimum detectable activity for I-131 using the HP-210 probe is considerably greater than that 19 of 26 Rev. O
EP IV-110-B
() Attachment 4 obtained using SAM-2/RD-19 instrumentation. It should also be noted that the RM-14/HP-210 is incapable of discriminating between different energy isotopes. The use of silver zeolite for sample collection does improve this condition.
B. GENERAL INSTRUMENT CHECKOUT
- 1. Energize the RM-14 by plugging the power cord (which exits the instrument chassis at its rear) into a 120 VAC supply. Then switch the five (5) position rotary switch from "off" to one of the three (3) counting ranges (X1, X10, X100).
- 2. Connect the HP-210 probe de*.ector using its coaxial cable to the terminal at the right hand corner of the face of the instrument.
% 3. Place the rotary switch to the "X10" position, flip on the test toggle switch to on (located on back of instrment chassis), the count rate should rise to 3600 cpm + 10%. If the instrument "on test" reads in this range, the instrument should be in good working order.
- 4. When operating with batteries (no AC power available), turn rotary switch to "BATT" position to see if battery charge is within proper charge range (indicated on instrument scale).
C. COUNT RATE METER OPERATION
- 1. Using sample holder or generally applied counting geometry, record background count rate.
- 2. Using check source, read and record count rate.
- 3. Sample Type: Particulates: Place the filter in the holder or O preferred geometry, then read and record count rate. Allow 20 of 26 Rev. 0
EP IV-110-B
() Attachment 4 instrument reading to stabilize for approximately 5 to 10 j seconds. Charcoals and Silver Zeolites: Place the cartridge into the sample holder or preferred geometry, place the probe onto the cartridge, read, and record count rate.
Particulate Filters: uCi/cc = Net cpm x 1.6E-ll* x 1 sample volume (ft3) efficiency Cartridae Filters: uCi/cc = Net cpm x 1.6E-11* x 1 sample volume (ft3) efficiency
)
NOTE Background and source checks should be made approximately once O per hour or as appropriate between large number of sample counting runs.
*l.6E-ll is the product of the conversion factors for uCi/dpm and cc/ft3 1
i O
21 of 26 Rev. O i
i EP IV-110-B ATTACHMENT 4 VI OPFRATION OF TFE RADECO H-809C PORTABLE AIR SAMPLER A. DESCRIPTION The Model H-809C portable battery powered air sampler is designed for collecting air samples in field areas where electrical power is not conveniently located. The Model H-809C consists of a dual-stage turbine blower directly co upled to a DC motor. Battery clip leads are supplied for attachment to a 12 or 24 volt battery.
B. TO OPERATE AIR SAMPLER
- 1. Place the iodine cartridge and filter paper into the standard RADECO filter holder. Screw the filter holder into the air sampler inlet.
- 2. Connect battery clips to behicle battery ensuring positive clip is attachead to positive termin:1. Switch the sampler power switch to the "on" position.
- 3. Obtain a 40 cubic foot sample; approximately 4 cfm for 10 minutes. Read indicated flow rate on rotometer.
NOTE: Smaller volume samples may be requested by the communicator at the EOF.
- 4. Turn off unit when sampling is complete.
- 5. After counting sample, place cartridge and filter paper into separate envelopes and mark each envelope with the following information:
Emergency Station No: Date:
Sample Start Time: min Sample Stop Time: min Sample Flow Rate: ft /3 min Tech:
Record sample data on the Emergency Survey Log.
A U
22 of 26 Rev. 0
l t
i EP IV-110-B Attachment 4 O PSE&G FIELD SURVEY TEAM DATA IODINE DOSE RATE CALCULATION
, a) Sector and distance b) Time of sample c) Field team name d) Instrument eff. (demical)" !
e) DPM above background f) Sample volume (ft 3) i
; g) (e) t (f)x(1.6E-11)'*x(1/eff)= uCi I-131/cc i h) Child thyroid dose rate from graph mrem /hr
!
- Ffficiency obtained from calibration sticker on instrument.
The default value for efficiency is 0.025 (1/eff = 40) l ** 1.6E-ll = (4,50 E-7 uCi/dpm) x (3.53E-5 cubic feet /cc) i i uCi/cc IODINE-131
! 9 i i . , , ,, y - . . . . .P - 8 . . . . . . . .M-7 . . ., .P-6 . ..M.5, 7 ,
j s i s
i .
! 3 1
! a 4
1,000j
! a 1 . i% sxn m = -; m s .
{' 2 . - - - + . . . -
- ug ----
===_r-p3 :t a g = = x =-2w. = = - - ,
3 s
; N .
n H 3 o .._ _] CHILD ETEEN 3 3
- o EET J
$ 100 s
3 I . _, n :n;4:i r -- i 3 a:
8 r= ri :-== e!-r:nn -': . . _s .
4 3
a 1
l O' 23 of 26 Rev. 0 2
---__..--.__-----,.----.__,..,..__,,,-.-,,.--n,,,-,--.w.--, ,.. - n.,-. ,_ ,.- n ,,
/
EP'IV-110-B ATTACHMENT 4 TABLE 4-1 REM DOSE TO THYROID FOR 1 HCUR EXPOSURE SAM-2 cpm DCi/cc* Infant Non-Occu-and pational Working Above Background (assuming I ft3 and 2.5% off) Child Teen Adult Adult 1 x Ins 6.4 E-5 118 los 87 131 5 x 104 3.2 E-5 59 54 44 65 1 x Ifd 6.4 E-6 12 11 9 13 5 x 103 3.2 E-6 6 5 4 7 1 x 103 6.4 E-7 1.2 1.1 0.9 1.3 5 x 102 3.2 E-7 0.6 0.5 0.4 0.7 1 x lo2 6.4 E-8 0.12 0.11 0.09 0.13 50 3.2 E-8 0.06 O.05 0.04 0.07 10 6.4 E-9 0.01' O.01 0.01 0.01
.l
*To correct for actual sample volume divide tabulated pCi/cc value by the actual volume in cubic feet.
24 of 26 Rev. O
EP IV-110-B ATTACHMENT 5 CHECK-OFF LIST FOR OFF-SITE MONITORING TEAMS
(
- 1. SAM-II Assay Meter Equipment (optional)
- a. SAM-II Meter
- b. Shielded RD-19 Detector
- c. Detector Cable
- d. Cigarette Lighter Power Cord
- 2. Two (2) Dose Rate Meters
- a. Ion Chamber - PIC-6A or RO-2
- b. G-M Meter - E - 520
- 3. Spare 9 Volt Transistor and "D" Cell Batteries
- 4. Low-Volume Air Sampler - Radeco H809C with Battery Cable Filter Holder
- 5. Charcoal Cartridges
- 6. Silver Zeolite Cartridges (OPTIONAL FOR DRILLS)
- 7. Filter / Smear Paper
- 8. Paper Coveralls O 9. First Aid Kit
- 10. Procedure / Form Kit - Contains:
- a. Procedures EP-IV 110 A & B
- b. Multiple Copies of Attachment 2
- c. Multiple Copies of Attachment 3
- d. pad of Paper
- e. Pen and Pencil
- f. KI Tablets
- 11. Shoe Covers (protective)
- 12. Caps
- 13. Protective cloves (Surgical or Rubber) 14 Small Fnvelopes for Used Filters
- 15. Masking Tape
- 16. Small plastic Bags
- 17. Wipes (e.g., Handi-Wipes, Lab-Wipes)
) 18. Salem and Cumberland County and Wilmington Area Map Above Issued in Kits 25 of 26 Rev. 0 l
EP IV-110-B Attachment 5 Separate Issue
- a. Self-Reading Dosimeters
- b. TLD's
- c. Respirators
- d. Lead Blankets and/or Bricks
- e. Lantern Flashlights
- f. Dosimeter Charger O
l ;
i l
O t
I 26 of 26 Rev. 0
EP IV-lli O -
EMERGENCY PROCEDURE EP IV-lll EFFLUENT DOSE CALCULATIONS ACTION LEVEL This procedure shall be implemented upon the request of the Senior Shift Supervisor /EDO/ERM or the Radiation Protection l staff.
The calculations shall normally be performed by the Radiation Protection personnel in the TSC or the Radiological Assessment Staff at the EOF. At the TSC, the primary individuals responsible for the initial calculations will be the Shif t Radia-tion Protection Technician (Shift RPT) and the REP /ALARA Super-visor.
LIMITS OF AUTHORITY Projected off-site dose estimates should be forwarded to the Senior Shif t Supervisor /EDO/ERM, the Radiation Protection Engineer (RPE) and the Rad.iological Support Manager (RSM).
Transmittal of the projected doses shall require the prior approval of the Senior Shif t Supervisor, RPE, or RSM. l If re-entry into the affected area is required for effluent determination, consideration shall be given to the potential for encountering high dose rates. Approval of the Radiation Protec-tion Engineer and the EDO shall be obtained prior to entering the penetration areas.
ATTACHMENTS No. 1 - Xu/O Value Determination g
es No. 2 - (a) & (b) Noble Gas / Iodine Dose Conversion Factor (K)
( ,/ vs. Decay Time 1 of 25 Rev. 2
t l
EP IV-lli ATTACHMENTS (cont.)
No. 3 - R43 Concentration Conversion Factor vs. Decay Time No. 4 - Default Values for Low /High Plant Vent Monitors No. 5 - Containment Monitor R21 Response vs. Dispersion Factor No. 6 - Survey Meter Response vs. Main Steam Activity No. 7 - Unit Analysis of Off-Site Dose Calculations No. 8 - Dose Calculation Sheet l ACTION STATEMENTS
- 1. Contact the Control Room and obtain a briefing on the incident and identify the probable pathways for release of radioactive material.
- 2. Determine which sections of this procedure are appropriate for the particular release.
TYPE OF RELEASE PAGE A. Releases from PLANT VENT (Elevated Release)
- 1. Unit 41 3
- 2. Unit #2 7 B. Unmonitored releases from: (Ground Release) 11 i 1. POWER OPERATED RELIEFS
- 2. AUTOMATIC RELIEFS
- 3. STEAM DPIVEN AUX FEEDWATER PUMPS C. Releases due to CONTAINMENT LEAKAGE 14 (Ground Release)
D. Release Rate Calculation
- Attachment 8 l
l
*See too left corner of Attachment 8 for release rate O determination calculation.
2 of 25 Re v. 2
EP IV-lll O A .1 PLANT RELEASE FROM UNIT NO. 1 A.l.1 Contact the Control Room and ensure that 1R-llA, 1R-12A and IR-12B are in the " Plant Vent" mode. If they were not, allow sufficient time for the channel readings to atabilize.
A.I.2 Record the following plant parameters for subsequent calculations.
VALUE AFTER METER HAS BEEN IN THE VALUE WHEN METER METER PLANT MODE FOR IS FIRST PUT IN VALUE AT FARAMPTER NUMBER TIME, TX PLANT MODE SELECTED TIME
- a. Low Range Gaseous IR-12A cpm Release Rate
- b. High Range Gaseous R-43 mr/hr Pelease Rate
- c. Iodine Release Rate 1R-128 cpm (Cx) cpm (Co) time (Tx) time (To)
F1 ')w cfm OPlantVent(1)
Rate
- o. A Temp (2)(4) at 4t C*
Elevation (ft)
- f. Elevation ft
- q. Wind Speed (3)(4)(5) aph
- h. Wind Direction (4)(5) e (from)
- 1. Shutdown Time hr
- j. Transport Distance for mi Calculation NOTES:
(1) If plant vent flow rate is unobtainable or cannot be estimated, assume 125,000 cfm.
(2) If the (3noC)-(33C) is unobtainable to determine the at use the (150'*C)-(33C) reading. If this is unavailable refer to Note 4 and note chosen elevation.
(3) If the wind speed is unobtainable, assume 5 mph.
Use Elevation 300' data for an elevated release.
Use Elevation 33' data for a ground release.
(4) Backup meteorological data f rom Wilmington Airport (302-323-2280 or NAWAS Line) including wind speed, wind direction and an estimated stability class. If the estimated stability class is not available, asstane conditions to be stable.
O) Average data over 15 minute period from the strip chart recorder in the control room.
O 3 of 25 Rev. 2
EP IV-lll A.1 PLANT RELEASE FROM UNIT NO. 1 (continued) l NOBLE GAS CONTRIBUTION TO WHOLE BODY DOSE RATE A.l.3 Lcw range or default values ( Attachment 4)
Noble Gas (ID-12A)(Plant(wina vent speea)
Flow Rate)(Xu/0)(Dose Conversion Factor)(SE-4) =
ares /hr (a )(b )(c
)(d 1(5E-4) =
mees /hr te ;
2,R A.l.4 High Range (R-43)
Noble Gas
= aren/hr (R-43 )(Plant Vent Flow Rate)(Xu/0)(Dose Conversion Factor)(1.05E+3 )
(Wind Speed)(Concentration Conversion Factor)
(f )(b 1(c )(d 1(1.05E+3) = aren/hr l
(e )(9 )
lO
- NOTE
- a. 1R-12A in cpm, or equivalent cpm value from Attachment 4.
- b. Plant vent flow ~ rate in ft3/ min.
- c. Xu/O value from Attachment 1. (1/m2)
- d. Dose conversion factor from Attachment '. ' mrem /hr
\ pCi/m%
- e. Wind speed in miles per hour.
- f. R-4 3 reading in mR/hr.
- g. Concentration conversion factor in mrem /hr Attachment 3.
uC1/cc
(
l l
Calculated By Date Time Reviewed By Date Time :
4 of 25 Rev. 2
EP IV-lll A.1 PLANT RELEASE FROM UNIT NO. 1 (continued)
IODINE CONTRIBUTION TO THYROID DOSE COMMITMENT A.1.5 Determine the rate of increase of iodine activi.ty.
a) Low Range Monitor 1R-12B com = Cx-Co = ( 1-( )= ( IcAn = ( ) cy liiTK YiiT!'o ( 1-( ) ( 1 min min NOTE Refer to Step A.1.2(c).
Z b) Using Default Values Use Attachment 4 to determine the appropriate equivalent cpm / min.
cpm / min A.1.6 Ecuation for 50 year thyroid dose commitment rate O
epm Iodine liiIK (Plant vent Flow Rate)(Xu/0)(Dose Conversion Factor)(3.5E-7) = ares /hr (wino speea)
(a )(b )(c )(d )(3.5E-71 = area /hr te 1 NOTE a, cpm / min from Step A.1.5 (a or b).
- b. Plant vent flow rate in ft /3 min.
- c. Xu/O from Attachment 1. (1/m2) d.
DoseconversionfactorfromAttachment2(b)./ mrem /hr)
(pCi/m3 /
- e. Wind speed in miles per hour.
Calculated By Date Tir.e _
Reviewed By Date Time 5 of 25 Rev. 2
EP IV-lll
, A.1 PLANT RELEASE FROM UNIT NO. 1 (continued)
IODINE CONTRIBUTION TO THYROID DOSE COMMITMENT (continued)
A.l.7 To obtain dose commitment, multiply dose commitment rate by the hours exposed to that rate, (e.g. ,15 mrem /hr X 5 hours exposure = 75 mrem-50 year dose commitment).
1 i
O l 2 l
a Calculated By Date Time Reviewed By Date Time 6 of 26 Rev. 2
EP IV-lll O A.2 PLANT RELEASE FROM UNIT NO. 2 A.2.1 Contact the Control Room and obtain the following plant parameters for subsequent calculations.
VALUE AFTER METER s NAS BEEN IN THE VALUE WHEN METER METER PLANT MODE FOR IS FIRST PUT IN VALUE AT PARAMPTFR NUMBER TIME, TX PLANT MODE SELECTED TIME
- c. Low Range Gaseous 2R-41C cpm Pelease Rate
- b. Nigh Range Gaseous R-43 ar/hr Release Rate c Iodine Release pate 2R-41B cpm (Cx) cpa (Co) time (Tx) time (12)
- d. Plant tent (1) Flow cfm Rate l
l 9 g Ter4(2)(4) At C*
Elevation ft
- g. Wind Speed (3)(4)(5) aph
- h. Wind Direction (4)(5) e (from)
- 1. Shutdown Time hr
- j. Transport Distance for mi Calculation NOTRS:
(1) If plant vent flow rate is unobtainable or cannot be estimated, asstume 125,000 cia.
(2) If the (300'*C)-(33C) is unobtainable to determine the t use the (150'*C)-(33'*C) readir.g. If this is unavailable refer to Note 4. ,
(3) If the wind speed is unobtainable, asetane 5 mph.
Use Elevation 300' data for an elevated release.
Use Elevation 33' data for a ground release.
(4) Backup meteorological data from Wilmington Airport (302-323-2280 or NAWAS Line) including wind speed, wind direction and an estimated stability class. If the estimated stability class is not available, assume conditions to be stable.
(5) Average data over 15 minute period from the strip chart recorder in the control room.
l O
7 of 25 Rev. 2
EP IV-lli O A .2 PLANT RELEASE FROM UNIT 2 (continued)
WHOLE BODY DOSE RATE DUE TO NOBLE GAS A.2.2 Low range o_r r default values ( Attachment 4)
(2R-41C)(Plant Vent Flow RatelfX Dose C on Factor)(2.8E-5) =
area /hr l
I'h II' g,
Ifd )(2.sE-5) =
meen/hr l
2 A.2 3 High Range (R-43)
Noble Gas O (p-43 )(Plant vent Flow Rate)(Xu/0)(Dose Conversion Factor)(1.05E+3 )
(wind speed)(concentration conversion Factor)
=
ares./hr ..
(f 1(b )(c )(d ) (1.05 E+3 ) = area /hr (e )(g )
NOTE
- a. 2R-41C in cpm, or equivalent cpm value from Attachment 4.
- b. Plant vent flow rate in ft3 min. /
- c. Xu/O value from Attachment 1. (1/m2)
- d. Dose conversion factor from Attachment 2(a). mrem /hr uCi/m3
- e. Wind speed in miles per hour.
- f. R-43 reading in mR/hr.
- g. Concentration conversion factor in mrem /hr Attachment 3.
uCi/cc Calculated By Date Time O Reviewed By Date Time 8 of 25 Rev. 2
EP IV-111 O A .2 PLANT RELEASE FROM UNIT 2 (continued)
THYROID DOSE COMMITMENT DUE TO IODINE ,
'A.2.4 Determine the rate of increase of iodine activity.
a) Low Range Monitor 2R-41B ge = Cx-Co = ( 1-( ) = ( Icpm = ( )c min M ( ;-( ) ( } min an NOTE Refer to Step A.1.2(c) .
2 b) Using Default Values Use Attachment 4 to determine the appropriate equivalent cpm / min.
cpm / min O
A.2.5 Equation for 50 year thyroid dose commitment rate enn Iodine mTii (Plant Vent Flow Rate)(Xu/0)(Dose Conversion Factor)(3.35t:-7) = mrom/hr (wana speeaj (a )(b )(c )(d )(3.35E-7) = arem/hr (e >
NOTE
- a. cpm / min from Step A.2.4 (a or b).
- b. Plant vent flow rate in ft /3 min.
- c. Xu/O from Attachment 1. (1/m2)
- d. Dose conversion factor from Attachment 2(b). mrem /hr uci/m3
- e. Wind speed in miles per hour.
Calculated By Date Time Reviewed By Date Time 9 of 25 Rev. 2
EP IV-111 A.2 PLANT RELEASE FROM UNIT 2 (continued) l THYROID DOSE RATE DUE TO IODINE (continued)
A.2.6 To obtain dose commitment, multiply dose commitment rate by the hours exposed to that rate, (e.g., 15 mrem /hr X 5 hours exposure = 75 mrem-50 year dose commitment) .
O Calculated By Date Time O Peviewed By Date Time 10 of 25 Rev. 2
I EP IV-lll B. RELEASE RATE DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS
! B.1 If control room personnel have determined a primary leak exists i
in one or more steam generators by one or more of the following indications:
a) Air Ejector High Radiation Alarm b) Uncontrolled increasing level in Steam Generator c) Increasing steam pressure in one Steam Generator d) High Activity alarm in the steam generator blowdown system with or without an isolation then the Senior Shift Supervisor shall initiate monitoring of the affected steam lines upstream of the isolation valves to estimate the microcurie content per cc of steam in the affected steam lines. This action is required if the potential exists for a relief valve lifting, a power operated relief being
(} opened or the operation of the steam driven Aux. Feed Pump attached to the affected Steam Generator (11 & 13)(21 & 23).
B.2 Prior to radiation protection personnel entering the penetration areas to measure the contact dose rate on the affected steam lines, the Senior Shif t Supervisor /EDO and the Senior Representative from radiation protection will evaluate and determine the potential for high radiation areas being encountered in the penetration areas for the following reasons:
a) Reactor malfunction resulting in fuel damage b) LOCA resulting in fission products being rel. eased to con-tainment resulting in radiation streaming through containment penetration.
11 of 25 Re v. 2
-~ EP IV-lll U. B.3 If any of the above conditions are present, specific action points must be established in accordance with EP I-17 to determine the following requirements.
a) Total dose accumulation for operation b) Maximum dose rate field to enter c) The types of dosimeters and instruments to use d) The type of protective clothing and equipment to be used B.4 Enter affected penetration crea or location and measure the contact dose rate on the affected steam line or Aux. Feed Pump exhaust line.
a) The contact dose rate measurement can be made with any dose rate instrument having a range of 0.1 to at least 10,000 mR/h r.
b) If it is expected that the background in the affected penetration area will be greater than 10 mR/hr a dose rate instrument with a shielded probe should be used.
c) Dose rates should be taken at the indicated location marked on each steam line.
d) Record the contact dose rate on pipe.
mR/hr B.5 Use the contact dose rate corrected for background radiation to determine the uCi/cc concentration in the pipe of concern from Attachment 6.
pCi/cc B.6 Use the following flow rates to determine steam release rates:
a) Power operated relief valve 450,000 lb/hr
( b) Relief Valve 800,000 lb/hr each c) Aux. Feed Pump exhaust 50,000 lb/hr 12 of 25 Rev. 2
EP IV-lll O. R. RELEASE RATE DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS (continued)
B.7 Multiply the pCi/cc from B.5 and the proper flow rate in Ib/hr from B.6 to determine release rate in UCi/sec.
(pC1/cc) (lb/h r) (3. 3 ) = pCi/sec (a )(b )(3.3) = pCi/sec
- a. uCi/cc from Step B.S.
- b. Ib/hr from Step B.6.
B.8 Whole body dose rate due to noble gas releases mrem /hr = (uci/sec)(Xu/0)(DCF)( 2.22 )
(Wind Speed - El.33')
mrem /hr = (a )(b )(c )(2.22)
(d )
NOTE
- a. uCi/sec from B.7.
s b. Xu/O in 1/m2 from Attachment 1.
- c. Dose conversion factor from Attachment 2(a). mrem /hr pC1/m4 ,
- d. Wind speed in miJes per hour (EL. 33').
1 B.9 Document total run time for the steam driven Aux. Feed Pump.
l B.10 Document the total period of time the relief and power operated l relief valves were open on the affected steam generator.
B.11 The number of times the relief and power operated relief valves are open on the affected steam generators are limited as per Emergency Instruction I-4.7.
Calculated By Date Time
()ReviewedBy Date Time 13 of 25 Rev. 2
, C. RFLEASES FROM CONTAINMENT LEAKAGE r i
NOTE This dose determination assumes a design basis containment leak rate (La). Actual containment leak rates may be more or less. This dose determination is a postulation and should be used as such. Field monitoring results are preferable.
C.1 Contact the control room and obtain the reading on the high range containment radiation monitor either R-44 (Unit 1) or 2R-21 (Unit 2).
R/hr C.2 Using Attachment No. 5, correlate the meter reading to the vertical axis and determine the base X/Q from the horizontal axis.
base X/O C.3 Determine the actual Xu/O using Attachment 1.
i actual Xu/Q C.4 Determine the 24 hour dose.
(Actual Xu/0)(2.22) = 24 hour dose in rem (Wind Speed - El. 33')(Base X/Q)
(a )(2.22) = rem (b )(c )
NOTE
- a. Acutal Xu/O from Attachment 1.
- b. Windspeed in miles per hour (El. 33').
l c. Base X/O from Attachment 5 (correlated to containment monitor).
l Calculated By Date Time Reviewed By Date Time 14 of 25 Rev. 2
,e- --
-- - = - g- y---,, ww--- m- r- ,---, -.w--- --y-,-----m .,yp*- - - - ,- + - . -- ..--.--m - y----------rr-i- -- --
EP IV-111 NOTE Forward all completed forms to the Nuclear Emergency Planning Engineer. Attach other completed EP's or attachments used.
Prepared By: M f/
Peviewed .
9 73 N
/ Department Head 'Date Reviewed By: A Im f- / J- p 2.
Nucle #ar Emergency Planning N gineer Date Feviewed By:
3W StationQualit/Assu nce Review Date' (if required se EP VI-2)
~ '
SOFC Meeting No.: q lDate' Approved By: / h
Mk3/f#
General Man'ager - Salem Operations Date f
Approved By: 9 f 2--
Manager - Nuclear Site Protection Date 15 o f 25.
Rev. 2
EP IV-lli ATTACHMENT 1 Attachm: Int 1 Xu/O VALUE DETERMINATION
^Calect the Xu/n values that correspond to the stability class as determined by the f temperature, f ictance from the site and the release point (ground or elevated).
. USE THE d TEMPERATURE VALUE FROM THE METEOROLOGICAL TOWER TO DETERMINE STABILITY CLASS.
Primary Instrufnent NOTE 300 f t. - 33 f t. temperature ('C)
UNSTABLE IS 1 -1.3'C UNSTABLE l NEUTRAL iSTABLE NEUTRAL IS > -1.3*C 1 -0.5'C
-1.3 -0.5 STABLE IS > -0.5'C Packup Ins trtament NOTE 150 ft. - 33 ft. temperature ('C) UNSTABLE IS 1 -0.6*C UNSTABLE l Nf*; TRAL l STARLE NEUTRAL IS > -0.6*C 1 -0.2*C ,
STABLE IS > -0.5'C
-0.6 -0.2
- 2. DISTANCE CPOUND LEVEL RELEASE (E-6/m2) ELEVATED LEVEL RELEASE (E-6/m2)
METFPS MILES UNSTABLE NEUTRAL STABLE UNSTABLE NEUTRAL STABLE 1000 0.62 15 61.39 244.8 18.28 45.1
- 1270 MEA 0.79 9.95 41.5 227 12.4 42.2 **
2000 1.2 4.64 22.49 168.0 6.13 27.99 .017 3000 1.9 2.32 12.20 113.3 3.12 17.26 .793 4000 2.5 1.42 7.86 81.7 1.92 11.72 3.54 5000 3.1 .968 5.58 62.3 1.31 8.55 7.22 6000 3.7 .708 4.21 49.5 .963 6.56 10.48 7000 4.4 .543 3.32 40.5 .740 5.23 12.81 A000 49 .432 2.70 34.0 .589 4.28 14.26 8045 LPZ 5.0 .42 2.5 33.3 .57 4.06 14.3 9000 5.6 .353 2.25 29.0 .481 3.50 15.02 10000 6.2 .294 1.91 25.2 .402 3.06 15.29 11000 6.8 .250 1.65 22.1 .341 2.65 15.23 12000 7.5 .215 1.44 19.6 .294 2.32 14.95 l 13000 8.1 .187 1.27 17.6 .256 2.05 14.55 14000 8.7 .165 1.13 15.9 .225 1.83 14.06 15000 9.3 .146 1.02 14.4 .200 1.65 13.54 16000 EPZ 9.9 .131 .952 13.2 .179 1.49 13.01 MEA - Minimum Exclusion Area LFZ - Low Population Zone EPZ - Emergency Planning Zone .,
*value of xu/O for 1000 meters distance = 5.33E-16/m2
**Value of xu/O for 1270 meters distance = 1.35E-12/m2 etance Xu/O = F-6/m2 (ground) Xu/O = E-6/m2 (elevated) l 16 of 25 Rev. 2
, , , , , - , . -r-r -
- m. .. . . .
Attact4 2(a)
Att. 2(at O O.B - 5 0 0i SHUTDOM BASED ON EPA-520/1-75-001; 3200 W THERM 4L AT EeulLISAION HOTE: INGROUTH OF GASEOUS DAUGHTERS INCLUDED IN 00$E RATES l 0.S -
A. Time f ran shutdown to time of release in hours = g B. Time for transport = (Desired Distance)/(Wind Speed) j M
( mi)/( mph) =
/ 0.4 hr H l C. Total decay time = (Step A) + (Step B)
R I I+I I "
/ hr y y i D. Correlate the total decay time (hours following shutdown)
.i a C to the curves to detennine the dose conversion factors I
O.3 -
for Noble Gas.
- w /
! o N M I ,
i 0.2 -
.l i
l
! 0.1 -
i i
- 38 M l
' I y5 i O.0 ' 4 I I I l l I l l i E
0 10 20 1
l g 30' 46 50' 50 hhr TOTAL DECAY TIME - IlOURS I
l O Attagc nt 2. (6)
Att. 2m O l
3000 - IODINE DRCF FOLLOUING REACTOR SHUTDOUM l
l BASED ON EPA-520/1-75-0013 3200 MU THERMAL AT EQUILIBRIUM I 2900 DRCF'S FROM REG OUIDE 1.1093 HORMALIZED TO I-131 CONC OF 1 UCI/M**3 l
I-TOT DRCF=2928.1-( s0. 02987 )+ ( 1. 6723*T**B )-( 0. 04003s*T**3 )
,,,, _ +(s.34e9E-4*T**<n-(a.aTs?E-e*T**s>
i M 2700 -
R 1
E I-707 DRCFs NORMALIZED TO 1 UCI/M**3 I-131
)2600 -
H I R i
A. Time fran shutdown to time ]
i /Es00 -
of release in hours =
hr i E U B. Time for transport = (Desired l $ C Distance)/(Wind Speed) g I2400 -
( mph)
/ ~ mi) / ( -
hr k N C.
" *2300 -
Total decay time = (Step A)
* # + Step B) 3 , I I+I I "
hr i
! Correlate the total decay time (hours
; 2200 -
i i L i following shutdown) to the curves to determine the dose conversion . factors for Noble Gas.
1 2000 -
l !
I I
>m 1900 l '
I I I I I I I I I I O 10 N 20 30 40 50 e
TOTAL DECA 7 TIME - IIOURS 60
] i
_ ~ _ _ _ _ _
O O O Attachment 3 55 - R-43 CONCENTRATION CONVERSION FACTOR FOLLOWING S!!UTDOWN BASED ON EPA-520/1-75-001; 3200 MU THERMAL AT EQUILIBRIUM NOTE: INGROUTH FROH PARENT. ISOTOPES HOT INCLUDED
50 - c' 45 - ' '
l 40 - l
~
N '
{
1
$ 35
- ~
- H -
R -
j / 30 I ' '
i
' U .
s-
- 2 C >
l '-
, ; I 25
/
[ C l o C EO -
~
i m _
w ' -
J w -
i 15 - i i -
i '
, 10 :
l 5 -! ;
~
i l f _
O L'
; I' I I I I I I I I I - I I >M
- o 0 - 10 20 30 40 50 60 h
w HOURS FOLLOUING SHUtDOUM _
*E u
i H 1 ,- H
,1 .-
_, H i
m
i d i
EP IV-lll ATTACHMENT 4 DEFAULT VALUES FOR LOW /HIGH PLANT VENT MONITORS Read the below accident description and determine which case is applicable. From the table select the apprcpriate release rates (cpm). j CASE I LOCA A LOCA assuming severe core damage - fuel melting (Regulatory Guide 1.4 assumptions) 100% of noble gases and 25% of the iodines contained in the core are assumed released to the containment. The containment initially leaks at the maximum design leak rate.
CASE II LOCA 1
Primary coolant leaks at a rate fast enough to increase the temperature of the core to the point where there is damage to the
, fuel rods. For this case, it is assumed' that all the gap activity (the gases contained between the fuel and fuel rod) is released to the containment. The containment is assumed to initially leak at the maximum design leak rate. In this accident, it is up to the Senior Shif t Supervisor or Emergency Duty Of ficer (EDO) to assume that there has been no fuel melting. If there is any question, a CASE I LOCA should be assumed.
)
CASE III DECAY TANK RUPTURE This procedure is used only if actual radiological monitoring 4 equipment is unavailable for release evaluation (monitors out of service, read off scale, etc. ) .
CASE IV FUEL HANDLING ACCIDENT 1
Any activity occurring as a result of a fuel handling accident is normally drawn into the Fuel Handling Building Ventilation System and vented to the plant vent for release. The process monitors are used to monitor these releases; however, should these monitors be out cf service or off scale, this technique is used to evaluate off-site dose.
CASE V STEAM GENERATOR TUBE RUPTURE The activity released during a minor tube rupture can be determined using vent monitors and normal procedures. "his procedure addresses the steam generator tube rupture as analyzed in the FASR. This accident is set apart from others because of the inability to consult radiation monitors to determine the activity release rate.
Therefore, this is the primary procedure to determine the activity release rate resulting from a steam generator tube rupture.
O 20 of 25 Rev. 2
EP IV-lll ATTACHMENT 4 (continued)
EQUIVALENT IODINE EQUIVALENT NOBLE CAS ACTIVITY INCREASE RATE ACCIDENT CLASS RELEASE RATE CPM CPM / MIN UNIT 1 UNIT 2 UNIT 1 UNIT 2 I(1) 2.42 E5 4.34 E6 9.35 E6 9.73 E6 II(l) 7.82 E2 1.40 E4 1.45 E5 1.51 E5 III(l) 1.25 ES 2.24 E6 NO RELEASE NO RELFASE IV(1) 9.9 E4 1.78 E6 1.22 E6 1.27 E6 I V(2) 1.42 E4 2.54 ES 3.3 E6 3.50 E6 (1) Use actual or estimated plant vent flow (cfm) as provided in the procedure.
(2) Case V is assumed not released through the plant vent so use a flow of 125,000 cfm for this calculation.
O i
i
\
l l
t
~
21 of 25 Rev. 2
EP IV-lll ATT. 5 ATTACHMENT 5
, CONTAINMENT MONITOR (lR-44/2R-21) VS DISPERSIO'N FACTOR I
. DISERSION FAC10R (X/Q - SEC/ ) ,,
10-5 .10 4 10-3 10-2 g l,,nEN5kih iskhNfSIObMihii=d!AiiiMQiih[
e 5 . = . = -
-_j.,
4 [h g_N +. :_.-
=m h_ U -
b= =hdb r N:- d __ b--h p_ --
hh=: _g_- _ _ _ '_ _ f =. _
,=-- ==-
-W_m== 7==+3 2
=m;;;========h=r.:===- =;========-t=== _
10 a g. _ -
, = _, ; _ _._ -_ .__ -
6;W=Mk*ksi k -kM=hdiv+ & musu-= 4s &=
= _
=
~
m 1 -
_ === _ _ ==- .=_
_= = mm _= __ -_m _-- g .m __
= , , ,, _ _
3 L
hi .
g ,
l e.
O , , , ; . , , .,, , ,
I -
,,i i,.,,
l lE i:92idisn*NisE
, == = -m== _
nn, =indiEEbis-d, M AEENSEEuni
- - - - ~ = = = = = = = = = = = = - ==
~- -
6 Sis;bsbs$$_nf 5!$5$$24sd5d .
N25L 152$_ _
'l NOTE FFSITE DOSE OF 1 REM IN 24 HOURS FOLLOWING A LOCA AS DETERMINED BY CJ R-21 RESPONSE AND X/0.
i l Page 22 of 25 Rev. 2
- EP IV-lli ATT. 6 p ATTACHMENT 6 6' SURVEY METER PESPONSE VS, MAIN STEAM LINE CONCENTRATION 10-3 10-2 1g-1 100 101 102 l
. . . . . . ...? = * ' ~ .
. . . . . . . . .! * * * '"a ,
105 :
a
--.a
= ' ' -
g J- I l
.4 -. M .1 . ' IJ 1 mg
. r T- s-- - . - -:-.
g m;4 p -M;4t" ","4 m ll PME "_. pin-,ibl e .J1- r., 4.m.M- . I-f.
. =: au. = . =-= --
.m n. = ~ .-.iq,-4..,
.--n--~ <; ,.
g y .p a.- I h MAF -
T I
- n = ~,-+ -
, -. =c = . ,.
~.:~r-=-
L-E2EAfR = "41 --H .Tm. = wJ-M
-'~~
5N"~
' . ' .I : =_r"".*/.' _.~.W g = S. L' i a f
-=-ww . .-
.,.. _ _ 7__ __, __ -M___.--EE.T
- -- - - = ._. . .. _-. .. _ .- -
10 4 ,.
M ME
- =-
= . : . :
, = - ._ . . m .. . . - . - , :,
g_ T_'- - _-' 4_ 4 I Ii { j r.5 .-_ A = J _' 3 3l /~~_- . z I- . i ' l _* ? . } "
.T*' I [d f - ._ I _ 1 *
'i.z- s . - + %.-4._i Ep.4 . Eus: =-.1,1.3 T- 3' . r.la. ' (! i . [~ 6 i ] } i .2ai
, i upa
, ;.. ,rj 4 fa- 9 4,. s sf 4 ..
g ., _ , ,
.. , , --w .t1 .m ~_-._
_c_ .
.w-. n .= . a,e._. _ 1
-s, uu., r- . , . .
_..J @H f d*-
g 5 5'I_ -'E--l -
.'.s.4 M-- a-% _ _
} . 3 ~ _4 fi , f _.
jf f q - F i
_=-.=.m x.__. = n:w .-mm= -= r_ w
" ~
.IM W r.-%IIui==w= M:X.~
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~
g; 10 3
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. ,:2 . ,
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n
,- w.
s g
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n .. o.- c. -..-.,.-/-.+ ...,
. c
...u p.
m ,,/ -
, ~
f.-
w - .
gg ; , .
m m.=;_-. - ;-, . 2 o =- ---
- .sEE7= --- '/ - .-2 7] =
P.
- E" --
- - ' . :' . -* ,2--'
o .d--
f _ _a g -.
f +----
w ,
102 M ; _
- -.- -- = . , ,
=:
,- m.
4
~~_,
u% A w>-. +
_- m. ..
gt y
.. = =mm m.--
mm-, _
+ ,w_-m ._m ,
=-- + -.
c - s, a b m u :-m.~
mh_, w:ww-.-- s.u y- - . .s- s .
m ,.
r.. w_ wm m._ 1 u ~ > wwe
-~_
y _'?:E ~_--Z !--.-_
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=> / /
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., nn _
5 ~ ' .. -
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3-
.. . , . 1 w~ . ~ . . +
,_ --'[ 4 } -'.. f .a. 454 ' ~. Pf [-f:-dij i a =.: d l==_ I[ M- '.[-f w !.', - * * *'1 - ) H - M W- L .rw- ] E 7 J-
.y 3,n- : - y . -
7 '
, :-- > v- -nes -, u av- .r - ~ > e
? ,w -m , tw ,_n_, v v -
, --/~ waw-~ /= -m m .:--1 -m~ --x- ,.
- %[j[j ._f-/ x -J=3_.. 1 i*Lj .-- -- / Mj5 -f
_ El-fi M M - ~~ -tf-
- m /; .. ; g ;.g - ,,. .Q ----n-----.---..- --r-----
0 ,w,--_.,
10
- e
. _ _ , > mm . . , . - ,
, n u + -. mn, .n-~mn .. - .- __a,
, p- 4.4f LP--- .i d+y.d . _ . .; _ .sf -4:d e --.*=~g I' - . ' ' '__ ' ::_-da tid -
. % -r--L-i.4.w:
- i s-M.--=+ , . t.-, . h r4 i a u, , ,y 1 -.- ; '_Ha 34
.,.2;--- -m.. !i .; - . . . __
w m
. ~ c .,w,-r x w
~ .
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=
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1-
==
-=
p
=
g.
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a~.+.-
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m-
..3 . ._
10-1 . =-
g CONCENTRATION IN MAIN STEAM LINES g uCr/cc a 1005 PSIA
- v~
*TO CONVERT TO ucr/LB NULTIPLY BY 1.20E4 Page 23 of 25 Rev. 2
EP IV-111 Attachment 7 O ATTACHMENT 7 UNIT ANALYSIS OF OFF-SITE DOSE CALCULATIONS A.1.3 Unit 1 Low Range Noble Gas !
(cpm . uCi/cc )(ft3 2.832E4cc . 1 min)( 1 )(mrem /hr) 2'.lE6 cpm min ft3 60 see m2 uCi/m3 = SE-4 (mph . 0.45 m/sec) mph A.l.4 Unit 1 Hioh Range Noble Gas (R-43) l (mr/hr) ( f t3 2.832E4cc . 1 min) ( 1 )(mrem /hr) min ft- 3 60 see m2 uCi/m3 = 1.05E3 (mph . 0.45 m/sec)(mr/hr) mph uCi/cc A.I.6 Unit 1 Iodine l (cpm , uCi/cc )(ft3 2.832E4cc . 1 min)( 1 )(mrem /hr) min 3.0E9 cpm / min min ft3 60 sec m2 uCi/m3 = 3.5E-7 (mph . 0.45 m/sec) mph
() A.2.2 Unit 2 Low Range Noble Gas (cpm . uCi/cc ) (ft3 . 2.832E4cc . 1 min)( 1 )(mrem /hr) l 3.75E7 cpm min ft3 60 sec m2 uCi/m3 = 2.8E-5 (mph . 0.45 m/sec) mph A.2.3 Unit 2 Hich'Pange Noble Gas (R-43) g (mr/hr) ( f t3 . 2.832E4cc . 1 min)( 1 )(mrem /hr) min ft3 60 sec m 2 uCi/m3 = 1.05E3 (mph . 0.45 m/sec)(mr/hr) mph uCi/cc A.2.5 Unit 2 Iodine g (cpm . uCi/cc )(ft3 2.832E4cc . 1 min)( 1 )(mrem /hr) min 3.13E9 cpm / min min ft3 60 sec m2 uCi/m3 = 3.35E-7 (mph . 0.45 m/sec) mph B.7 Release Rate From Unmonitored B.8 Whole Body Dose Pates S team From Release Rate
/) 1.20E4 cc/lb = 3. 3 (uCi ( 1 )(mrem /hr) k/ see uCi/m3 = 2.22 3.6E3 sec/hr m2 (mph . 0.45 m/sec) mph 24 of 25 Fev. 2 t
Attachment 8 DOSE CALCULATION $HEET EP IV-lli Monitoring Reading
$NF.S - UNIT PAGE CALC. DATE CALC. TIME RELEASE RATE ATM00PHERIC Ol5PER$10N COSE CONV. FAcr0R DOSE 70 awl AT FHOM fes$
AT LOCATION OF INTEREST OCF =>
M I/sec== 3 THE LCCAfl0M
---sec/m -== wom/he*= OF INTEREST (See Att.1) uct/e> (See Att. 2)
- - .=
0 . - - Senslt Release Stabit(ty? =
Release a *
- loolne = Thyroid Dose Rate et M = 0 * (VQ) * (DCF)
FDi$ & Floe Ground or Rats - - . Unit Rate Elevated ? e
( ) ( ) ( ) e Constant 8 MEA uCl/sec sec/e> DCF Dose Rate (xu/0)(2.22) = X/O (a) (d) 015 CHARGES FROI PLANT VENT wind speed sph taree/hr)
( ) ( ) ( ) =
0 LPZ uCl/sec sec/e> OCF :me Rate ICDINE: If R418 is of fscale use Att. 4 EP, IV-Ill e NEA ( )(2.22) = (d) (a) (e) e tg=
( )
(a) ( ) (
cpe/J const
) ( )
- vent flos
- uCl/sec 8 EPZ uC1/sec RetS or sec/eJ OCF Qose Rate (h) cfm e LPZ ( )(2.22) e pla (el (a) (f) 4t"2 see note (
) '
( ) ( ) ( )
- l NQlLE GA$3 f f 441C ls of fsCale use R43 channel use Att. 3. EP IV-Ill for I ters e EPZ ( )(2.22) =
8
~ uCl/seC seC/e> OCF Dose Rate (f ) (a) (3) 4t=3 (Remember to divide br I tere) ( )
If R43 Is offscale use Att. 4, EP IV-ill .
Noble Gas - Whole Body Dose Rate => N e Q (K/Q) (OCF) !
O meters ( )(2.22) = (g) '
( ) ( ) ( ) (b) ( ) ( ) ( ) ( )=
cpe const vent flee a uCl/sec AltC or (j) 8 MEA uCl/sec sec/e* OCF Dose Rate cfe El2A see note (b or c) (d) (mree/hr) as/0 (E-6/m 2, g 3 g 3 g ye Cround 8 LPZ uCl/sec sec/e> OCF
( )e( ) ( ) (4.T2E23 = (b) Dose Rate er/v const (b) (e) e tg e vont tiou uCI/sec ~80/
M3 (1) cfm 8300-
~c-l.3 2-0.5 ( ) ( ) ( )=
30 f t. u stab neut stab 8 EPZ uCl/sec sec/e> DCr 01;715 FRCH ATMOSPHERIC RELIEF VALVES Dose Rate tb or c) (f) et"
{ } MEA 9.95 41.5 227 2 Li v Ya TisEt
( ) ( ) ( )e using AMach. 3 LPZ 0.42 2. 5 33.3 uCl/sec of EP IV-Ill 4_ sec/ed OCF Dose Rate L!st are=/hr for this time (b or c) (g ) tta3 EPZ 0.15 0.95 13.2 uCl/cc a
( ) ==ee see e
( )
er/hr e whole Body Dose = Contef ament Leekage
* *> uCl/cc Survey Eu/0 (E-6/e 2) e MEA (
- 1=
Elevates (Sese VQ VQe*EA)
Inst. AtN in 24 hrs.
(d)
*C/ ~c-1.3 2 LPZ (
- 1=
( ) (3.31 ( ) (c) 8300- *-0. 5 vCl/cc (Base VQ VQ4LPZ) AS4 in 24 hrs.
Ib/hr e uCi/sec 30 f t. unstaD neut stab (e) 8 UZ ( )=
USING CONTAlt#8ENT OslTCRS TO ESTIMATE OFF5ITE 00SE MEA 12.4 42.2
- FR(M LEAKAGE. USE EP IV-Ill Attachment #3.
(Base VQ
- x/QtEPZ) RS4 in 24 hrs.
(f)
LPZ 0.57 4.06 14.3 0 ( )=
(d) ~
R/hr .> Base V9 (Base VQ
- VQ4 ) RD4 in 24 hrs.
EPZ 0.179 1.49 13.0 (gE C21 or K44A. 8 to yloid IR in 24 hrs.
g For Unit I (j) = 2.25E-4 thlt 2 (j ) = 1.42E-5 For Unit 1 (h) = 1.57E-73 thlt 2 (h) e f.5tE-7 e
itoo: Does the release rate seem reasonablet if Stops if the wind speed (mph) and stability Stop s if the whole body dose rate exceess 0.5 res/hr criemistry con take e sanote of t%e vent, has not changed you may use the same alert ttwa RO8 If the thyroid dose rate e==
cmoere their reported uCl/cc value with *be values in subsequent calculations.
f f rst two terms above. coeds 7.5 ree/hr alert the Res. The doses cal-culated are future doses. List the arrival
- 1.35E-12/m2 Olscherges which on the average exceed 3600 time for all calculations.
CI/hr ICf/s (noble gases) era cause for con-Arrivat time thrs)* tg a distence to location f alles) cern. Olsenerges whics on the everage er-(wind speed la men) 7 uCl/sec (25 eCI/hr) of todine are cause concern. t2
- 2'1 Nultiply by 60 to get arrival time in af astes, white = Dose Integrators Cenery - Status Board Attendant Pf ah = State Commanications: Goldenrod = Dose Calculefor
'dCA:srd 25 of 25 Rev.2 M PS2 43/161/2
i EP IV-ll2 EMERGENCY PROCEDURE EP IV-ll2 ;
FMEPGENCY OPERATIONS FACILITY - RADIOLOGICAL ASSESSMENT '
l ACTIOM LEVEL This procedure shall be implemented when the Radiological Support Manager has determined that his/her staff is ready to assume the responsibilities for off-site surveys, determining dose rates, doses, dose projections, and making Protective Action Recommenda-tions.
RESPONSIBLE INDIVIDUALS Radiological Support Manager (RSM) and Radiological Assessment Staff.
ACTION STATEMENTS N/
- 1. Responsibilities of Radiological Assessment Staff
- a. Radiological Support Manager (PSM) - The RSM has the ultimate responsibility for making protective action recommendations to the ERM and keeping the ERM informed with regard to dose estimates and field measurements.
The RSM is not given specific duties within the RSM office other than decision-making so that he can freely assess the plant status, dose calculations, off-site field data, and projections. It is the responsibility of the RSM to assure that the overall requirements of radio-logical assessment are met. Delegation of responsibility and authority to meet the goals of the assessment team is an important element of the RSM function. The primary responsibility of the RSM is to ascertain whether or not protective action is indicated by the radiological status
( within the Emergency Planning Zone (EPZ). Additionally, 1 of 29 Rev.01
k EP IV-112 the RSM is charged with ensuring that " Station Status Checklist" information is transmitted to the states of Delaware and New Jersey.
- b. Assistant Radiological Support Manager (ARSM) - The ARSM has the responsibility to directly assist the RSM in the discharge of the prescribed RSM duties. The ARSM serves as both an alternate and " relief" RSM. In the event of a prolonged emergency, it may be necessary to rotate the RSM and ARSM through the RSM duty. The ARSM should assist the RSM and the radiological assessment staff in performing analyses for any special problems which may arise.
- c. Radiological Assessment Staff - The Radiological Assess-ment Staff peforms multiple functions within the RSM
() office which include dose calculations, dose integra-tions, dose projection, field data calculations, attending the status boards, off-site team deployment planning, and source-term calculations. For long term recovery considerations, the Radiological Assessment Staff may assist the RPE at the station.
- i. Dose Calculation Staff - The dose calculation function can be filled by a minimum of two staff members. One staf f member must dedicate all of his time to dose rate calculations based on RMS monitor readings or release rates. The second dose calculation team member can verify dose calcolation results and perform dose integrations and projections. Additionally, one staff member will complete the station status checklist form and ensure that it is forwarded for transmittal to the states.
l l /~%
~- ii. Status Board Attendant - One staff member will update the status boards and the dose /RMS event history boards. The status boards highlight the latest RMS, 2 of 29 Rev.0
EP IV-112 l
meteorological, and dose calculation data. The event history boards allow the Radiological staff and observers a quick glance at what has been happening and provides the ability to spot questionable anomalies. If necessary, the Status Board Attendant can complete the Station Status Checklist form, iii. Off-Site Team Coordinator - The staff member who is assigned the duty of Of f-site Team Coordinator gathers field data from the radio communicator and from the state communicators. These data are plotted on the Emergency Planning Zone (EPZ) Map located in the RSM area. Based on meteorological data, plant release data, plume extent estimates, and accumulated field data, the Off-site Team Coordinator shall determine the most prudent deployment of field teams to provide
() timely and relevant information to the RSM for protec-tive action considerations. The off-site Team Coordinator.shall provide deployment instructions to the radio communicator (dispatcher) and field team personnel.
l iv. Radio Communicator - The radio communicator assists in
! communicating deployment instructions to the Off-site field monitoring teams and responding to questions from these teams. To eliminate confusion in the RSM office, the radio communicator should generally limit his conversation to the off-site teams by radio and the Off-site Team Coordinator who will be located
, adjacent to the communicator. The radio communicator is responsible for maintaining a log of all offsite field team activities.
, v. Phone Communicators - The function of the phone commu-nicators is of vital importance to the overall ftnction of radiological assesssment. One communica-3 of 29 Rev. O
EP IV-ll2 O tor is ansiened to receive information from the TSC or Control Room. This communicator provides the team with the data necessary to perform the dose calculations and assessments in a timely manner. Only selected RMS data (necessary for dose calculations) and " Station Status Checklist" data need to be received by phone. The phone communicators who speak directly with the states of Delaware and New Jersey have the responsibility to make sure that any protective action recommendations to be transmitted to the states have been approved by the RSM and the Emergency Response Manager (ERM) . With regard to other transmitted data such as calculated dose rates and " Station Status Checklist" information, any questions should be directed to a radiological dose assessment team member (Status board attendant, team coordinator, dose calculator, etc.) and not the RSM.
O The primary responsibility of the phone communicator to the states is to clearly transmit data in a timely fashion and to accept questions from the states.
Answers to questions may be handled by the communicators if the correct answer is obvious to the communicator; otherwise, the questions should be referred to the ARSM or staff members.
vi. Runner - The primary function of the runner is to carry information from location to location both within the PSM area and throughout the EOF.
(~~
l \._) 4 of 29 Rev.0
EP IV-112
- 2. Station Status Checklist Once the EOF has been officially activated and the Emergency Coordinator function has been transferred to the Emergency Response Manager (ERM), the Radiological Support Manager shall be responsible for filling out and sending the
" Station Status Checklist" (See EPI-2, EPI-3, and EPI-4) to the states of Delaware and New Jersey. This information transmittal shall normally be done through the two phone communicators assigned to the state communications in the REM office. The types of information to be routinely compiled for the " Station Status Checklist" include 1) time and date of incident (shutdown, if applicabi=); 2) current accident clasification, 3) oasis for classification (i.e.,
EAL's),4) description of systems involved, 5) meteorological data, 6) Noble gas and iodine release rates, and 7) estimated duration of release. (See Attachment 1) . This
[
information should be compiled onto the " Station Status Checklist" by a dose assessment staff member as soon as sufficient data is available. Both the individual who received the checklist information from the plant and a Radiological Assessment Staff Member shall review the status information to identify any significant anomalies.
- 3. Dose Calculations In addition to the routinely updated " Station Status Check-list" (Attachment 1) a " Supplemental Station Status Checklist" should be transmitted to the states completed to a pratical level with available information (See Attachment 2). During the initial stage.s at the EOF during an emergency, it may be practtcal to transmit calculated dose b
o 5 of 29 Rev, o
EP IV-ll2 O rates to the states. Other information such as isotopic mixes, contamination levels, and estimated impact times may be transmitted as this information becomes available.
Using procedures EP IV-lll, EP IV-ll3, or SP IV-114, dose rates should be calculated as soon as updated Radiation Monitoring System (RMS) data becomes available. At least one person from the Radiological Assessment Staff should be dedicated strictly to performing dose calculations. This position may be rotated to allow team members rest periods.
- 4. Special Problems Special Problems will be performed by Radiological Assess-ment Staff member (s) and the Assistant RSM. It is antici-pated that special problems outside the routinely g anticipated dose calculations may require attention. In
this event, attention can be given to these problems without diverting the attention of the dose calculation staff members. If available, a meteorologist will assist the assessment staff in plume extent estimation.
- 5. Field Team Deployment Since off-site dose rate and air concentration data may represent the most accurate picture with regard to plume status, deployment of field teams is a vital role to be played by a Radiological Staff member. One member of the t
staff will be assigned to the Team Coordinator position. A description of the duties and responsibilities of this Radiological Assessment team member and others is provided later in this procedure.
I 6 of 29 Rev. O
EP IV-112 f}
\m ' 6 Status Boards and Data Sheets Status Boards and Sheets are updated and/or circulated to keep staff members, observers, and other EOF participants informed on a timely basis. Availability of both current calculated and measured dose assessment data provides for a well informed assessment staff and reduces unnecessary conversation and questioning within the EOF. (See Attachments).
- 7. Radiation Monitor System (RMS) Data The RMS system includes numerous process and area radiation monitors. For simplicity at the EOF, the RMS is divided into two (2) categories, namely " Selected" dose calculation RMS data and "Other" RMS data. The " Selected" RMS data includes the iodine and Noble gas vent monitors for Units 1 1
() and 2 (namely, R12A, R12B, R41B , R41C ) , the high range R-4 3 monitor, the containment monitors (R4 4 and R21) , the letdown R-31 monitor, R11A, and R41A. " Selected" RMS data will be routinely transmitted from the TSC by phone.
The "Other" process and area monitors are useful in assess-ment of plant status and providing a basis for judging the validity of key monitor readings. "Other" RMS data will be transmitted by other means such as telecopy or by phone if time permits.
- 8. Field Team Data l Measured whole body dose rates and iodine-131 activities will be radioed from PSE&G field teams back to the EOF as I soon as practical. Additionally, field data from state l
O o
7 of 29 Re v . O l
EP IV-112 O (Delaware and New Jersey) teams will be phoned in through the state communicators. These data will be processed through the dose calculation staff and the status board attendant.
- 9. Communications with Plant The RSM office will maintain communication with a liaison within the Technical Support Center (TSC). Additionally, a line to the Centrol Room may also be available. A line will also be available such that the RSM or staff members can speak with the Radiation Protection Engineer or a Chemistry Department representative. A spare phone can be employed to enlist labor force or equipment support from other utilities and mobilize other support capabilities.
- 10. Dosimetry and TLD Issuance N~J
- a. Post two TLD Control badges and two self-reading dosimeters at two separate locations (one of each at each locale) in the EOF.
- b. Issue one TLD and one self-reading dosimeter to each off-site field monitoring team member and any other personnel who may enter a significant radiation field.
- c. In the event that the EOF is in the middle of a plume which warrants evacuation of the EPZ sector, issuance of TLD's and self-reading dosimeters to all EOF personnel should be made.
- 11. Access Control Access to the EOF will be controlled by security force
() members. If there is a significant likelihood of contam-8 of 29 Rev. O
EP IV-112 (A
N_/
)
ination being introduced into the EOF (as determined by the RSM staff), contamination control shall be instituted. A Step-off-pad (SOP) with a stachion/ barricade set-up should be instituted. An RM-14/HP-210 frisker should be set up at the entrance to the EOF and used to screen all personnel entering the EOF. A Radiological Assessment Staff member will brief the security guard on ensuring that the frisker is properly used. Contaminated foot apparel (if any) shall be removed prior to entrance.
- 12. Posting The front entrance to the EOF shall,be the main throroughfare. Posting of a guard at side or rear entrances during off-site field team preparation shall be permitted.
Otherwise these other doors shall be locked and posted to l indicate that the front entrance is the only entrance. If areas of the EOF become contaminated for some reason, these
! areas should be cordoned off and posted as is reasonable considering circumstances at that time.
- 13. Evacuation Criteria Consideration of EOF evacuation should be made based on the folicwing criteria:
Whole Body Dose Rate Consider Evacuation (within Facility) 1 500-2500 mR/hr within 2 hours 2500-5000 mR/hr within 1 hour j greater than 5000 mR/hr immediately i
It should be noted that the EOF need not be evacuated at the same time as the surrounding populace (based on EP IV-108).
\J 9 of 29 Re v. O
EP IV-ll2
- 14. Access to RSM Area ,
l Only personnel on official business shall enter the RSM area. Status sheets can be posted to update other interested personnel. !
4 ATTACHMENTS Number 1 - Station Status Check List Number 2 - Supplemental Station Status Check List Number 3 - Dose Assessment Data Status Board Number 4 - Centerline Plume Dose Rate Status Board Number 5 - Centerline Plume Integrated Doses Status Board Number 6 - Dose Calculation Sheet Number 7 - PSE&G Field Survey Team Data - Iodine Dose Rate Calculation Number 8 - Post Accident RMS Assessment Data Number N. 9 - Semi-log Data Plotting Board Number 10 - Other Area / Process RMS Data Number 11 - PSE&G/NJ/ Delaware Field Monitoring Data Form Number 12 - Dose Assessment Data Sheet Number 13 - SNGS - Operational Status Board - Emergency O
10 of 29 Rev.0
EP IV-112 j O Prepared By: M[ !
O e e Reviewed By: _9//> P7 -
/ Department Head Date Reviewed By: [ M- e d f-/d-Fa Nuclear NInergency Planning Ngineer Date Reviewed By: / f b StationOualityAssubfeReview ' Date if r gyired s V )
SORC Meeting No.: oD / 2/
[ ate #
Approved By: /c h b/ d[ w 9/A J/M GeneralMana[er-SalemOperations Date Q Approved By: C /2_
U Manager - Nuclear Site Protection Date 11 of 29 Rev. 0
i EP IV-112 4
ATTACHMENT 1 STATION STATUS CHECK LIST Salem Generating Station Unit No.
Transmitted By: Name Position:
- 1. Date and Time of Incident: Date Time (24 hr clock)
- 2. Accident Classification: Unusual Event Alert (Circle One)
Site Area Emergency General Emergency
- 3. System Involved:
(A) ( ) Reactor; or (B) ( ) Radioactive Waste System: (Circle One) Gaseous Liquid; or (C) ( ) Fuel Handling: (Circle One) Fuel Handling Bldg. Containment
- 4. Cause of Incident:
Primary Initiating Condition used for declaration of event EPI-0 Part , and/or Significant Event No.
Detailed Description of the event b
U
- 5. Is Reactor Tripped: (Circle One) YES NO Date: Time:
- 6. Gaseous Release: (Circle One) YES NO (A) Release Terminated: (Circle One) YES NO (B) Anticipated or Known Duration of Release Hours (C) Type of Release: (Circle One) GROUND ELEVATED l
(D) Wind Speed: MPH Wind Direction: (Toward)
Divide by 2 to get M/Sec (From)
(Compass Points)
(E) Stability Class: ( ) Unstable ( ) Neutral ( ) Stable (F) Release Rate Iodine CI/Sec.
(G) Release Rate Noble Gas: CI/Sec.
(Figure 9) 12 of 29 Rev. 0
EP IV-ll2
- 7. Liquid Release: (Circle One) YES NO (A) Release Terminated: (Circle One) YES NO (B) Anticipated or Known Duration of Release Hours (C) Estimated Concentration PICO Curies / Liter (D) Release Rate Liters / Hour
- 8. Recommended Off-site Actions (As Soon As Data Is Available):
Use Attached Worksheet
- 9. Status Checklist Data Relayed To New Jersey State (Date)
(Time), To: (Name)
Status Checklist Data Relayed to Delaware State (Date)
(Time), To: (Name)
- 10. Proceed to Supplemental Station Status Checklist (Addendum 2) if Information and Time Allow Supplemental Checklist Attached: YES NO
- 11. Date Time Peceived By O
l O
13 of 29 Re v. 0
-m- -
ym ,w .,y- _ , - -
l s 9 v %
"S =
7.8
>0 Hd v
%v M OC NORTH NNW fr mi. NNE S
NW 8 NE 7
8 RECORDER WIND FROM COMPASS DIRECTION FROM 5 ENE 348 3/4*to 11 1/4' N 3 11 1/4*to 33 3/4' NNE m 33 3/4*to 58 1/4* NE y i 58 1/4' to 78 3/4' 78 3/4'to 101 1/4*
ENE E
ESE l l i l E y$
tn W 101 1/4'to 123 3/4* O SE -d 123 3/4'to 148 1/# N 148 1/4'to 188 3/4e SSE .s.
S WSW H 188 3/# to 191 1/#
191 1/4*to 213 3/4* SSW ESE 213 3/4*to 238 1/4* SW 238 1/4'to 258 3/48 WSW 258 3/4*to 281 1/4* W WNW SW SE 281 1/4*to 303 3/4' 303 3/4*to 328 1/4' NW 328 1/4' to 348 3/4' NNW SSN SSE SOUTH RECOMMENDED PROTECTIVE ACTIONS WORKSHEET Designate areas and/or sectors with recommended protective actions symbo3e as f ollows:
S - Take shelter F - Food, water and milk control E - Evacuate 0 - Other (speci f y)
Time Wind Direction Wind Speed (from) , ,
Completed by: Reviewed by:
Emer. Coord./bSS/EDO/ERM G G G
i ATTACHMENT 2 ,
ATTACHMENT 2 SUPPLEMENTAL STATION STATUS CHECxLIST NOTE The inteat of this attachment is to provide a uniform format for data transmission between state and company personnel knowledgeable in radiation dose assessment. Examples are: 1) New Jersey Bureau of Tadiation Protection, 2) Delaware's Accident Assessment Advisory Group, 3) the Radiation Emergency Manager at the EOF, and 4) the Radiation Protection Engineer at the TSC.
Peactor and Unit No.
)
Transmitted From TSC/ EOF By: Name Position: .
Time Of Reactor Shutdown:
Time Of Pelease To Containmen't:
Time of Pelease From Site AIPPORNE RELEASES: Actual Potential-NOTP: RFLFASE (ELEVATED OR GROUND LEVEL)
IODINES 1
FLFVATED RELEASF GROUND LzvEL RELEASE (Ci/sec) (Ci/sec)
SPECIFY IF DATA IS AVAILABLE I-131 I-132 I-133 I-134 I-135 l
I NORLE GASFS PLFVATTD RELEASE GROUND LEVEL RELEASE (CI/sec) , (Ci/sec)
SPECIFY NUCLIDES IF AVAILABLE Kr - as er - as m nr - 87 Kr - an Mr - 133 Kr - 133 m Mr - 135 nr - 135 m 15 of 29 Rev. 0
j ATTACHMENT 2 i
PAPTICULATE PFLFASE: Actual Potential PARTICULATES A D R M A5E GROUND LgvEL RELEASE
( Ci/sec) (Ci/sec)
I-131 Cs - 137 Sr - 89
.9r - 90 FSTIMATF OF SURFACE RADICACATIVE CONTAMINATION:
Location Activity Exposure Rate In-plant Onsite Offsite Radionuclide Composition dpe/100cm2 mR/Nr i
I
]
l t
l Additional Remarks:
e i
i f
16 of 29 Rev.O
ATTACHMENT 2 JXPOSURE/ DOSE RATE MEASUREMENTS AND ESTIMATES:
Dose (Rem)
Sector Zones Exposure Dose Rate Location (1 - 16) (0 - 10) ( R/h r) (rem /hr) WB Child Thyroid Site Boundary i
- Plune centerline Peak :
2 Miles 4 Miles t
in Piles other Locations:
(Describe)
I I
O J
- Measured Calculated i
17 of 29 Rev.O
....3 4 . _ _ ~
ATTACHMENT 2 ESTIt'ATED IMPACT TIMES:
)
AIRBORNE / PARTICULATE RELEASES Location (Distance mi) for description) Sector Zone (s) Time To Impact: Hr Min (circle) j l
\
WATERBORNE RELEASES Location (Distance Mi): Public Water Intake, Beach Private Time To Impact: He Min (circle) (circle)
O 1
18 of 29 Rev.O
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1 Attc. chm ^nt 6 EP IV- 112 005iCALCULAMON 3117 honitoring Reading 58G5 = tAelf PnM_ cal.C. DATE CALC. TiesE RELEASE Raft ATMOSPHERIC OISPER$104
- 005E CDNV. FACTGt DOSE 70 swl AT FROM fbel Af s*T,AT104 0F INTEREST OCP o TMt LCCATION
==4Ct /sec-= ---sec/m 3 - -eres/hr= 3' INTEREST (See Att.1) uCI/m3 (See Att. 2)
- - - =
g - . .
Sensit Release -
Stabilityt a Release e 8 bel
- 4
- Plow tedine thyroid Dose Rete o H e 0 e (x/0) * (OCF)
Ground or Rete -. limi t Rete e Elevated t Coastant
( ) ( ) ( )=
8 8eEA uC1/sec sec/m3 QCF Oose Rete (Mu/0)(2.22) = X/0 (a) (4)
DI5OWIGES fet0M PLANT VENT wind speed aqbh (aren/hr)
( ) ( ) ( ) e IG)lNE: If R418 le of f scale use Att. 4 EP, IV.Ill 4 LPZ uCl/ses sec/e' OC# Qose Rete e MEA ( )(2.229 e (d) (e) (e) 4 (g o I
( l (a) spe/o const vent flow e uC1/seo t n( ) ( ) e CCC or (hl efe 8 EPZ uCl/see sec/m' OCF Dose Rete
$ LPZ ( 1(2.22) * (e) (a)
RID see note
(
(f) et" 2 !
)
i adinLE Gass if R41C is offscele use R43 cnennel
( ) ( >( ) e use Att. 3, EP lW.lli for 1 tere e vCl/see sec/m3 OCF Dose Rete l
8 (PZ ( 1(2.22) e (f)
~~~
(e) (g)
(R- to divide Ipp I term) ( )
49e3 I If R43 la effscale use Att 4, EP IValll Mble Gee = vhole Body Dose Rete en M e Q (X/03 (DCF) l 8 meters ( 1(2.22) e (g)
( ) ( ) ( ) (b) ,
I
( ) ( ) (
com cons t vent flee e uCl/sec ) ( )*
RelC er (j) efe 0 taEA uCl/nec sec/e' QCF Dose Rate Cl2A ese note (b or cJ (4) (eren/hr )
h/0 (E 6/m 2, g 3 g 3 g 3 woumi e LPZ uCl/see sec/e'
( le( ) ( ) (4.72E23 m OCF Dose Rete (b) (b) 1 er/hr sonst vent flow (e) e tg=
uCl/sec *C/
R43 (1) cfm 8300= <-l. 3 3-0. 5 ( ) ( l ( le 30 ft. Estely neut stab 8 EPZ uC1/sec sec/m3 0C7 01 ~ 7 P1830 ATMOSPHERIC RELIEP VALVES Dose Rete
( (b or c) (f) 49*
NEA 9.9s 41.5 227 2 LikslY Tleets ( ) (
Uelag Attach. 3 ) ( l*
of EP Ivaill LPZ 0.42 2. 5 33.3 e_ vCl/ses (b er c) sec/=3 (g)
OCF Dose Rete List aree/%r fir tais flee EPZ C.13 0.93 073 13.2 uCl/ car a
( ) ( ) .
as/nr e n => uct/cc shele Body Dose = Contelnsent Leemego, Survey b/0 (E.6/m2 l 8 MEA ( e ie Elevated (Sese X/Q ins t. N/Q9eEA[ REM in 24 hrs.
(d)
*C/ <= f.3 9 LPZ ( e )e
( I (3.33 ( ) ~
(el 6300- 3-0.5 uCl/cc (Sese X/Q VQfLPZ) #EM in 24 he s.
It/hr = uCl/sec 30 f t. unsten nest stem to)
USING (2)pfTAlfdsENT MONITORS TO ESTIMATE OFFSITE DOSE 8 EPZ ( )e MEA 12.4 42.2 * ~
FR@s LEAAAGE. ust EP IV.itt Attacneont #5. (Bees A/Q e VQ4EPZ) REM in 24 nrs.
(fl LPZ 0.57 4.06 14.3 e ( )e (d)
(Bese K/9 e VQd R/hr ) RD4 in 24 hrs.
=> Base 3/Q EPZ 0.179 1.49 13.0 (g7 K21 or K44A. 9 to yleid IR in 24 hrs.
gs For Unit I (jl e 2.2SE-43 t.h t t 2 (j ) = t. 42E-5 For Unit 1 th) e 1.57E-73 1.htt 2 th) = f.51E-7 itops Does t%e release rete seem reasonable? If eenistry con take e semple of the vent, Stopt if the wind speed (eph) and stability Stoon if the enote body does rate emceeds 0.5 ren/hr has not eenged you esy use the some slert the RDs. If the Myreld done rate swa compere their reported uCl/cc value oltit t'ae velves In subsequent calculottone.
first two terme above. coeds 7.5 ree/hr eiert the R0t. The doses cel-
- 1.ssE t2/e2 culated are future doses. List the arrivel Qianers wheen on n. ev.ree. e c.ed 3600 time for all ceicuistione.
CI/hr ICl/s (neble gases) are cause for cosa
. Olsenerges enten on the everage es. Arriven flee thrsle tg a distence to lacetion telles)
T uCl/see (25 uCt/hr) of lodine oro cause (el-e speed in spal t2 e 2tg concern
- multiply by 60 to get arrival time in minutes.
white = Dose integrators Canary - Status Board Attendents Pf ah = State ra Efretions: Goldenrod = Dese Calculator
<A s srs 22 of 29 Rev. O u PS2 43/16 t/2
l i EP IV-112 I i Attachment 7 .
I
; PSE&G FIELD SURVEY TEAM DATA IODINE DOSE RATE CALCULATION a) Sector and distance b) Time of sample c) Field team name d) Instrument eff. (demical)"
, e) DPM above background f). Sample volume (ft 3 }
g) (e) + (f)x(1.6E-11)**x(1/eff)= uCi I-131/cc h) Child thyroid dose rate from graph mrem /hr
- Ef ficiency obtained from calibration sticker on instrument. '
The default value for efficiency is 0.025 (1/eff = 40) i
** 1.6E-11 = (4.50 E-7 uCi/dpm) x (3.53E-5 cubic feet /cc) 1 uCi/ N IODINE-131
- le-9 -8 -7 -5 10-6
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f Rev. O w-v-y--vyyww ,.-ww--p-w e W me -wqq--w gg
l l O O O POST ACCIDENT RMS ASSESSMENT DATA Date Salem Generating Station PLANT VENT FRO 4 RATE CFM Time WIND SPEED Unit No. EL- 300 E'- 150
- WIND DIRECTION (FROM) EL. 300 EL. IC RllA com ^ " *C I g3aa,_33.) T150'-31*
! R12A com R1?A-H com R12B cpm R12B-H cpm R43 _mr/hr R16 com
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I
<- Waste'Gos
- o >
i f - R46A R46B com com o R31A com R46C com -R31B com h
a R46D com -R31C Yes/No Alarm N cn FIGURE 4 REV 1
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25 of 29 Rev.0
~ ._- . . - -
ATTACHMENT 10 t OTHER AREA / PROCESS RMS DATA '
AREA CHANNELS (mR/hr) <
NAME TIME I
1 BIA CONTROL ROOM R3 RADIOCHEM LAB i
R4 CHARGING PUMP AREA R5 FUEL HANDLING BUILDING R6A SAMPLING ROOM B9 FUEL HANDLING BUILDING R20B COUNTING ROOM R23 CONTPOL ROOM (PSE&G)
R34 MECHANICAL PEN (EL. 100)
R40 CONDENSATE FILTER
!O PROCESS CHANNELS (CPM)
RlB CONTROL ROOM INTAKE DUCT l R19A NO. 1 S.G. BLONDOWN R19B NO. 2 S.G. BLOWDOWN Pl9C NO. 3 S.G. BLOWDOWN R19D NO. 4 S.G. BLOWDOWN
- o FIGURE 5 26 of 29 Re v. 0
- -._.._.--__..-___.-.._--.__--:1-_ . _ _ _ _ _ _ . _ . _ - . _ . - , _ _ - _ _ _ . . _ - _ - - _ . . . _ . _
Attachmont 11 PSE&G/MJ/ DELAWARE FIZI,D MONITORING DATA FORM Time secation Teams whole nody lodine Cone.** Sample Thyroid Dose nose mate Type *** Aate (ares /hr)
(m4/hr) not cya min ft /3 min pCi/cc not cya min ft / min pC1/cc not epa min ft /ain pCi/cc not cps sin ft /3 min I .~..._ ... .
pCi/cc not cps min it /3 min pCi/cc j
- List name for PSE&G teams, or state desiTnation for New Jersey (NJ) or Delaware (D) .
**meport met cya, ooanting time, and flow rate.
l *** Particulate (P), Silver Seolite (SI), or Charcoal (C) .
27 of 29 Rev.0
Attachmsnt 12 DOSE ASSESMENT DATA SHEET DATE UNIT TIME OF READING Plant Vent Flow Rate (CFM)
Wind Speed (MPH) or EL-300' EL-150' Wind Direction (FROM) or EL-300' EL-150' '
4 Temp ('C) or 300'-33' 150'-33' Release Level (circle one) Elevated / Ground R11 A cpm R12 A cpm R12 B cpm
- cpm I last reading time R43 mR/hr R41 A cpm R41 B cpm t cp 9 last reading time R41 C cpm R21 (Unit 2) R/hr l
R44 (Unit 1) R/hr R31 cp Steam Line Survey Instrument mR/hr Steam Release 1bs/hr (Flow Ratel
*obtain cys/ min from CRT display if available (note cpa/ min units) 28 of 29
< m R@v0 @
Attachmsnt 13
$NGS OPERATIONAL STATils BOARD - EP8ERGENCY i
j DATE/ TIME OF UPDATE: /
2400 HRS 1281T No.
I. PRIMARY C00! M T SYSTEM 1 III. CONTADRENT INTECRITY
- e. Th - LOOP 1 'F '
- s. CONT. PRESS M FSIC
- b. Th - IAOF 2 'F b. 00NT. TEN (ATC) *F- -
- c. Th - IAOF 3 'F c. CONT. DEM FOINT 'F --
- d. Ib - IA0F 4 'F d. CONT. M CONCIN.
2
- e. e.
TAVC ( -
. HON MAM
- a. M . M SS. mc Q .A ..
- g. FER. LEVEL (NOT) %
- h. SUSC00 LING MARCINS IV. SAFETT INJECTION SYSTEM AF .
PSIC a. CENTRIFICAL CERC. F139 FLoli CFM AT *F b. S.I. F13EF FLOli CFM
- 1. RCS FIAll c. M FIBF FIAU CPN FORCED MATURAL d. R.W.S.T. 12TEL FEET
- j. RCF's IN SERVICE (CIRCLE) e. 5.1. ACTUATION 1 2 3 A M M
- k. 2400 ERS RCS BORON FFM
- 1. NEUTROII FLUE CPS i
Y. EM
- a. LETDOWN FLOW CFM II. SECONDARY C00!M T SYSTEN b. CNARCING FIAW '
CFM l
- a. No. 1 S.C. LEVEL (WIDE) I
- b. No. 2 S.C. LEVEL (WIDE) I
- c. N0. 3 S.C. LEVEL (WIDE) % VI. SIGNIFICANT FtMT EVENTS
- d. No. 4 S.C. LEVEL (VIDE) I g TIME
~
- e. No. 1 S.C. PRESS. FSIC
- f. No. 2 S.C. PRESS. PSIC S. NO. 3 S.C. PRESS. PSIC
- h. No. 4 S.C. FRESS. PSIC
- 1. No. 1 S.C. FEED FLOW !
- j. NO. 2 S.C. FEED FIDW 7
- k. No. 3 S.C. FEED FIall Z
- 1. NO. 4 S.C. FEED FIAW I l
Figure 3 Rev. 0 29 of 29
EP IV-113 EMERGENCY PROCEDURE EP IV-113 COMPUTERIZED DOSE CALCULATIONS ACTION LEVEL This procedure may be used in lieu of the manual dose calculation procedures.
RESPONSIBLE INDIVIDUAL An individual familiar with the Nuclear Data 6620 system (normally the shift RPT).
1.CTION STATEMENTS
- 1. Contact the Control Room and obtain the necessary information for the respective unit. This information can be compiled onto O the Dose Assessment Data Sheet ( Attachment 3 of EP IV-ll2).
WIND SPEED (mph)
WIND DIRECTION (degrees, from)
DELTA T ('C)
ELEVATED OR GROUND RELEASE TIME FROM START OF INCIDENT (hrs)
NOBLE GAS MONITOR (cpm) - Unit 1 (lR-12A);
i Unit 2 (2R-41C)
HIGH RANGE GAS MONITOR (mr/hr) - R-43 INITIAL cpm FROM IODINE MONITOR - Unit 1 (lR-12B);
Unit 2 (2R-41B)
FINAL cpm FROM IODINE MONITOR - Unit 1 (lR-12B);
Unit 2 (2R-41B) l TIME BETWEEN READINGS - (minutes)
Unit 1 (lR-12B); Unit 2 (2R-41B)
O 1 of 11 Rev. 2
. EP IV-113 ACTION STATEMENTS
- 2. Ensure a valid uscr ed on the computer and that the Decwrl:e:- s .iinal settings are correct (these settir.js a.. listed on the acustic coupler used with P.te t.erminal).
Dial Type in: WHO (return)
- 3. If tne system indicates a user is signed on, proceed to Step 4. If the system response is "NO USER SIGNED ON" Type in: HEL 10 (return)
/
- 4. Type in: R BASIC (return)
- 5. Response: MIDAS BASIC VOL-01 READY Type in: OLD (return)
- 6. Response: OLD FILE NAME - -
l Type in: DOSCAL.ALL (return)
- 7. Response: READY l
Type in: RUN (return)
)
l a 2 of 11 Rev. 2 L.
EP IV-ll3 O ACTION STATEMENTS
- 8. Response:
ALL (TODAY'S DATE MIDAS BASIC V01-01)
THE FOLLOWING PROGRAMS ARE AVAILABLE TO YOU:
PROGRAM PURPOSE 1 EFFLUENT DOSE CALCULATIONS 2 DOSE COMMITMENTS BASED ON WHOLE BODY COUNTS 3 I-131 EQUIVALENCE CALC-USING GELI ANALYSIS 4 DOSE COMMITMENTS BASED ON AIR SAMPLE DATA 5 UNMONITORED RELEASES FROM:
O-POWER OPERATED RELIEF VALVES STEAM DRIVEN AUX FEED PUMP SAFETY RELIEFS 9 TO EXIT PROGRAM Type in: 1 (FOR EFFLUENT DOSE CALCULATIONS)
There will be a pause of about 20 seconds.
- 9. Proceed to answer the questions with a carriage return (CR) af ter each entry. The answers below are examples, use actual values.
Response: ENTER YOUR NAME (EXAMPLE: J.R. DOE)
Type in: J. R. DOE (CR) 3 of 11 Rev. -2
EP IV-113
( .
ACTION STATEMENTS Response: ENTER THE CURRENT TIME OF DAY (EXAMPLE: 2230)
Type in: 2230 (CR)
Response: ENTER THE SALEM UNIT NUMBER (1 or 2)
Type in: 1 (CR)
Response: ENTER THE WIND SPEED IN MPH Type in: 2 (CR)(IF UNKNOWN ENTER 5)
Response: ENTER THE WIND DIRECTION (IN DEGREES FROM)
Type in: 200 (CR)
Response: ENTER THE DELTA TEMP Type in: 1 (CR) (IF UNKNOWN ENTER 1)
Response: ENTER 300 IF YOU'RE USING THE 300 FT. METER OR 150 FOR THE 150 FT. METER Type in: 300 (CR)
Pesponse: IS THE RELEASE FROM PLANT VENT
(~5
\
l (ELEVATED) OR FROM THE GROUND? ENTER E FOR ELEVATED OR G FOR GROUND Type in: E (CR)
Response: ENTER THE PLANT VENT FLOW RATE IN CFM Type in: 65000 (CR)(IF INOPERABLE USE 125,000)
Response: ENTER THE TIME IN HOURS SINCE SHUTDOWN Type in: 2.5 (CR)
Pesponse: NOTE:
ENTER THE CPM ON 1R-12A, IF OFF-SCALE OR INOP ENTER 0 (ZERO)(1)
IF YOU WISH TO USE THE VALUES FOR THE FIVE ACCIDENT CLASSES, ENTER 0 (ZERO)
FOR THE REQUIRED METER READINGS:
Type in: 12000 (CR)
(1) 1R-12A for Unit 1, 2r41C will be requested for Unit 2.
l 4 of 11 Rev. 2
EP IV-ll3 O ACTION STATEMENTS NOTE: IF 0 (ZERO) ENTERED FOR 1R-12A or 2R-41C, A VALUE FOR R-43 (MR/HR) WILL BE REQUESTED. IF 0 (ZERO)
ALSO ENTERED FOR R-43, THE DESCRIPTION AND DEFAULT VALUES FOR THE 5 ACCIDENT CATEGORIES WILL BE PRINTED OUT AND YOU MUST ENTER THE EOUIVALENT GASEOUS CPM FOR THE APPROPRIATE TYPE OF ACCIDENT.
Response: (For Unit 1)
ACCIDENT TYPE EOUIVALENT CPM 1 2.42 E5 2 7.82 E2 3 1.25 E5 4 9.9 E4 5 1.42 E4 ENTER THE EQUIVALENT CPM / MIN FOR THE APPROPRIATE ACCIDENT CLASS:
Type in: (VALUE FOR APPROPRIATE ACCIDENT CLASS)(CR) i l
i i
l I
5 of 11 Re v. 2 l
c
EP IV-113 O ACTION STATEMENTS Fesponse: ENTER THE INITIAL CPM FROM 1R-12B.
IF INOP OR OFF-SCALE ENTER 0 (ZERO)(2), ;
Type in: 10 (CR)
Response: ENTER THE CURRENT CPM ON 1R-12B(2)
Type in: 100 (CR)
NOTE: IF 0 (ZERO) IS ENTERED FOR THE INITIAL 1R-12B (IODINE MONITOR) THE DEFAULT VALUES BASED ON THE 5 ACCIDENT CATEGORIES WILL BE PRINTED OUT AND YOU MUST ENTER THE EQUIVALENT CPM / MIN FOR THE APPROPRIATE TYPE OF ACCIDENT.
Response: (For Unit 1)
ACCIDENT TYPE EOUIVALENT CPM 1 9.35 E6 2 1.45 ES 3 NO RELEASE 4 1.22 E6 5 3.3 E6 ENTER THE EQUIVALENT CPM / MIN FOR THE APPROPRIATE ACCIDENT CLASS:
Type in: (VALUE FOR APPROPRIATE ACCIDENT CLASS)(CR)
Response: ENTER THE ELAPSED TIME (IN MINUTES) BETWEEN READINGS 1R-12B Type in: 10 (CR)
Response: ARE YOUR ENTRIES CORRECT? (Y/N)
Type in: Y (CR)
( (2) 1R-12B for Unit 1, 2R-4B will be requested for Unit 2 6 of 11 Rev. 2
EP IV-113 O MTS NILL BE A PAUSE OF ABOUT 20 SECONDS.
se: THE FOLLOWING CALCULATIONS ARE FOR ASSUMING AN ELEVATED RELEASE:
- 12000 R-43: 0 VENT FLOW: 65000
; : 1 INIT 1R-12B: 10 FINAL 1R-12B: 100 OR COLLECTION: 10 VENT WB DOSE THY DOSE MINS FOR PLUME MILES IN MREM /HR IN MREM /HR TO TRAVEL DIST 310752 8.06881E-06 2.86314E-08 9.32256 621504 7.94761E-06 2.85648E-08 18.6451 78931 7.88217E-06 2.85292E-08 23.6793 932256 7.82642E-06 2.84989E-08 27.9677
( 24301 1.30989E-03 4.83372E-06 37.2902 55376 .0145613 5.44685E-05 46.6128 86451 .0591803 2.24459E-04 55.9354 17526 .142428 5.47889E-04 65.2579 48602 .255604 9.97538E-04 74.5805 79677 .38123 1.50988E-03 83.903 10752 .503816 2.02561E-03 93.2256 41827 .61369 2.50552E-03 102.548 72902 .705899 2.92752E-03 111.871 039?r .778525 3.28086E-03 121.193 350!. .831791 3.56319E-03 130.516 66128 .869154 3.78608E-03 139.838 97203 .891379 3.94992E-03 149.161
.89232 3.96026E-03 150 28278 .901681 4.06613E-03 158.484 59354 .90248 4.14329E-03 167.806 90429 .894874 4.18440E-03 177.120 7 of II Rev. 2
-. _ ._=_. -
l l
l EP IV-113 ACTION STATEMENTS DISTANCE FROM VENT WB DOSE THY DOSE MINS FOR PLUME IN METERS IN MILES IN MREM /HR IN MREM /HR TO TRAVEL DIST l 10000 6.21504 .881642 4.20066E-03 186.451 '
10500 6.52579 .863111 4.19223E-03 195.774 11000 6.83654 .841267 4.16746E-03 205.096 11500 7.1473 .816326 4.12645E-03 214.419 12000 7.45805 .789563 4.07475E-03 223.741 12500 7.7688 .761641 4.01513E-03 233.064 13000 8.07955 .733171 3.95036E-03 242.387 13500 8.3903 .703734 3.87775E-03 251.709 14000 8.70106 .6744 3.80275E-03 261.032 14500 9.01181 .654672 3.72809E-03 270.354 15000 9.32256 .616639 3.64835E-03 279.677 15500 9.63331 .58826 3.56895E-03 288.999 16000(3) g,94407 .560967 3.49356E-03 298.322 O
THE MAXIMUM DOSE RATES ARE CALCULATED TO BE AT:
THYROID: 10000 METERS WHOLE BODY: 9000 METERS BASED ON YOUR INPUT THE PLUME IS CURRENTLY TRAVELING TOWARDS THE NORTH (OR 20 DEGREES) AT 2 MILES PER HOUR.
( (3) This is approximately the EPZ.
8 of 11 Rev. 2
1 EP IV-ll3 l
() ACTION STATEMENTS THE CURRENT CURIE PER SECOND RELEASE RATES ARE:
IODINES: 9.18450E-08 GASEOUS: .1755 DATE OF CALCULATION: (TODAY'S DATE) TIME OF CALCULATION:
2230 DATA ENTERED BY: J.R. DOE PLEASE WAIT 20 SECONDS . . . .
D9 YOU WANT A PRINTOUT OF THE Y PLANE PLUME PARAMETERS? Y/N Type in: Y (CR) l Response: PLUME PARAMETERS FOR 10% OF CENTERLINE DOSE DISTANCE FROM SITE DISTANCE FROM CENTERLINE PLUME WIDTH IN METERS IN MILES IN METERS IN MILES IN DEGREES 1000 .621504 253.999 .157861 28.4546 1270 .78931 306.055 .190214 27.0519 2000 1.24301 436.15 .271069 24.5617 3000 1.86451 598.393 .371904 22.5216 4000 2.48602 748.925 .46546 21.1726 5000 3.10752 891.31 .553953 20.1796 6000 3.72902 1027.52 .638608 19.4016 7000 4.35053 1158.8 .7202 18.7664 8000 4.97203 1286 .799256 18.2323 8045 5 1291.64 .802761 18.2102 9000 5.59354 1409.75 .876163 17.7735 10000 6.21504 1530.5 .951209 17.3725 O
9 of 11 Rev. 2
EP IV-113 O ACTION STATEMENTS DISTANCE FROM SITE DISTANCE FROM CENTERLINE PLUME WIDTH IN METERS IN MILES IN METERS IN MILES IN DEGREES 11000 6.83654 1648.61 1.02462 17.0174 12000 7.45805 1764.39 1.09657 16.6993 13000 8.07955 1878.05 1.16722 16.4118 14000 8.70106 1989.81 1.23668 16.15 15000 9.32256 2099.83 1.30505 15.9098 16000 9.94407 2208.24 1.37243 15.6883
- 11. The program will return to Step 8. You may run the program again.
- 12. To exit and terminate the program:
Type in: 9 (CR)
O Response: DO YOU WISH TO EXIT THIS PROGRAM? .
(Y/N)
Type in: Y (CR)
BYE (CR)
BYE 10 (CR)
Response: SIGNED OFF O 10 of 11 Rev. 22
I EP IV-113 l Signature Page O'N Prepared By: [w w/I, O l h [ M [ b (A+ W v v fr/ f 'f V r .
Reviewed By: M --
/ -
f//o[P 1
/ Depar'tment Head Date j Reviewed Ry: [j M . 9-/d-F2-Nuclea[ Emergency Planning Edaineer Date Reviewed By: p, yA Station Ouality As nce Review Date (if requi _ P I 2)
__ / N SORC Meeting No.: '
[ '/ M date[
Approved By: A[. h N h v 9/>c h General Manager - Salem Operations Date Approved By: 9 f f7 Manager - Nuclear Site Protection Date 1
O 11 of 11 Rev.2
EP IV-ll4 EMERGENCY PROCEDURE EP IV-114 COMPUTERIZED DOSE CALCULATIONS ON PROGRAMMABLE CALCULATOR (TI-59)
ACTION LEVEL This procedure may be used in lieu of the manual dose calculation
- procedures.
RESPONSIBLE INDIVIDUAL An individual familiar with the Texas Instruments TI-59 programmable calculator (normally a Shif t RPT or EOF assessment team member).
ACTION STATEMENTS O DOSE CALCULATIONS FOR PRE-SELECTED LOCATIONS PART A (MEA, LPZ, EPZ, OR 5.5 10, AND 13 Km LOCATIONS)
- 1. Contact the Control Room (or TSC) and obtain the necessary information for the respective unit. This information can be compiled onto the Dose Assessment Data sheet (Attachment 3, EP IV-ll2).
WIND SPEED (mph)
WIND DIRECTION (degrees, from)
DELTA TEMPERATURE (4T, 'C)
TIME FROM START OF INCIDENT (hrs)
NOBLE GAS MONITOR (cpm) - Unit 1 (lR-12A);
4 Unit 2 (2R-41C)
HIGH RANGE MONITOR (mR/hr) - R-43 INITIAL READING FROM IODINE MONITOR (cpm) -
Unit 1 (1R-12B); Unit 2 (2R-41B)
O FINAL (OR MOST RECENT) READING FROM IODINE MONITOR (cpol - Unit 1 (lR-12B); Unit 2 (2R-41B)
TIME BETWEEN READINGS ON IDOINE MONITOR (minutes) - Unit 1 (lR-12B); Unit 2 (2R-41B) 1 of 22 Rev. 0
EP IV-ll4 O PART A (continued)
- 2. Prepare programmable calculator TI-59 for use:
a) Lock TI-59 calculator securely into printer cradle (PC-100).
b) Turn printer power on, then turn calculator power on.
c) Select the Salem 1 or 2 (appropriate) MET-RMS-DOSE calculation cards (two cards - three sides) for the distances of interest (i.e., MEA, LPZ, EPZ or 5.5, 10 13' Km).
d) Prior to card reading, press 3 Op (2nd tier) 17. (The number 719.29 should appear on display.) Then press CLR. Press CLR before reading any card side.
e) Read all appropriate program card sides (cards are to be inserted into slot on right hand side of TI-59). This
; program is contained on three (3) sides of two (2) cards.
If the calculator display blinks following the attempt to
- read the cards, the card has not been read. Press CLR and ~
reinsert this card side until number designated of card side is shown on display without flashing.
f) After reading all appropriate program cards, initialize calculator by pressing 2nd A.
- 3. RUN DATA ON PROGRAM (see example - Attachment 1).
i a) Enter wind direction from which the wind blows (degrees AZIMUTH), then press A.
NOTE The direction the wind blows towards will also automatically printout.
O 2 of 22 l Rev.0.
l
EP IV-ll4 O PART A (continued) b) Enter the wind speed (mph) then press R/S.
c) Enter station delta temperature (AT), then press R/S.
d) Select type of release, Press O for ground level release, or 1 for elevated release (plant vent), then press R/S.
NOTE The calculator will now pause for 5 to 10 seconds and then print three numbers with exponents representing the X/O values for the three program distances (i.e., MEA, LPZ, and EPZ).
1 e) Following this calculator printout, enter the plant vent O flow rate in cubic feet per minute (cfm), then press B.
(Default value for flow rate is 125,000 cfm).
f) Select type of data to be introduced: for low range vent monitors or FSAR Design Basis Accident (DBA), enter 0; for high range monitors, press 1, then press R/S.
g) If 0 (zero) is selected above enter the appropriate Noble Gas Monitor reading (cpm), or DBA cpm equivalent then press F/S; if 1 (one) is selected above, enter mR/hr reading from I
l R-43 as actually read on the instrument, then press R/S.
After the actual R-43 value is introduced then enter the R043 concentration conversion factor from Attchment 4 and press R/S. This entry is only required if the high range choice is made. DBA (design basis accident) classes and cpm i equivalents are given in Attachment 5.
(d 3 of 22 I
Rev. O
EP IV-ll4 O PART A (continued) h) Enter the initial iodine monitor reading (cpm), or 0 for DBA cpm equivalent, then press R/S.
- 1) Enter the latest iodine monitor reading (cpm), then press R/S. If off-scale, use DBA default values - these defaults can be used with R-43 readings (see Attachment 5 for DBA default values).
j) Enter the amount of time lapse (delta time) between the iodine monitor reading time (t0) and latest reading time (ti) in minutes, then press R/S.
NOTE For DBA default or zero readings use one (1) minute.
k) Af ter calculator finishes printing (eight lines of numbers O' in exponential form taking 10 to 20 seconds), enter the appropriate Noble Gas Dose Rate Conversiion Factor (DRCF).
See Attachment 2 for decay time versus factor graphic.
After entering this factor, press C.
NOTE The eight lines of output represent Noble Gas and iodine source terms and calculated concentrations (see Attachment 1).
- 1) Enter the appropriate Iodine Dose Rate Conversion Factor (see Attachment 3), then press R/S.
l 4 of 22 Rev. 0
_ - _ . - _ - _ . . = _ __ _ __ _ -
EP IV-114 O PART A (continued) m) This completes the dose calculation program, (e.g., the dose rates for whole body and thyroid are printed out for the MEA, LPZ, and EPZ). To reinitialize calculator, press CLR, then press 2nd A. To sign off, press CLR and then turn off calculator first and then the printer.
NOTE
- 1. Because program enters only one decay time for the three distances from plant release, only one of the distances is decay corrected for the proper transient time using Attachments 2 and 3 for the Noble Gas and iodine dose conversion factors. For more accurate transient time input on other distances, rerun program with transient time for desired distance.
l
- 2. Be sure to partition (3 OP 17) before reading cards.
! 3. Be sure that all card sides are read properly.
- 4. Be sure to initialize calculator (2nd A) before dat'a entry.
- 5. ALL KEYBOARD ENTRIES REOUIRE CLOSINF STATEMENT: THIS STATEMENT IS R/S for all entries except wind direction (press A), plant vent flow rate (follow with B), and the Noble Gas Dose Rate Conversion Factor (then press C).
5 of 22 Rev. 0 4
I
EP IV-ll4
() Attachment 1 ATTACHMENT 1 EXAMPLE PROBLEM FOR TI-59 CALCULATIONS EXAMPLE f
GIVEN: a) Meteorological data is as follows:
wind direction (from) = 230* at 300 ' Elevation wind speed = 1 mph T = 0.5'C b) Unit 1 Containment monitor 1R12B reads 1500 cpm now.
Five minute ago, this monitor was reading 50 cpm.
c) Plant vent flow rate = 68,000 cfm d) Monitor 1R-12A reads 500,000 cpm d) Reactor has been shut down for two hours SOLVE: a) What are the whole body and thyroid dose rates for the MEA, LPZ, EPZ distances of 5.5, 10 and 13 kilometers.
ANSWERS: (mrem /hr)
DISTANCE WHOLE BODY THYROID MEA km 288 0.805 LPZ 10km 27.8 0.077 EPZ 13km 10.2 0.028 ,
O 6 of 22 Rev.0
EP IV-ll4 Attachmrint 1 PRINTOUT FOR EXAMPLE PROBLEM (TI-59)
INPUT TI-59 PRINTOUT OUTPUT _ UNI _TS Exclanation Press Units 3a. wind direction (from) A 230. (*)
- 50. Wind direction (towards) (*)
3b. wind speed RJ 1. (mph) 3c. A temperature RLS, -0.5 (*C) 3d. elevated release ~
R/S 1.
9.4398712-05 MEA X/Q (sec/m )
, 9.0819613-06 LPZ X/O (sec/m )
4 3.3330351-06 EPZ X/O (sec/m ) +
3e. station vent flow B 68000. (cfa) 32096000. Vent flow (in cc/se 3f. Iow range monitor choice _R_/S 0.
- 39. noble gas monitor M 5.05 (cpm) 3h. initial iodine monitor readirN RLS 50. (cpm)
- 31. current iodir.t.
- monitor reading g 1500. (cpa) i f
- 33. delta time between l
\ iodine readings M 5. (minutes) 7.638848 06 Noble Gas Source (mci /sec) ;
3.0995107 00 Iodine Source Term (pCi/sec) 7.2109741 02 NG-MEA conc. (pCi/m )
6.9375722 01 NG-LPZ conc. (pCi/m )
2.5460548 01 NG-EPZ conc. (mci /m )
2.9258982-04 I-MEA conc. (pCi/m )
2.8149637-05 I-LPZ conc. (mci /m )
1.0330778-05 I-EPZ conc. (NCi/m )
3k. dose rate conv.
factor-Noble Gas C 0.4 (-)
(NG)
- 31. dose rate cony. R/S 2750. (-)
factor-iodine 288.4389635 WB Dose Rate (mrem /hr) 27.7502889 WB Dose Rate (arem/hr!
10.18421933 WB Dose Rate (arem/hr)
.8046220004 Thyroid 5.5 Dose Rate (mrem /hr)
.0774115005 Thyroid 10 Dose Rate (mrem /hr)
.0284096394 Thyroid 13 Dose Rate (mrem /hr)
- 7 of 22 j Rev.0
O Attach h 2 Att. 2 NOBLE GAS DRCF FOLLOWING SHUTUDW O.6l-BASED ON EPA-520/1-75-001; 3200 NW THERM 4L AT E4LilL18AIUM NOTE: INGROWTH OF GASEOUS DAUGHTERS INCLUDED IN 00SE RAT 6S 0.5 -
A. Tine f ran shutdown to time of release in hours = hr D. Thae for transport = (Desired Distance)/(Wind Speed)
( mi)/( mph) =
g
/ 0.4 C. Total decay time = (Step A) ~+ (Step B)
H R ( )+( ) "
hr
/
y D. Correlate the total decay time (hours following shutdown) m C 0.3 -
t.o the curves to determine the dose conversion factors o 1 for Noble Gas.
.s j U N 5 .
5 -
0.2 -
0.1 -
1
~
DE a
0.0 = I I I I I l I
- l. l I l- I 0 10 20 30 ~ 40 g
50 60 p fg TOTAL DECAY TIME - IIOURS ,
4 i .
O O Attachnent 3 att. 3q L.r'svAn]O .
_ IODIHE DRCF FOLLOUING REACTOR SHUTDOUH - - '
l BASED OH EPA-520/1-75-001; 3200 MU THERMAL AT EQUILIBRIUM ,' '
i 2900 DRCF'S FROM REG GUIDE 1.1093 NORMALlzED TO I-131 CONC OF 1 UCI/M**3 .
l I-TOT DRCF= 2928.1-( 50. 0298 T )+ ( 1. 6723t T**2 )-( 0. 04003527**3 )
l 2800 - +(5.3469E-4*T**4)-(2.8757E-6*T**5)
I
! M -
l2700 I-TOT DRCFs HORMALIZED TO 1 UC.t/M**3 I-131
)2600 -
H A. Time fran shutdown to time R -
of rs;1 ease in-hours -
/ 2500 -
hr
, , U B. Tiine for transport = (Desired C
- o m I 2400 Distance)/(Wind Speed) i j -
( mi)/( mph) =
u hr I " M
- c. Total decay time = (step A) g 2300 -
+ Step B) l 3 I I*I I "
hr j 2200 - . Correlate the total decay time (hours following shutdown) to the curves to determine the dose conversion . factors 2100 -
for Noble Gas.
2000 -
> to 1900 l I I I I I I I I I I I I N O 10 20 30 40 50 60 *E TOTAL DECAY TIME - IIOURS
O O Attacivnent 4 Art, SS -
R-43 CONCENTRATION CONVERSION FACTOR FOLLOWING SilUTDOWN BASED OH EPA-520/1-75-001; 3200 MU THERMAL AT EOUILIBRIUM NOTE:
50 --
INGROUTH FROM PAREHY ISOTOPES NOT INCLUDED i
4 45 f 40 -
i M
) 35 -
14 I
R -
/ 30 -
r U i o C i
o n
I 25 -
/
w C .
1 0 20 -
15 -
10 -
! 5 - '
O I I I I I I I I O I I I I 10 20 30 40 50 60 *y HOURS FOLLOUING SHUTDOWN 8 *h
- to
! o .,
EP IV-ll4 Attachment 5
(
ATTACHMENT 5 DEFAULT VALUES FOR LOW /HIGH PLANT VENT MONITORS Read the below accident description and determine which case is applicable. From the tsble select the appropriate release rates (cpm).
CASE I LOCA A LOCA assuming severe core damage - fuel melting (Regulatory Guide '
l.4 assumptions) 100% of Noble Gases and 25% of the iodines contained in the core are assumed released to the containment. The containment initially leaks at the maximum design leak rate.
CASE II LOCA Primary coolant leaks at a rate fast enough to increase the temperature of the core to the point where there is damage to the fuel rods. For this case, it is assumed that all the gap activity (the cases contained between the fuel and fuel rod) is released to the containment. The containent is assumed to initially leak at the maximum design leak rate. In this accident, it is up to the Senior Shift Supervisor or Emergency Duty Officer (EDO) to assume that there has been no fuel melting. If there is any question, a Case I LOCA O should be assumed.
b CASE III DECAY TANK RUPTURE This procedure is used only if actual radiological monitoring equip-ment is unavailable for release evaluation (monitors out of service, read off scale, etc.).
CASE IV FUEL HANDLING ACCIDENT Any activity occurring as a result of a fuel handling accident is normally drawn into the Fuel Handling Building Ventilation System and vented to the plant vent for release. The process monitors are used to monitor these releases; however, should these monitors be out of service or off scale, this technique is used to evaluate off-site dose.
CASE V STEAM GENERATOR TUBE RUPTURE The activity released during a minor tube rupture can be determined using vent monitors and normal procedures. This procedure addresses the steam generator tube rupture as analyzed in the FSAR. This accident is set apart from others because of the inability to consult radiation monitors to determine the activity release rate. Therefore, this is the primary procedure to determine the activity release rate resulting from a system generator tube rupture.
U,_
l 11 of 22 Rev. 0
4 l
EP 77-114 7-s\
i Attachment 5
%)
EOUIVALENT NOBLE GAS EQUIVALENT IODINE ACCIDENT CLASS RELEASE RATE CPM ACTIVITY INCREASE RATE (CPM / MIN)
Unit 1 Unit 2 Unit 1 Unit 2 I(l) 2.42 E5 4.34 E6 9.35 E6 9.73 E6 II(l) 7.82 E2 1.40 E4 l.45 E5 1.51 E5 IIli l) 1.25 ES 2.24 E6 NO RELEASE NO RELEASE IV(1) 9.9 E4 1.78 E6 1.22 E6 1.27 E6 V(2) 1.42 E4 2.54 ES 3.3 E6 3.50 E6
'/ (1) Use actual or estiraated plant vent flow (cfm) as provided in the procedure.
(2) Case V is assumed not to be released through the plant vent so use a flow of 125,000 cfm for this calculation.
i l
l l
l l
l
('~)h
\_
i 12 of 22 l Pev. 0 5
4 EP IV-ll4 PART B DOSE CALCULATIONS BASED ON RELEASE RATE OR FIEL'D MEASUREMENT i (OPTIONAL) FOR ANY LOCATION
- 1. Contact the Control Room or TSC or EOF field team coordinator.
Obtain the necessary information form the respective unit.
- a. Noble Gas Release Rate in Curies per second (can be calculated from RMS data using Part A of this procedure).
- b. Wind speed in miles per hour (mph),
directior. and stability class.
- 2. Based on the time since shutdown and the plant conditions affecting the release, determine the Noble Gas and iodine dose rate conversion factors (DRCF) from Attachments 6 and 7, and I estimate the duration of exposure.
- 3. Prepare programmable calculator TI-59 for use:
- a. Lock TI-59 Calculator into printer cradle (PC-100).
- b. Turn printer on, then calculator power on.
- c. Select the Release Rate Dose Calculation Cards'(two cards -
l three sides).
- d. Prior to card reading, partition the TI-59 by pressing 3 Op (2nd tier) 17. (The number 719.29 should appear on display.) Then press CLR. Press CLR before reading any card side,
- e. Read all three sides from the two program cards. If the calculator display blinks following the attempt to read the card side, the card side has not been read. Press CLR and reinsert this card side until number designation of card side is shown on display without flashing.
l O 13 of 22 Rev. O I
(
- _ - - _ - _ _ . - - . - . - . - - . . _ . - - - - - . - _ _ _ . _ - - _ . - . _ ~ _ . . _ . _ _ . . - . _ _ _ _ . _ . . _ . . - _ ~ _ . _ . _ . - _ . _ . _ _ , - - , . -
.: EP IV-ll4 O PART B (continued)
- f. After reading all three (3) card sides, initialize calculator by pressing 2nd A.
- 4. Data Entry I
- a. Enter distance in miles for which dose rates and dose commitments are desired and press A (e.g. , if dose i calculations for a location 10 miles from the station are desired, press 10 A).
- b. Enter appropriate Xu/O (Attachment 11), tuen press B (program code inserts exponent of 10-6; if Xu/Q = 6.1 x 10-6, then simply enter 6.1) .
- c. Enter Noble Gas release rate (Qn) in Curies /second (Ci/sec),
! then press C.
4
- d. Enter Iodine release rate (Qi) in Ci/sec then press D.
- e. Enter wind speed in miles per hour (mph), then press E.
- f. If available, enter field measured iodine concentration (XI) in Ci/m3 (same as (uci/cc), then press A' (press 2nd A).
- g. If available, enter field measured whole body dose rate in R/hr, then press B' (press 2nd B). If not available enter zero, then press 2nd A.
- h. Enter estimated duration of release in hours and minutes with decimal point, then press C:' (press 2nd C).
- i. Divide value of DRCF for Iodine from Attachment 7 by 1000 to correct to appropriate units (rem-m3/Ci/hr, and enter this value, then press D' (press 2nd D).
- j. Multiply value of DRCF for Noble Gas from Attachment 6 by 10 to correct to appropriate units (rem-m3/Ci/h r) , and enter this value, then press E' (2nd E).
1 14 of 22 Rev. 0
,_.._.-_._,~_____-_,-_--.__..-_....._...__.___.._.2_.._.._..._..
_- ...- _ = . __ ._ -- _ _ - . - . .- -
EP IV-ll4 PART B (continued)
- 5. Running Program
- a. Press R/S and program will run.
, b. Example printout is shown on Attachment 8. Initial data entries should first be logged on data log sheet (Attachment 9). Results should be logged onto calculation sheet (Attachment 10).
I O
i i
i I
i i O 15 of 22 Rev. 0
EP IV - 11'l l
O Attachme#f Att. 6 .
I a 0.6 -
u BASED ON EPA-520/1-75-001; 3200 NW THERPML AT EQUIL18A10N L
T HOTE: INGROWTH OF GASEOUS DAUGHTERS INCLUDED IN DOSE RATES I .
I i
,n i
L 0,5 -
Y A. Time f ran shutdown to time of release in hours = hr
[ B. Time for transport = (Desired Distance) /(Wind Speed) l I M sR ( mil /( mph) =
h'
/ g,4 _
C. Total decay time = (Step A) + (Step B)
N y ug ( )+( ) =
M / hr B
l g E U D. Correlate the total decay time (hours following shutdown) g R 0.3 - to the curves to detennine the dose conversion factors o y for Noble Gas.
B
' U Y N .
1
- s.
o3 0.2 -
i l
y .
o R
i P A O.1 -
I R 5 (B)
I I . s 0.0 I I l -l I
! O to 20 30
~
l.- 1 I I I mi 4 40 50 60 g TOTAL DECAY TIME - IlOURS
tt' av-115 -
Att.<7 Attachment 7 i
' D 3000 - IODINE DRCF FOLLOUINO REACTOR SHUTDOUH I .
I BASED OH EPA-520/1-75-001 3 3200 MU THERMAL AT EQUILIBRIUM
{g 2900 -
DRCF'S FROM REO OUIDE 1.109s HORMALIZED TO I-131 COHC OF 1 UCI/M**3
, E I-TOT DRCF=2928.1-(50.0298T)+(1.6723*T**a)-(0.040035*T**3)
T 8800 - * ~
'~ * ~
i 11 1 I
- s M 2700 -
1 R N E I-TOT DRCF HORMALIZED TO 1 UCI/M**3 I-131 j [B "2600 -
) H A. Time from shutdown to time E R 4 .
of release in hours = hr i g R / 2500 -
4 U
- o B C B. Tine for transport = (Desired Distance) / (Wind Speed) j Y I B400 -
( mi)/( mph) =
!U 1 M
hr i.
0 C. Total decay time = (Step A) 0
- 2300 -
+ Step B)
( )+( ) = hr F 2200 -
. Correlate the total decay time (hours o following shutdown) to the curves to R determine the dose conversion factors l
2100 - for Noble Gas.
P A
R gggg _
7 (B) I I I I I I I I I I I ' ym 1900
- O 10 20 30 g TOTAL DECAY TIME - IIOURS 40 50 60
*]
s O
EP IV-ll4 Attachment 8 ATTACHMENT 8 EXAMPLE PRINTOUT OF DOSE CALCULATIONS BASED ON RELEASE RATE TIME Distance from Site (miles) 3.00 00 Al Distance from Site (meters) 4.83 03 A2 Xu/n (1/M2 X 10-6) 3.20 00 B Wind speed (u) in meters /second 2.25 00 C plume Travel Time (ETA) hrs min. 360.00-03 D Dispersion X/O (1/m2) 1.42-06 E Iodine Release Rate (Ci/sec) 1.20 00 F1 Noble Gas Release Rate (Ci/sec) 100.00 00 F2 Dispersion Model Projected Iodine Concentration at distance A 1.71-06 G1 Dispersion Model Projected Noble Gas Concentration at distance A 142.22-06 G2 Measured Iodine concentrations (if any) (uCi/cc) 0.00 00 G'l Measured Noble Gas Exposure Rate (R/hr) (if any) 0.00 00 G'2 Dose Rate Conversion Factor-Iodine (rem-m3/Ci-hr) 5.60 00 H1 Dose Pate Conversion Factor-Noble Gas (rem-n3 /Ci-hr) 3.30 00 H2 Calculated Thyroid Dose Rate-Model 9.56 00 Il Calculated Whole Body Dose Rate-Model 46.93-03 I2 Thyroid Dose Rate-Field Data (if any) 0.00 00 I'1
, Whole Body Dose Rate-Field Data (if any) 0.00 00 I'2
\s / Estimated Duration of release (hrs. min.)
(3.30 = 3 hours, 30 minutes) 3.30 00 J Calculated Thyroid Dose Commitment-Model 33.45 00 K1 Calculated WB Dose Commitment-Model 164.27-03 K2 Thyroid Dose Commitment-Field Data 0.00 00 K'l Whole Body Dose Commitment-Field Data 0.00 00 K 2 INPUT CHECK i
l Distance in miles 3.00 00 A l
Xu/O X 10-6 3.20 00 B Noble Gas Release Rate (Ci/sec) 100.00 00 C Iodine Release Rate ( Ci/se c) 1.20 00 D l Wind Speed in mph 5.00 00 E Measured Iodine Field Conc. (if any) 0.00 00 A' Measured Field Exposure Rate (if any) 0.00 00 B' Estimated Duration of Release (hrs / min) 3.30 00 C' Iodine DRCF X'106 (rem-m3/Ci-hr) 5.60 00 D' Noble Gas DRCF X 102 (rem-m3/Ci-hr) 3.30 00 E' O 18 of 22 Rev. 0
~
O O O ATTACHMENT 9 PROGRAM DATA FORM RELEASE RATE DOSE CALCULATION ,
TIME (A) (B) (C) (D) (E) (A') (B') (C') (D') (E')
OF DISTANCE Xu/O* NOBLE IODINE WIND MEASURED ** MEASURED ** ESTIMATED IODINE *** NOBLE ***
DATA FROM x GAS RELEASE SPEED FIELD FIELD DURATION DRCF GAS DRCF
, 24 HOUR SITE 10-6 RELEASE RATE (mph) IODINE EXPOSURE OF x x CLOCK (MILES) RATE (Ci/sec) CONCENTRATION RATE RELEASE 106 102 (Ci/sec) (pC1/cc) (R/h r) (hrs / min) (rem-m3/ (rem-m3_
, Ci hr) Ci br) i I
4 5
A y ,
I
.; INITIALS NOTES: *Taken from Attachament 11 i
**If available
***Taken from Attachments 6 and 7 o
ATTACRMENT 10 CALCULATION SNEET FOR ABSOR8ED DOSE RATES AND DOSE COMMITMENTS
( AIRBORNE RELEASES)
DATE TIME (24 BR CLOCK)
PREPARED BY A D C C' I I' K I' DISTANCE PLUMF CALCULATED MEASURED CALCULATED DOSE CALCULATED FROM TRAVEL ATMOSPRERIC ATMOSPRERIC DOSE RATE RATE DOSE DOSE SITE TIME CONCE5.~TRATION CONCENTRATION FROM BASED ON COMMITMENT COMMITMENT T X (C1/m3) DISPERSION FIELD FROM BASED ON Al MILES (h r. min) (C1/m3) NDBLE gas NODEL MEASUREMENT DISPERSION FIELD A2 FFITDI ETA EXPOSURE RATE (res/hr) (ren/hr) MODEL MEASUREMENT (R/h r) ** ** (ren)** (ren)**
Al G1 G'1 Il I'1 K1 K'1 A2 G2 C'2 R44r 12 I'2 K2 K'2 11 G1 G'1 11 I'1 K1 K'1 62 G2 C'2 R/hr I2 I'2 K2 K'2 1 C1 G'1 Il I'1 K1 K'1 A2 C2 C'2 R/hr I2 T'2 K2 K'2 Al C1 G'1 Il I'1 K1 K'1 A2 C2 G'2 R/br 12 I'2 K2 K'2 Al C1 C'1 Il I'1 K1 K'1 A2 C2 C'2 R/hr 12 I'2 K2 K'2 Al G1 C'1 Il I'1 K1 K'1 A2 C2 C'2 R/hr 12 I'2 K2 K'2 f Al C1 G'1 Il I'1 K1 K'1 sr o A2 C2 G'2 R/hr I2 ,I ' 2 K2 K'2 NOTE: THE TOTAL DECAY TIME IS THE SUM OF THE TIME FROM REACTOR SHUTDOWN UNTIL THE TIME OF PLUME ARRIVAL. NO CREDIT WILL BE TAKEN FOR I DEPLETION FROM THE PLUME OR DECAY IN TRANSIENT.
LETTERS CORRESPOND TO LETTERS IN OUTPUT OF PROGRAM
- NUMBER FOLLOWING LETTER IS INTERPRETED AS FC;J M S: 1 (ONE) = IODINE 2 (TWO) = NOBLE CAS
** NUMBER FOLLOWINC LETTER IS INTERPRETED AS FOLLOWS 1 (CNE) = TRYROIDr 2 (TWO) = WHOLE 80DY 20 of 22 24%_A
t EP IV-114 Attachment 11 ATTACRMENT 11 Xu/O VALUE DETERMINATION Select the Xu/n values that correspond to the stability class as determined by the d temperature, distance from the site and the release point (ground or elevated).
- 1. USE THE 4 TEMPERATURE VALUE FROM THE METEOROLOGICAL TONER TO DETEMtINE STABILITY CLASS.
Primary Instrument NOTE 3nn ft. - 33 ft. temperature ('C)
UN9?ABLE IS 1 -1.3'C UNS: TABLE e NFffrRAL STABLE NECTRAL IS > -1.3*C < -0. 5'c
-1.3 -0.5 STABLE IS > -0.5'C sackup Instrument NOTE 150 ft. - 33 ft. temperature ('C) UNSTABLE 15 1 -0.6'c UNSTABLE NEUTRAL e STABLE NEUTRAL IS > -0.6 1 -0.2'c STABLE IS > -0.2*C
-0.6 -n.2
- 2. DISTANCE CROUND IEVEL RELEASE (E-6/m2) ELEVATED LEVEL RELEASE (E-6 /m2)
METFRS MILES UNSTABLE NEUTRAL STABLE UN3 TABLE NEUTRAL STABLE 1000 0.62 15 61.39 244.8 18.28 45.1
- 127n MEA 0.79 9.95 41.5 227 12.4 42.2 **
2nna 1.2 4.64 22.49 168.0 6.13 27.99 .017 3non 1.9 2.32 - 12.20 113.3 3.12 17.26 .793 40nn 2.5 1.42 7.86 81.7 1.92 11.72 3.54 5000 3.1 .968 5.58 62 3 1.31 8.55 7.22 60nn 3.7 ,.708 4.21 49.5 .963 6.56 10.48 7non 4.4 .543 3.32 40.5 .740 5.23 12.81 An00 4.9 .432 2.70 34.0 .589 4.28 14.26 8045 LP2 5.0 .42 2.5 33.3 .57 4.06 14.3 anon 5.s .353 2.25 29.0 .481 3.50 15.02 Innon 6.2 .294 1.91 25.2 .402 3.06 15.29 11000 6.8 .250 1.65 22.1 .341 2.65 15.23 12nnn 7.5 .215 1.44 19.6 .294 2.32 14.95 13nno 8.1 .187 1.27 17.6 .256 2.05 14.55 1400n 8.7 .165 1.13 15.9 .225 1.83 14.06 15nno 9.3 .146 1.02 14.4 .200 1.65 13.54 1spon EP2 9.9 .131 .952 13.2 .179 1.49 13.01 MFA - Minimum Exclusion Area LPt - Low Population Zone EP2 - Puergency Planning tone
*Value of Xp/O for Inn 0 meters distance = 5.33E-16/m2
**Value of Xu/O for 1270 meters distance = 1.35E-12/m2 Distance xp/O = E-4/m2 (ground) Ip/O = E-6/m2 (elevated)
NOTFs Other locations EP IV-11 1 21 of 22 Rev.0
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EP IV-Il4 -
(7 Signature Page Prepared By: [2[wj/
// 7 ~ /
Reviewed By: W /b [W Department Head Date Reviewed By: f' sfj$ 4 f-/d -W Nuclear E drgency Planning Engineer Date Reviewed By: 9 3 2 Station Quality Assura Review Dat'e 1
(i r ired e ,1 VI 2 SORC Meeting No.: [ M bate!
Approved By: /[9, 9/2-3[M General Manager - Salem Operations Date Approved By: 9 f!f2 Manager - Nuclear Site Protection D' ate l
l O 22 of 22 Rev.0
l I
EP IV-118 EMERGENCY PROCEDURE EP IV-118 HIGH ACTIVITY SAMPLE ANALYSIS ACTION LEVEL Any requirement to analyze a sample which has an exposure rate of 20 mR/hr at a distance of 8 inches. (Refer to EP IV-301 or EP IV-302, as appropriate.)
PESPONSIBLE INDIVIDUAL A Technical Supervisor of Radiation Protection or Chemistry shall be responsible for implementing this procedure.
LIMITS ON AUTHORITY
() Prior to proceeding with high activity sample analysis, dose estimates shall be evaluated. Approval of the Senior Shift Supervisor /EDO is required prior to analysis of any samples that may result in exposures in excess of 10CFR20. 101 limits.
ACTION STATEMENTS
- 1. Evaluate the analysis request for relative priority. If a result is not essential, consider its postponement until backup instrumentation arrives.
- 2. Notify the Chemistry or Padiation Protection Counting-Rooms that a high activity sample is to be analyzed.
j 1 of 8 Rev. 2
EP IV-118 ACTION STATEMENTS (continued) l NOTE ;
Normally, the Chemistry Counting Room would be designated the " hot" lab. In the event of an accident, the Radiation Protection Counting Room is more likely to retain a low background. Inform requestors where to deliver samples. A separate procedure shall be used for sample collection and handling until it is delivered to the appropriate counting facility.
- 3. Determine sample quantities awaiting analysis and consider establishing relative
- priorities for each before the backlog gets x_
excessive. Samples and data for evaluating Protective Action Guides should get the highest priority.
- 4. Ensure designated counting lab is prepared for sample arrival and don protective clothing, which, at a minimum, shall consist of lab coat and either one pair of rubber or two pairs of Latex (Surgeon's) gloves.
- 5. Ensure extremity TLD's are properly worn as required by REP instructions.
- 6. On receipt, survey the sample (preferably with a Teletector) and store in lead pigs, if available, apart from occupied areas, for exposure reduction.
2 of 8 Rev. 2
EP IV-Il8 ACTION STATEMENTS (continued)
- 7. Record survey data on Attachment I and calculate dose estimates for extremity using contact gamma dose rate and use general area radiation levels for whole body estimates.
When calculating dose estimates, approximate times for sample analysis are fifteen (15) l minutes for the first sample and six (6) i minutes for successive samples. Calculate dose estimates on Attachment 1.
R. Handle all samples with tongs or tweezers.
- 9. Continue monitoring background radiation levels for marked increases.
O 10. Continue to monitor your exposure. Use pocket dosimeters and calculations and continue updating exposure status. If doses exceed or are likely to exceed previous determined limits contact the Dose Assessment /ALARA Supervisor (located at the TSC, ext. 3309, 3310).
- 11. Sample Reduction (to obtain samples of 20 mR/hr at 8 inches for GeLi Analysis):
i .
O O
3 of 8 Rev. 2
[0 \ EP IV-118 ACTION STATEMENTS (continued) 4 a) Divide 20 mR/hr by the gamma dose rate at 8 inches to get reduction factors, e.g.,
20 mR/hr = 1 500 mR/hr 73 and multiply the sample weight by the reduction factor to get maximum desirable portion of sample. For example, if the above sample weight is 50 grams, 1 x 50 grams = 2 grams 25 you will have to use no more than 2' grams
() of the sample for ultimate counting.
This ensures dead time losses of less than 10% for samples counted at 8" from the detector.
b) Iodine Filters Work in vented, filtered hood. Place clean paper on scale for each weighing operation. Determine desired fraction and weight of portion of original sample and separate from balance of filter con-4 tents. Remove a similar amount of sample media in a plastic bag. To this bag, add the portion of the sample, twist and seal, and chake. Return contents to (or place bag and contents into) an unused O- 4 of 8 Rev. 2
EP IV-118 t
O ACTION SPATEMENTS (continued) container and tape. Discard remaining ]
sample media and conister into radio-active waste. What remains is a diluted sample in identical geometry to the original. Seal in bag or saran wrap.
Proceed with' standard laboratory counting methods and ensure you account for lost counts from sample reduction and dead time.
- c. Particulate Filter Work in a vented, filtered hood. Place clean paper on scale for each weighing
() operation. Determine what portion of the sample is to be used as per section "a" and cut out a slice (like a pie slice).
Seal in plastic bag or saran wrap and count. Proceed with standard laboratory methods and ensure that you account for lost counts from sample reduction and dead time.
- 12. Lead filters of various thicknesses may be used in lieu of sample reduction to reduce the instrument dead time to an acceptable level (>10%).
- 13. Wrap sample in clean saran wrap or equiv-alent for storage. If sample is to be saved it must be properly identified and a log
- kept of sample information.
5 of 8 Rev. 2
__,__ ____._-_. _ __.-_~__- _ ..- _ _-.__. _ __ ____ __ _:._-.__ _ . - - - . - - _ _ . -
d I
EP IV-118 O ACTION STATEMENTS (continued)
NOTE Samples should be stored in a suitable area which will not cause significant change to background radiation levels. If sample causes a high radiation area to be formed in the immediate area then a storage facility should be used which is capable of being locked.
(Possible storage rooms would include the Source Room - 100' El. Service Building or Gamma Calibrator Room - 100' El. Auxiliary ,
Building.)
- 14. Report results to requetor and the Dose Assessment /ALARA Supervisor.
- 15. Keep track of your exposure.
- 16. Monitor lab for contamination and airborne radioactivity. Decon as necessary.
l s
6 of 8 Rev. 2 l
l
EP IV-118 ATTACHMFNTS Dose Assessment / Sample Size Reduction Worksheet COMMUNICATIONS NETWORK Dose Assessment /ALARA Supervisor Radiation Protection (TSC) Chemistry Lab Lab 3309 3060 3209 3310 NOTE Forward all completed forms to the Nuclear Emergency Planning Engineer. Attach other complet.ed EP's or attachments used.
Prepared By: M /g
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[YM i
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Reviewed B _
f 3 J> t/
, [ Department Head Date Reviewed By:
Nuclear Emergency Planning Engineer Date Reviewed By: cp .r f N Station Ouality isstbance Revi Date SORC Meeting No.: > [ 2/
Date' Approved By: / f/A 3/#
General Mana'ger - Salem Operations Date Approved By: 9 .T /t.-
Manager - Nuclear Site Protection Date l
7 of 8 Rev. 2 l
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d EP IV-Il8 ATTACHMENT 1 DOSE EVALUATION AND SAMPLE SIZE REDUCTION WORKSHEET
- 1. DATE TIME
- 2. SAMPLE INFO: (a) LOCATION (b) LOCATION (c) LOCATION i
(d) LOCATION (e) LOCATION
- 3. PREVIOUS EXPOSURE DATA OUARTER TO DATE NAME/SS# WHOLE BODY EXTREMITY a.
b.
c.
d.
) 4. Use a dose limit of 1000 mrem whole body or 10,000 mrem extremity.
If you anticipate exceeding these, contact the Dose Assessment /
ALARA Supervisor at the TSC. If you anticipate exceeding 1500 mrem l whole body or 15,000 mrem extremity, obtain permi'ssion of'the Dose Assessment /ALARA Supervisor and the Senior Shift Supervisor /EDO.
! 5. Estimate time required to get results (e.g., 15 minutes for first sample, 6 minutes for each successive one) and dose:
S AMP LE GENERAL AREA MR/HR CONTACT MR/HR X X TIME = W/B DOSE TIME = EXTREMITY DOSE A (1/4) (1/4)
B (1/10) (1/10)
C (1/10) (1/10)
D (1/10) (1/10)
- 6. Calculate Sample Reduction Factor:
l l
20 mr/hr = R.F. R.F. X WEIGHT = REQUIRED PORTION OF _ SAMPLE mr/hr at 8" A.
\_/ B.
C.
-D.
8 of 8 Rev. 2
EP IV-122 b
ks/ EMERGENCY PROCEDURE EP IV-122 EMERGENCY STAFFING GUIDE ACTION LEVEL This procedure is to be followed whenever the Radiation Protection Organization is implemented, normally by order of the Senior Shif t Supervisor /EDO.
RESPONSIBLE INDIVIDUAL The Radiation Protection Engineer or the Senior Radiation Protec-tion Supervisor shall assure the Radiation Protection Emergency Organization is implemented and adequately staffed.
LIMITS ON AUTHORITY O The Radiation Protection Engineer / Senior Radiation Protection Supervisor has the authority to request additional personnel as required to meet Radiation Protection emergency staffing require-ments. Staffing sources are company personnel and/or contractor supplied personnel.
ACTION STATEMENTS TIME INITIAL
- 1. Determine the potential length of the emergency and follow the suggested staffing guide.
<1 hour - No additional staffing
<6 hours Call all available normal staff to Station
<24 hours - Provide coverage using
() available staff on an over-time basis 1 of 7 Re v. 1
l l
EP IV-122 I
ACTION STATEMENTS TIME INITIAL
>24 hours - Place normal staff on 12
<7 days hour shifts, alert contracting agencies that additional personnel may be required
> 7 d ays - Staff through company and contractor personnel as required by conditions
- 2. EP IV-101, Technical Support Cc: ster Activition, shall be used for all notifica-tions within the Radiation Protection organization.
i
- 3. Assistance for equipment and personnel requests can be processed by the office Administrator or through the Emergency Response Manager's office.
- 4. Complete staffing for outage conditions (Attachment 2) is recommended for emergency conditions lasting greater than 7 days.
- 5. The required staffing will be placed on shifts on an as needed basis. Shift scheduled will be set up so as to provide for the best utilization of available personnel.
2 of 7 Rev. 1 W - -
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EP IV-122
/
ACTION STATEMENTS TIME INITIAL
- 6. The normal processing time for contractor personnel when they arrive on site is one week. Previously trained contractor personnel should be requested when possible.
NOTE As a result of the rapid increase in personnel, assure that adequate sapervision and coordinating personnel are available.
- 7. A partial list of Radiation Protection contractors is provided in Attachment 1.
ATTACHMENTS
- 1. List of Radiation Protection Contracting Companies
- 2. Radiation Protection Department Emergency Staffing
- 3. Radiation Protection Department - TSC Staffing l
COMMUNICATIONS ~ NETWORK CONTROL POINT TSC TRAINING MAIN GATE RP OFPICE,
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3 of 7 Re v. 1
- - - -~
EP IV-122 DISCUSSION In an emergency situation, there are many tasks that'are required to be done. Through the effective use of available and incoming personnel, these tasks can be performed in the most efficient manner possible.
Many personnel, not traitted in Radiation Protection, can be used to fill various required positions with minimal training.
NOTE Forward all completed forms to the Nuclear Emergency Planning Engineer. Attach other completed EP's or attachments used.
Prepared B
/_ , . _
Reviewed By* A 9 /7 P" U
[ Department Head Date Reviewed By: q.f f Nuclear dmergency Planning Engineer Date Reviewed By: o f3 L--
Station Ouality Aksur ce Engine Da't
)
SORC Meeting No. : .
U/ 6 h '
Date Approved By: / hId W- ' f/J. J/M General Manager - Salem Operations Date Approved By: ] f/ J [2 Manager - Nuclear Site Protection Date 4 of 7 Re v. 1
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EP IV-122 Attachment 1
~
ATTACHMENT 1 RADIATION PROTECTION CONTRACTING COMPANIES Allied Nuclear . . . . . . . . . . ..
Applied H.P. . . . . . . . . . . . .,
Bartlett Nuclear . . . . . . . . . . I I
I
- Hydro Nuclear Services . . . . . . .
IRM . . . . . . . . . . . . . . . .
Numanco . . . . . . . . . . . . . ..'
] NSS . . . . . . . . . . . . . . . ..
k
- Rad Services, Inc. . . . . . . . . .. *
- Currently have contracts at Salem A more complete list of contracting companies supplying services and material. can be found in EP IV-212.
3 5 of 7 Re v . 1
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EP VI-122 ATTACHMENT 2 RADIATION PROTECTION DEPARTMENT EMERGENCY STAFFING DECON/
OPERATIONS RPT's ASST'S HELPERS CLERKS SUPV'RS LAUNDRY Control Point 6 12 12 2 Containment 3 9 3 Auxiliary Building 12 3 Operating Unit 3 6 3 Rad Waste 3 3 2 45 REP Room 3 3 3 Dosimetry 2 Dosimetry 3 3 Counting Room 3 3
() Eauipment Instruments 3 3 3 2
Respirators 3 6 Administration 8 2 TOTAL R 37 3T T T6 TT 135 Rad Protection Personnel 45 Decon Personel (This staffing assumes 3 complete shifts.)
O- 6 of 7 1
Rev.
EP IV-122 Attachment 3 ATTACHMENT 3 RADIATION PROTECTION DEPARTMENT TECHNICAL SUPPORT CENTER STAFFING l
RPE/ SENIOR RADIATION PROTECTION SUPERVISOR j SHORT TERM PHONE TALKERS TSC DOSE ENVIRONMENTAL CONTROL CONTROL SURVEYS ASSESSMENT MONITORING ROOM E.O.F. POINT RADIO Radiation Radiation Shift Radiation TSC TSC TSC TSC Protection Protection Protection RPH/ RPH/ RPH/ RPH/
Assistant Supervisor Technician Clerk Clerk Clerk Clerk Telecopier RPH/ Clerk RADIATION PROTECTION DEPARTMENT Technical Support Center Interim Staffing SHORT TERM ENVIROMENTAL MONITORING PHONE TALKER Shift Radiation Protection Technician Control Room to TSC l
l 7 of 7 Rev. l' l . . . . . _ _ . . . . . _ -
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l l
EP IV-301 EMERGENCY PROCEDURE EP IV-301 INTERIM POST-ACCIDENT PRIMARY COOLANT SAMPLING APPLICATION After a reactor accident in which a significant fraction of the core fission-product inventory is released, normal sampling vill not be possible because of the extremely high radiation fields.
The Sentry High Radiation Sampling System will be used for obtaining diluted and undiluted samples and performing certain in-line analyses during accident and conditions. Until this system is operational, the interim post-accident sampling system can be used to withdraw a single diluted reactor coolant sample under accident conditions. Either of two (2) reactor coolant hot legs or either of the RHR's can be sampled utilizing the Interim System.
Sampling is performed by purging a temporary sample line from the s- outlet of a sample cooler to a shielded waste bottle. A four-way valve captures approximately 0.09 ml of the sample in this line.
When the valve is rotated 90', dilution water flushes the sample in to a serum vial. The 1:100 diluted is used for hydrogen and boron analyses. The gas phase is analyzed for hydrogen and fission gas and the liquid phase is analyzed for boron and other fission products.
The procedure considers fission gas, hydrogen, and the high radiation fields. Design bases of the interim system are provided in Attachment 1.
APPARATUS Details for fabrication and a list of material required for the interim system are provided in Attachment 2.
1 of 30 Rev. 2
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1 1
-s EP IV-301 )
PRECAUTIONS -
- 1) Post-accident reactor coolant is extremely radioactive. Gases released from the sampling operation will be mostly hydrogen and fission gases. Airborne fission gases could result in extremely high radiation fields and hydrogen collected in waste bottles
+
without an inert cover gas may result in an explosive mixture.
The relatively small amount of halogen gases can cause very significant contamination problems.
- 2) Avoid cross-contamination by disposing of labware as radioactive waste. Any droplets of liquid from this operation will result in high surface contamination.
- 3) Frequently change rubber gloves when diluting and analyzing sampics.
- NOTE Normally, the Chemistry Counting Room would be designated the " hot" lab. In the event of an accident, the Radiation Protection Counting Room is mcre likely to retain a low background. Inform requestors where to deliver samples. A separate procedure shall be used for sample collection and handling until it is delivered to the appropriate counting facility.
PRERFOUISITES
, TIME INITIAL A. RADIATION PROTECTION i 1. Verify that Radiation Protection has a high range (0 - 1000 R/hr) survey meter for I
(
\
surveying all sampling and analysis operations.
2 of 30 Rev. 2
EP IV-301 PREREOUISITES TIME INITIAL A. RADIATION PROTECTION (continued)
- 2. Verify all personnel are wearing protective clothing, required respirators, and dosimetry as specified by Radiation Protection.
- 3. Verify that all personnel have been thoroughly briefed by Radiation Protection as per EP IV-106, "ALARA Task Review Instructions".
B. FUME HOOD PREPARATION
- 1. Remove all non-essential equipment from the fume hood which is to be used for sample dilutions and anayses. .
- 2. Assemble a body shield in the fume hood using lead bricks. A stack of 2 x 4 x 8 inch lead bricks, five high and three long will supply adequate shielding.
- 3. Place a metal tray within the fume hood to l contain all dilution and anaysis liquids.
- 4. Place a box of tissue inside the fume hood.
- 5. Tape a yellow poly bag within the fume hood with the top of the bag cut approximately two inches. The bag is to be used for containing all solid waste material generated during dilution operations.
( 6. Place a strip of blotter paper in front of the fume hood and tape the edge to the floor.
3 of 30 Rev. 2 v +--p. 9-.y ., -w,_ . - - - w- --
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EP IV-301 PREREOUISITES (f
TIME INITIAL B. FUME HOOD PREPARATION (continued) !
- 7. Place several pairs of rubber gloves on the lip of the fume hood in a position to permit easy and fast donning.
- 8. Prepare a shielded waste container for disposal of waste sample solutions.
C. FUME HOOD APPARATUS AND REAGENTS 1
- 1. Verify the following apparatus and reagents are available for performing boron analysis.
a) Fisher Accumet pH meter l b) Three (3) Nalgene 30-m1 plastic beakers filled with 4.5 ml of demineralized water c) Eppendorf or Oxford 1-ml pipette and tips i
d) Oxford adjustable 1-5 mi pipette and tips
^
e) Oxford 500 ul piette and tips #
i f) Demineralized water g) Fluoroborate Specific Ion Electrode ,
h) Plastic Single Junction Reference Electrode
- 1) Stopwatch for timing analyses j) Saturated Sodium Fluoride Solution k) 10 N Sulfuric Acid
- 1) 20 ppm Boron standard m) Magnetic stirrer and microstirring bar n) Current calibration curve
, 2. Soak the electrodes in demineralized water for l at least 10 minutes, or as long as possible prior to use.
i 4 of 30 i
l Rev. 2 I____ , _ _ _ . _ _ _ . _ _ _ _ . . . _ - . _ - . _ - _ _ _ _ _ _ . _ . . . _ , _ _ . ,
EP IV-301 O PREREOUISITES (continued)
TIME INITIAL C. FUME HOOD APPARATUS AND REAGENTS (continued)
- 3. Standardize the fluoroborate system using the relative millivoit mode as detailed in Procedure P D-3. 2. 0 8 0. -
- 4. Verify the following apparatus is available for performing gas sampling and dilution.
a) Snare for sample transfer b) 1 cc and 5 cc gas syringes c) 67 cc gas dilution bulb d) 5 cc gas counting vials e) Plastic wrap
- 5. Verify the following apparatus and reagents are available for performing liquid sampling and dilution.
a) Crucible tongs b) Tweezers c) 25 ul Oxford pipette and tips d) 100 n1 Oxford pipette and tips e) 250 ul Oxford pipette and tips l
i f) 500 ml Oxford pipette and tips g) Liquid counting vials, fulled with 10 mi of demineralized water h) Plastic wrap i) 100 mi volumetric flask, filled with demineralized water O
5 of 30 Rev. 2
f EP IV-301 O PREREOUISITES (continued)
TIME INITIAL D. GAS CHPOMATOGRAPH
- 1. Place several lead bricks on the lab bench near the gas chromatograph for sample shielding.
- 2. Verify that a sufficient supply of argon carrier gas is available to the gas chromatograph.
- 3. Verify that the gas chromatograph is in a standby condition with a current calibration check performed prior to initiating sampling.
- 4. Verify the following items are available near
! the gas chromatograph.
a) 100 and 1000 ul gas syringes b) Yellow poly bag containing absorbent material c) Cord or tape d) Snare and tongs e) Calibration curve s
E. POST-ACCIDENT SAMPLING SYSTEM
- 1. Open or check open the following valves:
a) Valve #1 b) Valve A2
! c) Valve #4 d) Gas vent line isolation valve
- 2. Align Valve 43 to the horizontal position.
1 6 of 30 l
Rev. 2
'^
1 EP IV-301 O PREREOUISITES (continued)
TIME INITIAL
- 3. Back purge the waste bottles with an inert gas for a minimum of five minutes.
- 4. Close valve #2 and #4.
- 5. close the gas vent line isolation valve.
- 6. Secure inert gas supply.
- 7. Verify the following items are available for the Post-Accident Sampling System:
i a) Lab jack b) 5 cc syringe with needle 1 O c) 20 cc syringe d) Stopwatch e) Wbod block with sample bottle f) Adjustable strench g) 7/16 inch open end wrench h) 11/16 inch open end wrench PROCEDURE TIME INITIAL ,
A. SAMPLING TEAM NO. 1 l 1. Enter the primary sample room and verify that
, the reactor coolant sampling system is isolated at the containment penetration valves, 1(2)SS104 and 1(2)SS33.
O 7 of 30 Rev. 2
^
l l
EP IV-301 l
PROCEDURE (continued) 1 TIME INITIAL ;
- 2. Check for green closed indication lights for valves 11(21)SS32,13(23)SS3 2, 11(21)SS22, and 12(22)SS22 on Panel 307-1(2).
- 3. Attach the syringe containing 15 ml of DM water to the sample dilution line. Ensure that the diluter valve, Valve 43, is in the up/down position. Force enough water from the syringe to allow water to flow from the hypodermic needle in a solid stream at the needle tip.
Ensure that 9.0 ml of water remains in the
! syringe.
j NOTE See Figure 1 in Attachment 2 for valve identification.
- 4. Switch the diluter valve, Valve #3, to the horizontal position to accept sample flow when the isolation valves are opened.
- 5. Position the sample vial in the wooden block holder into position under the needle at the diluter valve. Use a lab jack or other supporing objects as appropriate.
- 6. Visually verify that the needle has punctured l the septum. Evacuate the Wheaton sample bottle with a gas syringe.
'l lO j 8 of 30 Rev. 2
~1 EP IV-301 O PROCEDURE (continued)
TIME INITIAL
- 7. Step back from the sample station and carefully position the syringe in the designated holder with the sample dilution line fully extended from the sample station.
! 8. Actuate the switch to raise the sample transfer dumbwaiter to the sample room position. If the equipment is inoperable, notify supervision to have a carrier on standby to hand carry the sample to the laboratory.
i
- 9. Close or check closed valve 1(2)SS245 and 1(2)SS35.
- 10. Open the reactor coolant primary sample sink Valve No. 1(2)SS46 to relieve pressure on the
- sample line. Break the sample line connection
- on the outlet of the sample cooler and reconnect t the temporary line of the emergency sampling system.*
CAUTION 1
When reconnection is made, use extreme care not to cross-thread the fitting. The connection should be tightened securely to avoid any leak-age of the highly radioactive liquid flowing through this line.
- 11. Inspect the sampling system. Ensure all fittings are tight.
9 of 30 Rev. 2 i
,,.,..--,.-.---,,_n--- ...-_,,,.,.v-----.--,--- - , - - , . ,
EP IV-301 O PROCEDURE (continued)
TIME INITIAL ,
1
- 12. If either RHR is to be sampled, proceed to Step 14.
- 13. If either RCS hot leg is to be sampled, request the Control Room operator to open the contain-ment isolation valves, 1(2)SS104 and 1(2)SS33.
Open Valves No. 1, 1(2)SS35, and No. 2. Open
, the reactor coolant sample panel isolation valve ll(21)SS32 or 13(23)SS32, depending on which hot leg is to be sampled. Check for red light open
- position indication at sample panel 307-1(2).
Proceed to Step 16.
MONITOR DOSE RATES
- 14. For a RHR heat exchanger outlet sample, open valve 1(2)SS24.
i 15. Open Valves No. 1 and No. 2. Open RHR Heat Exchanger Outlet Sample Isolation Valve 11(21)SS22, depending on which heat exchanger is to be sampled. Check for red light open l position indication at sample panel 307-1(2).
MONITOR DOSE RATES l 16. Crack open Valve No. 4. Rapidly adjust the flow l rate to approximately 0.42 gpm on the flow me te r. Observe the flow meter from outside the cubical using the mirror mounted on the opposite '
wall.
10 of 30 Rev. 2
EP IV-301 i
PROCEDURE (continued) i 4
TIME INITIAL !
1
- 17. Note the time that flow was established and immediately exit the sample room. Relay the sample time-to Team No. 2 so that the sample can be collected after a three minute purge. I B. SAMPLING TEAM NO. 2
- 1. After the sample line has purged to waste'for approximately three minutes, isolate the sample by rotating the diluter valve (Valve No. 3) 90' and immediately deliver 9.0 ml of water using the syringe, and secure flow with Valve No. 4, then rotate valve No. 3 90* using the valve reach rods.
- 2. Observe the flow meter using the wall mounted mirror and verify no flow.
- 3. If RCS is sampled, close reactor coolant sample
. panel isolation valve 11(21)SS32 or 13(23)SS32, if RHR heat exchanger outlet is sampled, close RHR sample isolation valve 11(21)SS22 or 12(22)SS22 and immeidately exit the sampling room.
- 4. Immediately after exiting, notify the Control Room operator to close containment isolation valves 1(2)SS104 and 1(2)SS33 for RCS sample.
O 11 of 30 l Rev. 2 l
l - - __ ---__-_-. . - - - - - - . - -. - - - - -- - - - - ' --
EP IV-301 PROCEDURE (continued)
TIME INITIAL C. HYDROGEN ANALYSIS AND TRANSFER - TEAM NO. 3
- 1. Immediately lower the septum bottle from the needle. Hold the wooden bicck with one hand during this operation.
- 2. Place the sample behind several lead bricks on the lab bench near the gas chromatograph.
- 3. Using a gas syringe, withdraw a 100 ul or 1 mi aliquot directly from the serum bottle.
CAUTION x_- Keep the needle tip well above the liquid level so that only the gas is withdrawn.
NOTE Assuming a 0.09 ml diluter value volume and a 8.0 mi serum bottle gas space, the following hydrogen concentrations should be expected:
cc H 2/kg Q 100 0.11 503 0.56 1000 1.12 2000 2.25 5000 5.62 l
l lO 12 of 30 Rev. 2
EP IV-301 O PROCEDURE (continued)
TIME INITIAL
- 4. Inject the sample into the gas chromatograph and record the aliquot in Step No. 1 of the Dissolved Hydrogen Data Calculation Sheet in Attachment No. 3 NOTE A 100 x1 injection will result in approximately 1.4 uCi of gaseous activity being released by the gas chromatograph to the room one hour after the accident.
- 5. Place the sample vial into a yellow poly bag containing absorbent material. Tie the bag
/) closed with cord or use tape to close the bag.
V
- 6. Leave the sample room or chemistry laboratory and notify laboratoary personnel that the sample is ready for dilutions and analysis.
- 7. After approximately 20 minutes, have one person enter the primary sample room and collect the chromatograph for evaluation.
- 8. Calculate the approximate hydrogen concentration using the Dissolved Hydrogen Data Calculation Sheet in Attachment No. 3 l
- 9. After several days or when Radiation Protection determines conditions are safe, open the gas vent valve and allow the highly radioactive l
gases in the bottle to escape into the operating fume hood.
13 of 30 Rev. 2 L
+
EP IV-301 PROCEDURE (continued)
TIME INITIAL D. ANALYSIS AND SAMPLE DILUTION 4
- 1. Initial operations a) Using a snare, transfer the sample behind the lead bricks inside the fume hood.
b) Remove the wooden block from the poly bag and place the block behind the lead bricks.
c) Take radiation readings at the front of the fume hood.
NOTE Steady the wooden block with one hand as 4
appropriate while withdrawing samples from l the vial, i
- 2. Gaseous Activity a) Withdraw a 1.0 cc gas aliquot from the gas in the serum bottle using a 5 cc syringe.
Inject the sample aliquot into a 67 cc gas dilution bulb.
I b) Evacuate a gas counting vial. Inject a 1.0 cc aliquot (or smaller) of the diluted gas into the vial for counting.
c) Record the injected aliquot (cc) in Step No.
r 3 of the Gaseous Activity Data Calculation
- Sheet.
O '
I 14 of 30
. Rev. 2
EP IV-301 -
PROCEDURE (continued)
TIME INITIAL d) Wrap the counting vial in plastic wrap.
NOTE The vial will contain a 0.14 uCi under worse case conditions.
e) Analyze the sample for fission gas activity.
NOTE If the dead time on the MCA is excessive, increase the lower level discriminator setting to bias out 133 X e activity and
( } recount. Prepare a second sample for 133Xe
. using a 0.1 cc aliquot from the 67 dilution bulb with the lower level discriminator at the normal setting.
f) Calculate the gaseous activity level using the Gaseous Activity Data Calculation Sheet t
in Attachment No. 3.
4
- 3. Isotopic Liquid Sample Analysis NOTE Ensure that the hydrogen results are acceptable before proceeding with this I
step.
- O '
; 15 of 30 i
Rev. 2
9 EP IV-301 PROCEDURE (continued)
TIME INITIAL I a) Hold the wooden block with one hand and remove the septum cap using crucible tongs.
Lower the glass shield on the fume hood and remove the septum using tweezers. Discard j the septum cap and septum as radioactive waste. Close the fume hood.
)
b) After approximately five minutes, open the fume hood. Pipette a 25 ul aliquot into the
! previously filled 100 mi volumetric flask.
Discard the tip as radioactive waste. Cap the flask and carefully mix.
c) Pipette 100 to 500 ul of the second dilution
() into the previously filled counting vial and discard the tip. Cap the vial and wrap with ,
plastic wrap. Record the aliquot volume l pipetted into the counting vial in Step No. 3 of the Liquid Activity Data Calculation Sheet.
d) Remove the vial from the hood and wrap plastic wrap a second time.
e) Count the sample on the MCA. 1 f) Calculate the original sample activity using the Liquid Activity Data Calculation Sheet in Attachment No. 3.
O 16 of 30 Rev. 2
_ - _ . - _ - _ _ _ _ . . - _ _ _ _ . . . - _ _ . _ _ . _ . , , ~ . _ _ - _ _ . . _ _ - _ - _ . . . . ~
I i
EP IV-301 PROCEDURE (continued) l TIME INITIAL l
- 4. Sample for Boron Analysis a) Carefully place the tip of the 500 ul pipette into the serum bottle and pipette 500 #1 of the sample to each of the 30 mi beakers containing 4.5 ml water. Discard the pipette tip as radioactive waste.
b) Analyze the duplicate samples for boron using proedure PD-3.2.08 0.
c) Calculate the ppm boron in the original sample using the Boron Data Calculation Sheet in Attachment No. 3.
- 5. Wrap sample in clear saran wrap or equivalent for storage. If sample is to be saved it must be properly identified and a log kept of sample information.
NOTE l
l Samples should be stored in a suitable area which will not cause significant change to background radiation levels. If sample causes a high radiation area to be formed in the immediate area then a storage facility should be used whfbh is capable of being locked.
(Possible storage rooms would include the Source Room - 100' El. Service Building or Gamma l Calibrator Room - 100' El. Auxiliary Building.)
lO 17 of 30 Rev. 2
s EP IV-301 O
CALCULATIONS See Attachment No. 3.
ACCEPTANCE CRITERIA N/A REFERENCES _
NUREG 0578 and NRC Clarification letters dated October 13, 1979.
NOTE Forward all completed forms to the Nuclear
! Emergency Planning Engineer. Attach any referenced completed EP's or attachments.
i i
'I s
1 i
1 I
18 of 30 i
j Rev. 2
EP IV-301 Prepared By: b Reviewed By: .
.$ 0 OD
/ Department Head Date Reviewed By: [I m 9-- /4-F2--
NuclearEdrgencyPlanningEdineer Date l Reviewed By: , [ Yb Station Ouality Assu[a ce Revie Date if reg ired V- ) , .
SOPC Meeting No.: OA' -
[ '
Date '
Approved By: A[7' 9/.23/&
General Manag'er - Salem Operations Date l Approved By: 9 /L Manager - Nuclear Site Protection Date l
l l
i O
19 of 30 Rev. 2
EP IV-301 ATTACHMENT 1 DESIGN BASES FOR INTERIM SAMPLING SYSTEM i
PARAMETER VALUE Number of post-accident sample 1
~
Pydrogen 2000 cc/kg Radioactivity in diluted sample 900 uci Does rate of diluted sample:
Unshielded: 1350 R/hr at 1 car 356 mR/hr at 2 f t.
Shielded with'2 inch lead 67 R/hr contacts 18 mR/hr at 2 f t.
Furce Volume Inactive purge 3.0 gal., max Post-accident liauid 1.26 gal., max Maximum total of gas generation in waste 10400 cc 9 25c Pstimated pressure in waste gas container 31 psia Doce rate of:
yaste with 1.2e gal. in sand-packed drum e 10 ft. with 4 in. 94 mR/hr of lead 4.nd 9 in. of concrete.
4 f t. of 1/8 in. sample line # 2 f t. with equivalent of 238 mR/hr 2 in. of lead.
4 ft. of 1 in. Tygon vent line for gases 9 4 f t. from waste botcle with no shielding, I he after accident:
No Oilution 55.9 R/hr 163 Dilution 18.6 R/hr These teams are recuired to perform the entire sampling operation. Each team consists of a Chsmistry sampler and a Radiation Prctection person.
20 of 30 i
Rear. 2
EP IV-301 (Q ATTACHMENT 2 FARPICATION AND MATERIALS NEEDED FOR THE INTERIM SAMPLING SYSTEM -
- 1. Desian raiures 1 through 4 illustrate the basic sampling design.
- 2. FKbric'ation Fcbricate the interim post-accident sampling system as illustrated in Figures 1 through 4.'
Fnsure that the following are taken into account.
(1) Purge the waste liquid and gas bottle with inert to provide an inert atmosphere during post-accident sampling, as the explosive limit for hydrogen could be exceeded.
(2) Measure the active volume of the four-way diluter valve prior to installation. This may be accomplished by filling the valve with a 100 ppm chloride' standard solution and diluting with 4.0 ml of water to make a 1 ppm sample for analysis using the sepctrophotometric chloride method. FSrform three measurements and calculate the average volume of the diluter valve from:
Vd = (Avg. ppm chloride measured) x 9.0 ml/100 ppm O^(3) Pack the diluter valve and associated piping in three inches of lead shot.
(a) Drill a wooden block approximately two feet long at one end so that the Wheaton sample bottle fits with approximately one inch extended above the top of the block. Glue the bottle into the block holder.
- 3. List of Materials obtain the following materials for fabricating the interim post-accident sampling system:
- 1. Waste Bottles, 5 gal. . . . . . . . . . . .......................... 2
- 2. Steel drums . . . ........................ . . . . . . . . . . . . . . 2
- 3. Lead bricks, 2 x 4 x 8 in. . . . . . . . .. ....................... 144 A. Lead Shot . . . . ..................... . . . . . . . . . . . . As Required
- 5. Tygon' tubing, 1 in. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . As Required E. Isolation valve for vent . . . . . . . . .......................... I
- 7. 1/R in. OD 0.039 in ID SS caps tubing for sample lines . . . . . . . . . . . . . . As Required R. 40 in. reach rod for valves . . . . . . . ....................... . . . 1
- e. 20 cc syringe with Luer-Loc tip graduation to 0.2 ml (Hamilton No. 1020TSS) . . . . . . . . . I
- 10. Hypodermic needle, point style No. 2 16 gauge x 4 in. (Hamilton No. N17116) . . . . . . . . 2 Lab Jack, 3 x 3 in base, or appropriate support material for wood block . . . . . . . . . . I Os Whitey 4-way ball valve (SS-43YHF2 3-43-00125) ....................... 1
- 13. Vent line outlet isolation valve . . . . ........ . . . . . . . . . . . . . . . . . . I
- 14. Radiarm, 60 in. (Atomic Products No. 010-060) ........................ I
- 15. Radiarm, AR in. (Atomic Products No. 010-048) ........................ I Rev.2 21 of 30
i l
EP IV-301 ATTACHMENT 2 (continued)
INTERIM SAMPLING SYSTEM (continued)
- 16. Wheaton sample vials, 16 al (No. 224806) . .. . .. .. . . . . . . . . . . . . . . . . Case
- 17. Wheaton open top screw caps (No. 240515) . . . . . . . . . . . . . . . . . . . . . . . . Case
- 12. Wheaton solid screw caps (No. 18-425) . .. .. .. .. . . . . . . . . . . . . . . . . . Case
- 19. Wheaton septa, 13 x 20 (No. 240585) . . . . . .. . . . . . . . . . . . . . . . . . . . Case
- 20. CTFE tube fittings ans washer -
1/4 x 20 for 1/8 in. OD tubing (Hamilton No. 88807) . . . . . . . . . . . . .
Spare washers (Hamilton No. 88826)
. . Pack of 10
.. . . .. ... . . . . . . . . . . . . . . Pack of 10 .
- 21. CTFE female Luer connector 1/4 x 28 0.060 in. bore (Hamilton No. 32834) . . . . . ...... 2
- 22. Male Luer connector 1/4 x 28 0.060 in. bore (Hamilton No. 328825) . . . . . . . . . . . . . 2
- 23. TFF tubing, 1/8 in. OD x 1/16 in. ID (Hamilton No. 88922) . . . . . . . . . . . . . . . 10 ft.
- 24. Planging tool kit (Hamilton No. 88821) .. . ... . .. . . . . . . . . . . . . . . . . . .'1
- 25. Wood block with bore for 16 al Wheaton sample bottle, 24 in. long . . . . . . . . . . . . . . 2 SAMPLING AND DILUTION
- 1. Lead bricks, 2 x 4 x 8 in. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24
- 2. Crucible tongs modified with red rubber hose over tips . . . . . . . . . . . . . ...... 1
- 3. Tweezers . . . . . . ... .. . .. . .. . .. . ... . . . . . . . . . . . . . . . . . . 1
- 4. Volumetric flask, 100 ml .. . .. . . . . . . . . . . . . . . . . . . . . . . . ...... 1
- 5. Eppendorf or Oxford micro pipetting system with disposable tips for 25,100, and 50 ul . . . 2 6 Eppendorf or Oxford macro pipetting system with assorted tips for 1 and 4 ml . . . . . . . . 1
- 7. Nalgene beakers, plastic, 30 m1 in helders . . . .. . . . . . . . . . . . . . . . . . . . . 4 4 ~ Waste bottle, shielded with funnel in top . . . .. . .. . . . . . . . . . . . . ...... 1
. . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . 1 s_-.)washbottle.
Gas dilution buld, 67 cc with septum . . . . ... . . . . . . . . . . . . . . . ...... 1
- 11. Cas counting vials . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . 2
- 12. Liquid counting vials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 13. Plastic wrap . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . I roll
- 14. Mirror . . . . . . . . . .. . . . . . . . ......................... 1
- 15. Poly bags . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . As Required
- 16. Snare . . . . . . . . . . . . . . . . . . . ......................... 2
- 17. 5 cc Hamilton gas syringe (Hamilton No. 1005TLL). . . .. . . . . . . . . . . . . ...... I 1R. 1 cc Hamilton gas syringe (Hamilton No. 1001TLL). . . . . . . . . . . . . . . . . ...... I 10 Pypodermic needles, nint style No. 2 (22 guage x 2 in. No. N722) . . . . . . . . ...... 4 22 of 30 i Rev. 2
'e EP IV-301 ATTACHMENT 3 STFD , RECORD l
- 1. Microliters of sample injected into the gas chromatograph.
- 4
- 2. Chromatograph peak area in millimeters.
- 3. Microliters of H2 corresponding to peak area.
I
- 4. Divide microliters in Step No. 3 by microliters in Step No. I and multiply by 100 to determine % Hg.
- 5. Multiply % H2 in Step No. 4 by 900 to yield ccH 2/Kg.
FOPMtfLA t H2x 10-2 x vg (cc)
Vd (ml) x 10-J(Kg/mi) ,
Wherer 10-2 converts percent to a decimal Vg = 8 cc, serum bottle gas space Vd = 0.04 m1, diluter valve volume 10-3 converts mi to kg i
"PFDUCED FOPMt!LA ccH2/WC = % H2 x 889 l
9 i
i N
23 of 30 Rev. 2
l EP IV-301 ATTACHMENT 3
. (continued) 4tFD RECORD
- 1. Pierocuries/cc of isotope measured.
- 2. Multiply Step No. 1 value by 3.0 x 10 4 .
- 3. Record aliquot injected into the counting vial (cc).
- 4. Divide Step No. 2 value by Step No. 3 value to yield uCi/ml.
FOPMULA
_ Vg (ce) x V 2(ce) x V4(ce)
Gaseous activity, uCi/ml =
vd(ml) x v1(ce) x v3(cc)
! Whsrer Vq = 8 cc, serum bottle gas space V2 = 67 cc, dilution bulb volume N.
i V4 = 5 cc, counting' vial volume I
l Vd = 0.09 m1, diluter valve volume V1 = 1.0 cc, aliquot injected into dilution valve v3 = X cc, aliquot injected into counting vial
.RFDUCED FORMULA uCi/mi 1= uCi/cc x 29,77R v3 l
l l
6 s_
l 24 of 30 Rev. 2
(
EP IV-301 ATTACHMENT 3 (continued)
STFP RECORD
- 1. Microcurires/mi of isotope measured, t
; 2. Fultiply Step No. I value by 4.0 x 10 6,
- 3. Record aliquot volume (ml) pipetted into counting vial.
- 4. Divide Step No. 2 value by Step No. 3 value to yield uCi/kl.
F0FMULA Liquid Activity (uCi/ml) =
Vd(al) x V2 (ml) xV4(al) 3re: VI = 9.0 m1, syringe water volume v3 = Inn m1, volumetric flask volume vs = 10 m1, counting vial volums l Vd - 0.09 m1, diluter valve volume i
v2 = 0.025 m1, aliquot delivered to volumetric flask
,. v4 = x m1, aliquot pipetted into counting vial l
NEDUCFD FOPMULA uCi/mi = uCi/ml measured x 4.0 x 106 V4 O 25 of 30 Re:v. 2
s EO IV-301 ATTAChA)iRNT 3 (continued)
STFP RECORD
- 1. moron concentration measured (ppm * , .
- 2. Multiply Step No. I value by 1,000 to yield ppm boron in sample.
FOPMtifA pom Boron Concentration = ppm Boron measured x V i (ml) x V 3 (al)
Vd(al) x v2(ml)
Where: Vi = 9.0 m1, syringe water volume V3 = 5.0 m1, final sample volume Vd = 0.09 m1, diluter valve volume v2 - 0.50 m1, sample aliquot PFNtCFD FOPMtfLA port Poron concentration = ppm Boron measured x 1,000 3
26 of 30 Rev. 2
EP IV-301 (emisting) o vcas ris ig 20cc HP Flow (easshng) . Syringe geger i U Volve'2 wve#4 X . 7 X > X (eaisting) Volve8 3 (easstang) .
Whitey 4 - Way
- if Bell Volve whooton m 1 16cc Softle "
Fisme Hood
,' J'
~
t ,- .
_~ J'1 ,
55 get Steel 4 9 4 9 Oruni with weste - i Contosners pocked in Sand 5 gol. 5 gol.
Liquid Gos Woste waste FLUID FLOW PATH FIGURE 1 1
Rev. 2 27 of 30 l
EP IV-301
]
. \
O 'wdEATON BOTTIE HOI. DER * '
FIGURE 2 m i 2
E *-
e-
= 8 d.
*$2 o
u=g
.m 3 u 3r.o m /
W C 5>
c5E b$
.c -os e x 3.5 e cp O e o
.J
.5 t
N
.x o
2 m
t C
o 3
__Y Rev. 2 28 of 30
F
':P IV-301 O
Syringe _
~
. +
e + + >+ + + . + , e + + + + . ,,
+ + + + + , + + + + + e
. + + + > + . + + + + , . . , + .
+ + + + + + + + + + . + . + + + +
+ . + . + > + + + + + + , . , + + <
+ + + + + + + + + + + + + + + e * + + ,
- . . . * * . . . + + + + . , , + + , < To
+ + + + + + + . . , , , , . , , + ++++
+ . + + , + + + > + + + + + + , , + + + , < Woste
+ + + + + + + + + + + + + + + + + ++..
+ + + + + + + + > + + + + + . . . + + + + <
+ + + + + + + + + e + , , . . . + +++
Sox with lead shot a+++++++ > + + + + + + + + + + +
e equivalent fo 2"Ieod
+ + + + + +
+ e , + .ya g,,+#*+ >+++,+e + +++ ++ + > . ,
+ + + + +
+ <
+ + . 3 + + * . . . + + + + <
s *4'y' i
.+ MN2+ . ,
+
- VDl'.'4
+ ,
+
+++j
+ + +
+ +
. .. s, , , - . +
+ + + + + +1 , e + + +
. + + + + + + , + + + + +
++++,.. , + + . + + + + .
, , + + + + + + + + + + , ,
... . + < + + ++ + + + +
^
r
/
il s 6-8" 4 d e d -
Volve Reach Hypodermic Y Rods Needle FOUR-WAY VALVE ARRANGEMENT FIGURE 3 1
O l
i
. 29.of 30 Rev. 2
EP IV-301
_ . Vent
.stside isoletsom _tevolve.e, hood (closed) o 7
'* a f
2 -
+,,
/,
p
/
f,
/
/
/
//
/ /
Boa with
/ / leod shot
- - _ _ _ / // syr
.! L.- . _ _- r-L- _ / // U O
f ff
..y /
= --
- p - **
= = = --
- / 7</ +- ; -
/ '
/ /, . . . .
a d 5 gol. bof fle 5 got bottie, for gosas for liquid vented from NOTE: Both bottles must be purged with nitrogen hquod bottle gas to provide mere atmosphere prior to insteNellation.
WASTE CONTAINER FIGURE 4 1
30 of 30 Rev. 2 l
_ . . _ . _ _ _ _ . . _ . . - - - - - - - - -- --- - - - - - - - - - - - - - - -- - - '---- - ~ ~ - -
No. 108 U.S. NRC, Dir. of NRR washington, D.C. 20555 Mr. S.A. Varga, Chief, oper.
9 Reactors BR#1, Div. of Licensing SALEM GENERATING STATION EMERGENCY PLAN EMERGENCY PLAN PROCEDURES INDEX SEPTEMBER 30, 1982 SECTION I - ON-SITE PROCEDURES REV. NO.
EP I-0 Accident Classification Guide . . . . . . . . . . . . . . . . . . . . . . 2 Part 1 Radiological
- Part 2 Operational Part 3 Fire / Natural / Security Part 4 Miscellaneous Flow Chart . . . . . . . ........................ O i EP I Notification of Unusual Event /Significant Event . . . .......... 2 EP I-2 Alert . . . . . . . . . . ........................ 2 EP I-3 Site Area Emergency . . . . . . . . . . . ................ 2 EP I-4 General Emergency . . . . . . . . . . . . . . . . . . .......... 2 EP I-5 Personnel Emergency . . . . . . . . . . . . . . . . . .......... 1 EP I-6 Radioactive Spill . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 EP I-7 Station Fire . . . . . . ........................ 1 EP I-R Personnel Accountability ........................ 1
, FP I-9 Search and Rescue Operations . . . . . . . . . . . . .......... 1 l FP I-10 Conducting an Inventory of Emergency Equipment . . . .......... 1 EP I-11 Communications Equipment ........................ 1 EP I-12 Site Evacuation . . . . . ........................ 1 EP I-13 Post Accident Low Pressure Injection Monitoring . . . .......... 1 EP I-14 Initiation of Recovery Operations . . . . . . . . . . . ......... 1 EP I-15 Stable Iodine Thyroid Blocking . . . . . . . . . . . .......... 1 EP I-16 Rect.11 of Evacuated Site Personnel . . . . . . . . . . ..... ... 1 EP I-17 Radiation Protection - Emergency Action . . . . . . . . . . . . . ... 1 EP I-18 Operations Support Center Activation . . . . . . . . . ......... 1 EP I-19 Activation / Evacuation of the Technical Support Center . ......... 1 SECTION II - OFF-SITE PROCEDURES EP II-l Emergency Response Manager Preparation to Assume Responsibilities . ... 1 EP II-2 Site Support Manager Preparation to Assume Responsibilities . . . . . . . 1 EP II-3 Radiological Support Manager Preparation to Assume Responsibilities . . . 1 EP II-4 Notification of Corporate Emergency Response Personnel ......... 1 EP II-5 Emergency Paging of Corporate Emergency Response Personnel ....... 1 EP II-6 Off-Site Administrative Support . . . . . . . . . . . . ......... 1 EP II-7 Testing of Emergency Procecure EP II-4 . . . . . . . . ......... 0 1 of 3 Rev. 4 l
1
------n-- -e-- - , , - - - ,en--,-, ,- ,.,re-----,- ~- , -,,e, ann..-, e.,,---c,.m,-,----w--r,--r--_,m--- , - . - - , e , .- ----
SECTION III - SECURITY EMERCENCY PROCEDURES REV. NO.
FP III-I Opening of the Technical Support Center . . . . . . . . . . . . . . . . . 0 EP III-2 Opening of the Emergency Operations Facility .............. 0 EP III-3 Personnel Accountability ........................ 0 EP III-4 Site Evacuation - Security Support ................... 0 EP III-5 Emergency Vehicle Support . ....................... O SECTION IV - RADIATION PROTECTION /CNEMISTRY EMERGENCY PRCCEDURES EP IV-101 TSC Initial Response ................. ......... 1 EP IV-102 Control Room Initial Response . ..................... 1 EP IV-103 Control Point Initial Response ..................... 1 EP IV-104 TSC Evacuation .................... ......... 1 EP IV-105 Control Point and Equipment Evacuation ................. 1 EP IV-106 ALARA Task Review and Emergency Exposure Authorisation ......... 1 EP IV-107 Radiation Monitor Evaluation ...................... 1 EP IV-108 Protective Action Recommendations . . . . . . . . . . . . . . . . . . .. 2 l EP IV-109 Plume Tracking by Helicopter ...................... 1 EP IV-110A Fleid Monitoring by TSC ........................ 2 FP IV-110B Field Monitoring by EOF ........................ O
- EP IV-111 Effluent Dose Calculations ....................... 2 EP IV-112 Emergency Operations Facility - Radiological Assessment . ........ 0 EP IV-113 Computerized Dose Calculations ..................... 2 EP IV-114 Computerized Dose Calculations on Programmable Calculator . . . . . . . . O EP IV-115 Personnel and Vehicle Survey ...................... 1 EP IV-116 Fire Brigade Escort . ......................... . 1 EP IV-117 Re-Entry Team Radiation Protection ................... 1 EP IV-118 High Activity SaPple Analysis . . . . . . . . . . . . . . . . . . . . . . 2 EP IV-119 Personnel Decontamination . . . . . . . . . . . . . . . . . . . . . . . . 1 l
l EP IV-120 Equipment Decontamination . . . . . . . . . . . . . . . . . . . . . . . . 1 EP IV-121 Containment Atmosphere Remote Sampling ................. 1 EP IV-122 Emergency Staffing Guide. ........................ 1 EP IV-201 Radiation Protection Fanfor Supervisor Response . . . . . . . . . . . . . 1 EP IV-202 Chemistry Senior Supervisor Response .................. 1 EP IV-203 Administrative Assistant Response . . . . . . . . . . . . . . . . . . . . 1 EP IV-204 Short Tern Environmental Response . . . ................. 1 EP IV-205 Material and Instruments Supervisor Response .............. 1 EP IV-206 Dosimetry-Counting Room Supervisor Response . .............. 1 EP IV-207 Rad Weste Supervisor Response . . .................... 1 EP IV-208 Dose Assessment - ALARA Supervisor Response . . ............. 1 EP IV-209 In-Plant Supervisor Response ...................... 1 EP IV-210 Procedures-Training Supervisor Response . . . . . . . . . . . . . . . . . 1 EP IV-211 Radiation Protection Communications Guide . . . . . . . . . . . . . . . . 1 EP IV-212 Radiation Protection Emergency Inventory Control ............ 1 EP IV-301 Interim Post Accident Primary Coolant Sampling ............. 2 EP IV-302 Emergency Sampling Procedure for the Plant Vent . ............ 1 2 of 3 Rev. 4
m 1
S2CTION V - ENGINEERING DEPAR1HENT EMERGENCY PROCEDURES REV. NO.
EP V-1 Notification of Engineering and Construction Department . ........ O EP V-2 Corporate Engineering Support Manager Response (CHERC) ......... O EP V-3 Site Engineering Support Manager Response (EOF) ............. O FP V-4 Corporate Engineering Team Leader Response (CHERC) ........... O EP V-5 Corporate Ouality Assurance Department Response (CHERC) ......... 0 EP V-A Site Ouality Assurance Department Response (EOF) ............ 0 EP V-7 Site Engineering' Team Leader Response (TSC) ............... 0 EP V-8 Methods Department & Engineering Department Divisional Representatives Response (CHERC) . .. ........................ O SECTION VI - PLAN ADMINISTRATION EP VI-l Revision and Approval of Plans and Procedures . . . . . . . . . . . . . . 1 EP VI-2 Distribution of Plans and Procedures .................. O EP VI-3 Review of Plans and Procedures ..................... 0 EP VI-4 Procedures Format . . . . ........................ O EP VI-5 Conduct of Drills and Exercises . .................... 1
'N SECTION VII - PUBLIC INFORMATION i
EP VII-l Public Information Notification . .................... O FP VII-2 General Manager - Information Services Response . ............ O EP VII-3 Public Information Manager Response . . ................. O EP VII-4 Public Information Technical Liaison Response . ............. 0 EP VII-5 Public Information Technical Assistant Response . ............ O i EP VII-6 Internal Information . . ........................ O t
RP VII-7 Media Relations . . . . ... ...................... 0 EP VII-8 Emergency News Center Activation /Pulbic Information Coordinator Response .. . . . . . ........................ O ADDFNDUM Addendum 1 Master Phone List . . . ........................ 3 Addendum 2 Supplemental Station Status Checklist ................. I 1
1 FIGURES F,iqure 1 EDO Checklist . . . . . ... ...................... 1 l
Figure 2 Communications / EOF Manning Board .................... 1 l
Figure 3 Operational Status Board ........................ O Figure 4 Post Accident RMS Assessment Data . . .................. 1 m
Figure 5 Area / Process RMS Data . . ........................ O Figure 6 Offsite Dose Summary . .. ....................... 0 l
3 of 3 Rev. 4
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ADDENDUM 1 EMERGENCY PROCEDURE ADDENDUM 1 MASTER PITONE LIST EMERGENCY ASSISTANCE AND NOTIFICATION
, INDEX PAGE STATION RESPONSE . . . . . . . . . . .............................. 1 CORPORATE RESPONSE . . . . . . . . . .............................. 6 GOVERNMENTAL RESPONSE PEDERAL . . . . . . . . . . . . . . .............................. 11 STATE OF HEW JERSEY . . . . . . . . .............................. 11 CUMBERLAND COUNTY . . . . . . . . . .............................. 12 SALEM COllNTY . . . . . . . . . . . ............................... 13 LOWPR ALLOWAYS CREEK . . . . . . . .............................. 13 STATE OF DELAWARE . . . . . . . . . .............................. 13 KENT COUNTY . . . . . . . . . . . . .............................. 14 NPW CASTLE COUNTY . . . . . . . . . .............................. 14 STATE OF MARYLAND . . . . . . . . . .............................. 14 STATE OF PENNSYLVANIA . . . . . . . .._............................ 14 MISCELLANEOUS OPPSITE RESPONSE. . . . .............................. 14 j TELEPHONE LIST BY PACILITY . . . . . .........................., .. 17
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Reviewed By: h-EMERGENCY PLANNING ENGINEER 7/ND[6'2-DATE Approved By: y' / f 2.z. f'2.-
MANAGER - NUCLEAR SITE PROTECTION /DATE'
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