ML20210D416
| ML20210D416 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/26/1987 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20210C301 | List: |
| References | |
| PROC-870126-01, NUDOCS 8702100086 | |
| Download: ML20210D416 (168) | |
Text
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, Form 34731 (344) (1) 10 No.HP/0/B/1009/04 DUKE POWER COMPANY Change (s) O to PROCEDURE PROCESS RECORD o lacorporated PREPARATION Catawba (2) STATION (3) PROCEDURE TITLE _ Environmental Monitoring for Emergency Conditions within the Ten Mile Radius of Catawba Nuclear Station (4) PREPARED BY
^ -
DATE MMr ?
C) REVIEWED BY 2C DATE /' 8) A Cross Discipl. nary Review By N/R /JJ C) TEMPORARY APPROVAL (If Necessary)
K By (SRO) Date By Date
- DATE I I (7) APPROVED BY '
r
, C) MISCELLANEOUS I
- Reviewed / Approved By Date Reviewed / Approved By Date COMPLETION C) DATE($1 PERFORMED (10) PROCEDURE COMPLETION VERIFICATION -
O Yes O N/A Check lists and/or blanks properly initiated, signed, dated or filled in N/A or N/R, as appropriate?
O Yes O N/A Listed enclosures attached?
O Yes O N/A Data sheets attsched, completed, dated and signed?
O Yes O.N/A Charts, ysphs, etc. attached and properly dated, identif.ed and marked?
Oyes DN/A Acceptance criteria met?
VERIFIED BY DATE (11) PROCEDURE CDMPLETION APPROVED DATE REMARKS 0702100086 870126 PDR ADOCK 05000413 F PDR
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HP/0/B/1009/04 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ENVIRONMENTAL MONITORING FOR EMERGENCY CONDITIONS WITHIN THE
'ITN MILE RADIUS OF C.*.TAWBA NUCLEAR STATION 1.0 PURPOSE To provide a method for identifying gaseous plumes or 11guld effluent, and obtaining field data indicative of the radiation exposure to the general public following a suspected uncontrolled release of radioactivity. This procedure shall also be implemented by the Crisis Management Center once it is activated.
2.0 REFERENCES
2.1 HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory 2.2 HP/0/B/1002/12 Radiological Environmental Sample Collection 2.3 HP/0/B/1003/05 Operating and Calibration Procedure: Eberline Model PIC-6A Portable Ion Chamber i ' 2.4 HP/0/B/1003/12 Operating and Calibration Procedure: Eberline Model .
E-520 Portable Beta-Gamma Geiger Counter 2.5 HP/0/B/1003/17 Operation and Calibration Procedure: Canberra Series - 10 Portable MCA 2.6 HP/0/B/1003/31 Operation and Calibration: Eberline Model E140N Portable Count Rate Meter 2.7 HP/0/B/1009/16 Distribution of Potassius Iodide Tablets in the Event of a Radiciodine Release 2.8 HP/0/B/1009/19 Emergency Radio System Operations, Maintenance and Communications 3.0 LIMITS AND PREC4LTTIONS 4
3.1 The Field Monitoring Teams (FNT) should park vehicles completely off the road when sampling and use vehicle emergency flashers while stopped.
3.2 Five (5) FNrs and one (1) helicopter team (if necessan) shall be formed as follows: '
Team Call Sians Number of Members Transportation
( ,- Alpha 2 Land Vehicle Bravo 2 Land Vehicle Charlie 2 Land Vehicle Delta 2 Land Vehicle Echo 1 Helicopter Foxtrot 2 (Onsite Team)
_ _ . m . .____m- * - - - - -
_ _ _. ~ . .. . _ - -
1 HP/0/B/1009/04-
-] Page 2 of 7 3.3 Each Flff shall use particulate masks and protective clothing whenever activity justifies it or when directed by the Field Monitoring Coordinator (FMC).
3.4 If the team members are expected to be exposed to I-131 in excess of 70 MPC (6.1 x 10' DCi/ml), and directed by the FMC, each team member should ingest a tablet of potassium iodide per Reference 2.7.
3.5 Environmental sampling during emergency conditions shall not replace, but rather supplement normal environmental monitoring.
3.6 Minimum labeling requirements for all samples are as follows:
3.6.1 Date and time.
3.6.2 Location.
3.6.3 Volume of the sample (if applicable).
3.6.4 Name of person sampling.
t 3.7 Each FMT shall maintain open radio communications with the FMC per Reference 2.8. If a radio become,s inoperable telephone the following:
3.7.1 FMC in the TSC at 831-8182 (Lake Wylie/ Charlotte).
1 3.7.2 Station PBX Operator at 831-2282 (Lake Wylie/ Charlotte)..
861-0331 (Gaston County), 324-3128 (Rock Hill / Fort Mill),
and request ext. 2598 for FMC.
3.8 If any equipment becomes inoperable, notify the FMC and wait for further instructions.
3.9 Annual training in the use of this procedure and the associated equip-ment and instrumentation shall be conducted and documented on TSR-10.
3.10 Portable MCA's shall be picked up at the Health Physics Counting Room when directed by the FMC or Reserve Personnel / Personnel Monitoring (RPPM)
- Leader. Ensure that the dewars are adequately filled per Reference
! 2.5.
i 3.11 Ensure that portable survey instrumentation is on and monitored during transport to s11 sampling locations.
3.12 When returning kits to the Emergency Kit Storage Room, perform an equipment inventory check using the Environmental Survey Kit Checklist (Reference 2.1). Note deviations and forward to the Respiratory / Instrument Calibration Supervisor.
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HP/0/B/1009/04 Page 3 of 7 4.0 PROCEDURE 4.1 Activation 4
4.1.1 Upon notification and assembly FMT Foxtrot will obtain a portable radio, a site map and portable survey instruments from the HP Instrument Issue Area.
- 4. 1.1.1 Team Foxtrot will then be dispatched, as per the FMC, up to the security area' boundary fence at the estimated plume location.
4.1.2 The remaining FPff members shall:
4.1.2.1 Pick up portable MCA and check for proper operation (Reference 5.6.1 of Enclosure 5.7).
4.1.2.2 Report to the Emergency Kit Storage Room in the Temporary Administration Building to get Environmental Survey Kits.
4.1.2.3 Ensure the tamper seal on the Environmental l
Survey kits have not been broken and inventory any that have (Reference 2.1).
W 4.1.2.4 Immediately place batteries in the portable survey instruments and make a communication i
check with FMC, using the portable FM radios and the radio in the vans.
4.1.2.4.1 Perform a battery check and survey the area for higher than background radiation levels.
4.1.2.4.2 Report any above background radiation levels to the FMC. As i
advised by the FMC, move to = low background area to complete source checks.
4.1.2.5 Source check survey instruments (References i
2.3, 2.4, 2.6) if applicable.
4.1.2.5.1 Turn the E140N Count Rate Meter on and continuously monitor the audible signal while locating and tracking the plume.
4.1.2.6 Don TLD, high and low range dosimetry, and fill
- out dose cards.
! -Q 4.1.2.7 Ensure the Portable Power Generator is operational and the gas can is fully fueled I (Reference 2.1).
_ _ - - _ _ _ _ _ , _ . _ _ _ - - _ _ _ - _ _ . . _ _ _ _ _ _ _ _ , - _ .2 _. .. _ _ _ _ _ __--_- _ .-_.._. _-.___
-. . . . . - .. .. -- . _- . - ~ .
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" HP/0/B/1009/04 Page 4 of 7 s .
4.1.2.8 Obtain emergency vehicles as directed in Enclosure 5.9.
. 4.1.2.9 Each FNT will be dispatched as per the FMC.
'4.1.2.10 The radio operator in the TSC shall complete -
Radio Operators Los Field Monitoring Data Sheet (Enclosure 5.4), with the appropriate information.
4.2 Locating and Tracking the Plume .
4.2.1 At the assigned survey point, the FNT shall perform a general area Beta-Gamma survey. This method should be used to locate center and width of plume.
4.2.1.1 Record date, time, location and dose rate (ar/hr) on the Field Monitoring Data Sheet (Enclosure 5.5).
l 4.2.2 If survey results are less than or equal to expected background, call in the results to the FMC and wait for further instructions.
- u. j 4.2.3 If survey results are greater than background, take protective actions as necessary. Then, if directed, take 8
l an air sample (volume should be > 10 al) equipped with a Silver Zeolite Cartridge and particulate filter.
4.2.3.1 Insert cartridge with arrow pointing in.
4.2.3.2 Insert filter paper with smooth side facing out.
4.2.3.3 Calculate required sample time per Enclosure 5.6.
4.2.3.4 Place the electrical generator (gas powered or mounted generator in the vans) in service and start the air sampler ensuring the sampler is approximately two feet above the ground or higher.
4.2.3.4.1 Gas power generators should be kept i
from wet areas and handle with electrical gloves eontained in the j environmental monitoring kit.
i 4.2.3.4.2 Mounted electrical generation located in the emergency vans j should be operated as follows to
, . ,/ 4.2.3.4.2.1 Ensure the engine I of the van is running i
l-before energizing the generator.
l
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.4 3, RP/0/B/1009/04
<\ Page 5 of 7 4.2.3.4.2.2 Ensure the engine is running continuously if the generator is being used.
4.2.3.4.3 Ensura all sampling equipment is off the roadway for safety reaseas.
4.2.3.5 When air sampling is' complete, place the Silver Zeolite Cartridge in a thin plastic bag
- (baggio) for analysis. For transporting or
- storage place this into a labeled " zip-lock"
, bag.
4.2.3.6 Place filter in a separate poly bag and label.
4.2.3.7 As directed by the FMC, transport the completed sample to a vehicle that is carrying a Canberra Series - 10 Portable NCA for analysis per Reference 2.5.
4.2.3.8 Ensure the correct information is annotated on
, m, the Field Monitoring Team Work Sheet for v)
Determining Iodine Activity (Enclosure 5.7). .
4 4.2.3.9 Wait for further instructions from the FMC.
, 4.3 Special Sampling, as directed:
4.3.1 When sampling away from the emergency vehicles and no one is present to monitor the radio do the following:
! 4.3.1.1 For the emergency vans, ensure the exterior '
speaker is on and volume turned up. Switch '
located near the radio monitor on the right side of the' drivers seat.
4.3.1.2 For other Station vehicle or personnel I
vehicles, carry the portamoble radio to the sampling location.
4.3.2 All sampling immediately outside of the Auxiliary, Service and Turbine Buildings should be done by reas Foxtrot.
{ 4.3.3 Take smears aad place them in separate poly bags, label and i
retain for later analysis.
4.3.4 ' Count smears on E140N and record on Field Monitoring Data i
Sheet (Enclosure 5.5). Call in results to FMC.
I s., 4.3.5 Collect water sample (s) as per Reference 2.2 and retain for later analysis.
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- i. HP/0/B/1009/04
<g Page 6 of 7 4.3.6 Place TLD's in the savironment as pcr Reference 2.2.
4 4.3.7 Retrieve and replace air sample (s) and/or TLD's that are already located in the environment as per Reference 2.2.
Locatiets are listed in Enclosure 5.1. Retain sample (s)
~
- for later analysis.
4.3.8 Collect broad leaf vegetation sample (s) as per Reference 2.2 and retain for later analysis.
NOTE: Leaves in the shape of needles, i.e. pine or spruce needles, are not considered to be broad 4
leaf vegetation. ~
4.3.9 Collect shoreline sediment sample (s) as per Reference 2.2 and retain for later analysis.
4.3.10 Collect milk sample (s) as per Reference 2.2 and retain for later analysis. Locations are listed in Sample
- Enclosure 5.2.
4.4 Contamination Control Considerations 4.4.1 Don Anti-Cs inside the vehicle before leaving the
! . '.% vehicle.
i \ ;2 4.4.2 Paper Anti-Cs should be used over cloth Anti-Cs and l discarded before re-entering the vehicle.
4.4.3 Once a release has occurred, vehicle windows should be closed with ventilation off (unless flitration or rec'irculation is available on the ventilation) to minimise
! contamination until the plume area is identified. '
Depending on weather conditions (extrees heat or cold),
this may not be possible. .
4.5 Turnover j 4.5.1 Each FNT shall be relieved as directed by the FHC.
4.5.2 Infore the relief FNT on the status of the following:
. 4.5.2.1 Radiation surveys and dose rates in the plume area.
4.5.2.2 Kit Inventory consumed.
W l
4.5.2.3 Equipment operating status.
- 4.5.2.4 Any sampling problems.
! s 4.5.2.5 Plant status information.
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^ HP/0/3/1009/04 s Page 7 of 7 4.5.5 Direct the relief FMT to don TLD's and pocket dosimetry and fill out dose cards.
4.5.4 Return all samples to the Emergency Kit Storage Room as directed by the FMC.
4.5.5 Turn in all data sheets to the FMC or his designee.
5.0 ENCLOSURF.S 5.1 Air Sampler, TLD, and Water Sample Incations 5.2 Milk Sample Locations 5.3 Predetermined Sampling Incations 5.4 Sample of Radio Operators Los Field Monitoring Survey Data 5.5 Sample of Field Monitoring Data Sheet 5.6 Sample Time Required For Minimum Sample Volume
,...., 5.7 Sample of Field Monitoring Team Work Sheet For Determining, Iodine
- Activity .
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5.4 TSC Field Monitoring Organisation 5.9 Emergency. Vehicles e
l Page 1 of 9
" ' DUKE POWER COMPANY .
CATAWBA NUCLEAR STATION NP/0/3/1009/04 '
ENCIDSURE 5.1 ~
AIR SAMPLER, TLD, AND WATER SAMPLE I4 CATIONS AIR SAMPLE I4 CATIONS (NEED KEY, CPD-1) 20lg & RADIUS (NL) h DESCRIPTION A0 1 1 Hwy. 274-N for .5 alles. -right on Liberty Hill Rd. for .4 miles to fork in road, right at fork for 1.1 miles to end of road (TLD &
Air CNS #200, need key).
A0 i 5 Left exiting steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Myrtle Rd.
for .7 miles, left on Blue Bird La. for .1 miles to end (TLD & Air CN8 #201, need key).
(l
A0 ,1 26 Location at the base of Catawba Nuclear Station Meterological Tower (TLD & Air CNS #205, need key). ,
31 3 1 Nwy. 49-N for a miles, right Nwy. 160 for i 2.4 miles, right on Gold Hill Rd. (98) at Tega Cay sign for 1.2 miles, right on gravel i
road into Duke Power Company substation (TLD
& Air CNS #212, need key).
1 j
C2 10 5 Nwy. 274-8 for 5.1 sites left Nwy.161 for
.1.3 miles, right on Rawlinson Rd. (56) for j
1.8 miles, left on Hwy. 5 for 1.6 miles,
! right on Neckle Blvd. (901) for 3.3 miles !
l to end of road, left on Hey. 72 for 1.2 miles right on dirt road across fras
- Wayne,s Auto Service. Go .1 miles to Duke Power Company substation on left (TLD & Air CNS #217 need key).
l A0 1 1 Nwy. 274 N for .5 miles, right. on Liberty N111 Rd. for .4 miles to fork in road, right
( ,-
at fork for 1.1 miles to end of road (TLD &
l' Air CNS #200, need key). i
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o I' .
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-N DUKE POWER COMPANY
, CATAWBA NUCLEAR STATION .
HP/0/t/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPIX. LOCATIONS AIR SAMPLE LOCATIONS (NEED REY, CPD-1)
Zgg & RADIUS (M1) Np DESCRIPTION A0 1 5 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Myrtle Rd.
for .7 miles, left on Blue Bird La. for .1 miles to end (TLD & Air CNS #201, need' key).
A0 1 S Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Myrtle Rd.
^
Go .3 miles to first drive on ri Sht past s Paradise Pl., TLD across road (TLD CNS s c') #202).
A0 1 11 Left exiting Steam Production entrance on Concord Rd., for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Myrtle Rd.
for .2 miles. TLD is on left in curve (TLD CNS #223).
A0 1 14 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .2 miles. TLD is on right side of road (TLD CNS #224).
A0 1 17 Left exitinS Steam Production entrance on Concord Rd. for 1.1 miles to first transmission tower on left after trid Se (TLD CNS #225).
A0 1 20 Left exiting Steam Production entrance on
', Concord Rd. for .7 miles. TLD on left just past fence (TLD CNS #226).
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Page 3 of 9
l DUKE POWER COMPANY
< l CATAWBA NUCLEAR STATION '
HP/0/B/1009/04 {
ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS AIR SAMPLE LOCATIONS (NEED KEY, CPD-1) s ZONE & RADIUS (Mi) No DESCRIPTION '
s A0 1 23 Left exiting Steam Production entrance on s Concord Rd. for .4 miles. TLD on left at - '
beginning of guardrail posts (TLD CNS #204). s A1 4 2 Hwy. 49-N for 6.5 miles to the intersection -
of Pleasant Hill Rd. (1109). TLD is on the transmission tower on left (TLD CNS #232).
A1 4 4 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for .6 miles, left on
./
Zoar Rd. (1105) for .4 miles, right on Thomas Rd. (1104) for .1 miles. TLD is behind second house on.
B1 '3 1 Hwy. 49-N for 8 miles, right on Hwy. 160 for 2.8 miles, right on Gold Hill Rd. (98) at Tasa Cay sign for 1.2 miles, right on -
gravel road into Duke Power Company substation (TLD & Air CNS #212, need key).
B1 4 3 Hwy. 49-N for 8 miles, right on Hwy. 160 for 3.9 miles, right on Das Rd. (99) for 1.9 miles to last gravel road on right in sharp curve before Lake Wylie Dam, left l through fence for .2 miles to substation, TLD on right of inner substation fence (TLD CNS #235).
52 4 2 Hwy. 49-N for 8 miles, right on Hwy. 160 for 2.8 miles to the Home Federal Savings and Loan on left side of road. TLD on barbed wire fence approximately 50 yds.
)
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s DUKE POWER COMPANY CATAWBA NUCLEAR STATION 2 HP/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS
, AIR SAMPLE LOCATIONS (NEED KEY, CPD-1)
~
ZONE & RADIUS (Mi) No. DESCRIPTION
~\ B2- 7 6 Hwy. 49-N for 8 miles, right on Hwy, 160
. for 7.1 miles, right on Lee St. for .1
- miles, left on Self St. for approximately 100 yds. TLD at Fort Mill Municipal Water Supply on right behind Springs Mill (TLD CNS #247, Water CNS #213).
f B2 8 1 Hwy. 49-N for 10 miles, right on Carowinds Blvd. (1441) for 1.3 miles, left on Choate Circle for .3 miles, TLD is on the inside of fence left of the guardhouse (TLD CNS
- 246).
r A0 . 1 26 Location at the base of Catawba Nuclear Station Meterological Tower (TLD & Air CNS
- 205, need key).
A0 1 29 Left exiting Steam Production entrance on
, Concord Rd. for .1 miles. TLD at Shady Shor,e Dr. on right corner of.
~
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A0 1 32 Right exiting Steam Production entrance on Concord Rd. for .1 miles. TLD is on right
' side of entrance to Valelake Rd. (TLD CNS
- 228).
i A0 1 35 Right exiting Steam Production entrance on i .
Concord Rd. for .4 miles. TLD on top of
. hill on right at the intersection of
'~/. ~
Catawba Nuclear Station Construction
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~ Page 5 of 9 DUKE POWER COMPANY -
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIDSURE 5.1 AIR SAMPLER, TLD, AND' WATER SAMPLE LOCATIONS AIR SAMPLE LOCATIONS (NEED KEY, CPD-1)
ZONE & RADIUS (MI) No. DESCRIPTION A0 1 38 Go through Construction Ifaintenance Dept.
(Central) Main Gate for approx. 50 ft. ,
left on Alternate 1 for approx. 200 ft, to stop sign, left on gravel road for .1 miles, left into rebar yard for .7 miles on gravel road to end at chain link fence. ,
Follow chain link fence in a northerly '
direction for approx. 300 yds. TLD is hanging on fence (TLD CNS #229).
A0 1 41 Hwy. 274-N for .5 miles, rigl
- on Liberty
,- Hill Rd. for .4 miles to fork in road, Qf right at fork for .4 miles. TLD on fence on right (TLD CNS #207).
A0 1 44 Hwy. 274-N for .5 miles, right on Liberty Hill Rd. for .4 miles to fork in road, 3 '
right at fork for 1 mile to large rock pile at fence. TLD is on fence (TLD CNS #222).
A0 1 45 Left exiting Steam Production entrence ca Concord Rd. for 1.2 miles, left on Old Concord Rd. for 1.4 miles to end of road.
TIa is on fence on the left side (TLD CNS
- 203).
C1 4 1 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 5.2 miles, left on India Hook Rd. (30) for .9 miles to the S.C. Wildlife Resources Dept. on left (TLD CNS #236).
C1 4 3 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 3 miles, right on w-Homestead Rd. (657) for 2.5 miles to end of road. TLD is straight across at intersection of Twin Lakes Rd. (TLD CNS
- 237).
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.% Page 6 of 9
' DUKE POWER COMPANY .
CATAWBA NUCLEAR STATION HP/0/B/1009/04
, ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE IOC EIONS AIR SAMPLE LOCATIONS (NEED KEY, CPD-1) l ZONE & RADIUS (Mi) 'No. DESCRIPTION C1 4 5 Hwy. 274-5 for 3.8 alles,- left on Mt.
Gallant Rd. (195) for 1.3 miles, right on West Oak Dr. (962) for 1.2 miles to end at fork. TLD on left at fence. (TLD CNS #238).
C2 7 3 Hwy. 274-S for 9.2 miles, right on Herlong Ave for .3 miles to Piedmont Medical Center emergency entrance to back of hospital. TLD on fence at back right corner of Liquid Oxygen storage area (TLD CNS #248).
,. s D C2 8 6 Hwy. 274-5 for 5.1 miles, left on Hwy.161 for 1.3 miles, right on Rawlinson Rd. (56) for 1.8 miles, left on Hwy. 5 for .5 miles to Rock Hill Career Development Center on l' right. TLD on transmission tower in front of building (TLD CNS #249).
C2 10 5 Hwy. 274-5 for 5.1 miles, left on Hwy.161 for 1.3 miles, right on Rawlinson Rd. (56) for 1.8 miles, left on Hwy. 5 for 1.6 miles, right on Heckle Blvd. (901) for 3.3 l
I alles to end of road, left on Hwy. 72 for 1.2 miles, right on dirt road across from Wayne's Auto Service. Go .1 miles to Duke Pcwor Company substation on left (TLD & Air CNS #217, need key).
D1 4 2 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 2.3 miles, left on.
D1 5 1 Hwy. 274-S for 5 miles to Carter Lumber Co. TLD on fence near gate (TLD CNS #239).
F
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i
. Page 7 of 9 DUKE POWER COMPANY -
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ;
ENCLOSURE 5.1 '
AIR SAMPLER, TLD, AND WATER SAMPLE I4 CATIONS AIR SAMPLE LOCATIONS (NEED XEY, CPD-1)
ZONE & RADIUS (Mi) & DESCRIPTION D1 5 4 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 3 alles. TLD on left at beginning of fence (TLD CNS #241).
D2 10 4 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 3.4 miles, left on Hwy. 49-5
. for 5.2 miles, left on North Congress St.
(64) for .7 miles, left on Hwy. 5 for .2 miles to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #250).
El' 5 2 Hwy. 49-S for 3 miles, right on Parsham Rd.
(54) for .7 miles to transmission tower on left after bridge (TID CNS #242).
El 5 3 Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 2.3 ziles, left on Kingsburry Rd. (114) for .4 miles to transmission tower on left (TLD CNS #243).
E2 10 2 Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 7.4 miles to Duke Power Company Appliance Center on left. TLD on fence in back of building (TLD CNS #251).
F1 4 1 Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 1.5 miles to Bethel School. TLD on side of small building in back (TLD CNS
- 244).
F1 4 3 Hwy. 274-N for 3.4 miles, left on Glenvista Rd. to Crowders Creek boat landing. TLD to east of parking lot (TLD CNS #245).
i
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Page 8 of 9 a
')
DUKE POWER COMPANf .
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCI4SURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS AIR S4MPLE LOCATIONS (NEED KEY, CPD-1) ,
i ZONE & RADIUS (Mi) & DESCRIPTION F1 4 4 Hwy. 274-N for 3.1 miles-to River Hills
' Plantation rear entrance at Hamilton's Ferry Rd. TLD behind green building on right corner (TLD CNS #230).
}
i F1 4 6 Hwy. 49-N for 4.1 miles to River Hills Plantation entrance guardhouse (TLD CNS
- 231).
l A0 1 46 Left exiting Steam Production entrance on m, Concord Rd. for .7 miles. Turn left just
,,.j -'
after canal bridge. Go to pier (Water CNS
- 208, need key). ,
l A1 4 6 Huy. 49-N for 5.6 miles, left at Camp Steere sign after crossing Buster Boyd Bridge for .7 miles to end of road (Water CNS #215).
B1 4 5 Hwy. 49-N for 8 miles, right on Hwy. 160 for.3.9 miles, right on Das Rd. (99) for 1.6 miles, left on Gray Rock Rd. (251) for
.7 miles to Lake Wylie Dam. Walk through plant to upstream side of the das (Water l CNS,#211).
- - B1 4 6 Hwy. 49-N for 8 miles,.right on Hwy. 160 for 3.9 miles, right on Das Rd. (99) for 1.6 miles, left o'n Gray Rock Rd. (251) for
.7 miles to Lake Wylie Dam. Go to river access on downstream side of dam.
L i
l B2 7 6 Hwy. 49-N for 8 miles, right on Hwy. 160 for 7.1 miles, right on Lee St. for .1 L. . miles, left on Self St. for approximately 100 yds. TLD at Fcrt Mill Municipal Water Supply on right behind Springs Mill (TLD
~
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Page 9 of 9 DUKE POWER COMPANY- ,
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS AIR SAMPLE LOCATIONS (NEED KEY, CPD-1)
ZONE & RADIUS Qiji NA DESCRIPTION C2 7 2 Hwy. 274-S for 3.8 miles left on Mt.
Gallant Rd. (195) for 8.5 miles to the intersection of Cherry Rd. Go to Rock Hill Hunicipal Water Supply across intersection on left (Water CNS #214).
C2 7 8 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 7.6 miles, left on Hwy. 161 for 1.1 miles, left on Hwy. 21 for
.4 miles, left on Grier McGuire Rd. for .5 miles to end of road.
O F3 14 4 Hwy. 274-N for 5 miles, right on Pole Branch Rd. (279) for 2.8 miles, right on Hwy. 273 for 7.2 alles into Belmont, right on Catawba St. for .6 miles, left at next light for .2 miles to Belmont Municipal Water Supply (Water CNS #218).
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Page 1 of 1 DUKE POWER COMPANY -
CATAWBA NUCLEAK STATION HP/0/B/1009/04 ENCLOSURE 5.2 MILK SAMPLE I4 CATIONS
- ONE fa RADIUS (Mi) MILK DESCRIPTION D1 6 M Hwy. 274-5 for 5.1 miles, right on Hwy.161 far 2.1 miles, left on Rd.1080 for .5 miles to Pursley Dairy.
D2 8 M Hwy. 274-S for 5.1 miles, right on Hwy.161 for 4.7 miles, left at Scise Dairy and Equipment Co. (CASE sign).
E2 6 M Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 3.3 miles, left va Clinton Dairy Rd. to end of road.
F1 3 M Hwy. 274-N for 2.2 miles, right on Lake Wylie Rd. (1099) for .1 miles to first house on left (Ingram Richmond residence).
F2 7 M Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 3 miles, right on Paraham Rd. (54) for N) 1.5 miles,.left on h 7. 557 for 1 mile.
Barnett Dairy on left.
D1 7 M Hwy. 274-S for 5.1 alles, left on Hwy.161 for .1 miles, right on Adnah Church Rd.
(81) for 1.4 miles. Woods Dairy is on the left.
F2 13 M Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 9.5 miles through Clover, S.C., right on Lloyd White Rd. (148) for 2.3 miles ,
left on Crowders Creek Rd. (1103) for 1.3 miles, right on Sparrow Springs Rd. (1125) for .5 miles. Oates Dairy is on the left.
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,_ _ . . + , ~- '
- 8
Page 1 of 13
-s DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (Mi) No. DESCRIPTION A0 1 1 Hwy. 274-N for .5 miles, right on Liberty Hill Rd. for .4 miles to fork in road,
, right at fork for 1.1 miles to end of road (TLD & Air CNS # 200, need key).
A0 1 2 Hwy. 274-N for 2.2 miles, right on Lake Wylie Rd. (1099) for 2.2 miles to fork in road, right at fork onto Commodore Pl. for
.2 miles, left on Tioga Rd. for .3 miles to and of road.
A0 2 3 Hwy. 274-N for 2.2 miles, right on Lake Wylie Rd. (1099) for 2.2 miles to fork in road where pavement ends.
A0 2 4 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on
~,
Youngblood Rd. (1102) for 3 miles to fork
( ,
in road, left at fork for .6 miles to and k-at Catawba Yacht Club.
A0 1 5 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Hyrtle Rd.
for .7 miles, left on Blue Bird Ln. for .1 miles to end (TLD & Air CNS #201, need key).
A0 1 6 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for 2.8 miles, left on Snug Harbor Rd. (1357) for .5 miles, right on Kalabash Rd. for .3 miles, right on Cozy Cove Rd. (1434) for .5 miles to end.
A0 2 7 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for 2.8 miles to the intersection of Snus Harbor Rd. (1357).
A0 1 8 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Myrtle Rd.
s Go .3 miles to first drive on right past
'~' Paradise Pl., TLD across road (TLD CNS
- 202).
A0 1 9 Hwy, 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles.
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Page 2 of 13 f- ~ s -
i DUKE POWER COMPANY % , ,
CATAWBA NUCLEAR STATION ~ !
HP/0/B/1009/04 i ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (Mi) No. DESCRIPTION right on Youngblood Rd. (1102) for 2.a miles, left on Snug Harbor Rd. (1357) for 1.3 miles to and of road.
A0 2 10 Hwy. 49-N for 6.5 miles, right on Pleasant' Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for 2.8 miles, left on Snug Harbor Rd. (1357) for 1.3 miles, left on Crosshavens Dr. for .3 miles to end of road.
A0 1 11 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .3 miles, left on Crepe Myrtle Rd.
for .2 miles. TLD is on left in curve (TLD CNS #223).
, A0 1 12 Nwy, 49-N for 6.5 miles, right on Pleasant s_ '
Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for 1.6 miles, left-on McKee Rd. (1100) for 1.2 miles, right on Bankhead Rd. for 1.2 miles to end of road.
A0 2 13 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for 1.6 miles, left on McKee Rd. (1100) for 1.2 miles, right on Bankhead Rd. for .4 miles to the intersection of Bessbrook Rd.
A0 1 14 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for .3 miles, right on Acacia Rd. for .2 miles. TLD is on right side of road (TLD CNS #224).
3 A0 1 15 Left exiting Steam Production entrance on Concord Rd. for 1.3 miles, left on Kingfisher Dr. for 1.8 miles to Commodore j' Yacht Club.
A0 1 16 Left exiting Steam Production entrance on Concord Rd. for 1.3 miles where pavement ands.
~'
A0 1 17 Left exiting Steam Production entrance on Concord Rd. for 1.1 miles to first transmission tower on left after bridge (TLD CNS #225).
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Page 3 of 13 DUKE POWER COMPANY CATAWBA NUCLEAR STATION KP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (Mi) No DESCRIPTION A0 1 18 Left exiting Steam Production entrance on Concord Rd. for 1.7 miles, right on 4
Sandlapper Rd. for .2 miles. Stop at e transmission tower.
A0 2 19 Hwy. 274-0 for 1.6 miles,_left on Allison Creek Rd. (1081) for 3 miles to end of pavement.
A0 1 20 Left exiting Steam Production entrance on
~
Concord Rd. for .7 miles. TLD on left just past fence (TLD CNS #226).
A0 1 21 Hwy. 274-S for 1.6 miles, left on Allison Creek Rd. (1081) for 1.7 miles, left on Spratt Rd. to end. (Beware of dogs).
A0 2 22 Hwy. 274-S for 1.6 miles, left on Allison Creek Rd. (1081) for 1.6 miles to 4._ .
intersection of Bardale Rd.
A0 1 23 Left exiting Steam Production entrance on
' Concord Rd. for .4 miles. TLD on left at beginning of guardrail posts (TLD CNS #204).
A0 1 24 Hwy. 274-5 for 1.6 alles, left on Allison Creek Rd. (1081) for 1.7 miles, left'at Spratt Rd. for .1 miles, left on Morrison Rd., right at first 2 forks then left at i next fork to and for a total of .5 miles.
- A0 2 25 Hwy. 274-S for 1.6 miles, left on Allison i
Creek Rd. (1081) for 1.7 miles to intersection of Spratt Rd.
A0 1 26 Location at the base of Catawba Nuclear Station Meterological Tower (TLD & Air CNS
- 205, need key).
A0 1 27 Right exiting Steam Production entrance on Concord Rd. for .1 miles, left on Valelake Rd. for .1 miles to fork in road, left at i fork for .5 miles to end of road.
A0 2 28 Hwy. 274-S for 1.6 miles, left on Allison
~~ Creek Rd. (1081) for 1 mile to intersection of Colina Rd.
Page 4 of 15 l i
DUKE POWER COMPANY !
CATAWBA NUCLEAR STATION '
HP/0/B/1009/04 j ENCLOSURE 5.3 I PREDETERMINED SAMPLING IDCATIONS ZONE & RADIUS (Mi) h DESCRIM* ION A0 1 -29 Left exiting Steam Production entrance on Concord Rd. for .1 miles. TLD at Shady Shore Dr. on right corner of Bethel Community Clubhouse sign (TLD CNS #227).
A0 1 30 Right exiting Steam Production entrance on Concord Rd. for .1 miles, left on Valelske Rd. for .1 miles to fork in road, right at fork for .5 miles to and of road.
A0 2 31 Hwy. 274-S for 1.2 miles to the intersection of Campbell Rd. (80).
A0 1 32 Right exiting Steam Production entrance on Concord Rd. for .1 miles. TLD is on right side of entrance to Valelake Rd. (TLD CNS i #228).
- A0 1 33 Right exiting Steam Production entrance on
'/ Concord Rd. for 1 mile, left on Pine Point Dr. for .5 miles.
. A0 2 34 Hwy. 274-S for .7 miles to Big Allison Creek Bridge.
A0 1 35 Right exiting Steam Production entrance on Concord Rd. for .4 miles. TLD on top of hill on right at the intersection of Catsuba Nuclear Station Construction
A0 1 36 Right exiting Steam Production entrance on Concord Rd. for .9 miles. Stop at entrance to transmission lines.
A0 2 37 Hwy. 274-N for .5 miles, right on Liberty l
Hill Rd. for .3 miles, left on Fremont Rd.
for .2 miles to end of road.
A0 1 38 Go through Construction Maintenance Dept.
l (Central) Main Gate for approximately 50 l ft., left on Alternate 1 for approximately 200 ft. to stop sign, left on gravel road for .1 miles, left into rebar yard for .7 s
miles on gravel road to end at chain link
' g" ', fence. Follow chain link fence in a northerly direction for approximately 300 yards. TLD is hanging on fence (TLD CNS
- 229).
[ .
Page 5 of 13
( DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (MI) No. DESCRIPTION A0 1 39 Hwy. 274-N for .5 miles, right on Liberty Hill Rd. for .4 miles to fork in road, right at fork for .3 miles to third transmission tower on right.
A0 2 40 Right exiting Steam Produ,ction entrance on Concord Rd. for 1.3 miles, right on Hwy.
274-N for 1 mile.
A0 41 1
Hwy. 274-N for .5 siles, right on Liberty Fill Rd. for .4 miles to fork in road, right at fork for .4 miles. TLD on fence on right (TLD CNS #207).
A0 1 42 Hwy. 274-N for .5 miles, right on Liberty Hill Rd. for .4 miles to fork in road, right at fork for .8 miles to softball field entrance.
A0 2 43 Hwy. 274-N'for 2.2 miles, right on Lake Wylie Rd. (1099) for 1.9 miles, right on Beaver Creek Trail for .3 miles to and of l road. -
A0 1 44 Hwy. 274-N for .5 miles, right on Liberty Hill Rd. for .4 miles to fork in road, right at fork for 1 mile to large rock pile at fence. TLD is on fence (TLD CNS #222).
A0 1 45 Left exiting Steam Production entrance on Concord Rd. for 1.2 miles, left on Old Concord Rd. for 1.4 miles to end of road.
TLD'is on fence on the left side (TLD CNS
- 203).
A0 1 46 Left exiting Steam Production entrance on Concord Rd. for .7 miles. Turn left just after canal bridge. Go to pier (Water CNS
- 208, need key).
Al 3 1 Hwy. 49-N for 4.8 miles to the N.C. side of Buster Boyd Bridge.
, A1 4 2 Hwy. 49-N for 6.5 miles to the intersection
( j of Pleasant Hill Rd. (1109). TLD is on the l
L transmission tower on left (TLD CNS #232).
7 ~ e e ' + ,,
.s Page 6 of 13 I ') - '
DUKE POWER COMPANY ,
CATAWBA NUCLEAR STATION '
HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (MI) No. DESCRIPTION A1 5 3 Hwy. 49-N for 7.8 miles to Steele Creek Volunteer Fire Department on right.
A1 4 "4 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd.'(1109) for .5 miles, right on Youngblood Rd. (1102) fot .6 miles, left on Zoar Rd. (1105) for .4 miles, right on Thomas Rd. (1104) for .1 miles. TLD is behind second house on right in pines (TLD CNS #233).
A1 5 5 Hwy, 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for .3 miles, left on Hamilton Rd. (1106) for .7 miles to the intersection of Hwy.160.
A1 4 6 Hwy. 49-N for 5.6 miles, left at Camp
/m' Steere sign after crossing Buster Boyd V;
Brids.e for .7 miles to end of road (Water CNS #215).
A2 10 1 Hwy. 49-N for 11.4 miles to Westinghouse Blvd. Go 1 mile past Westinghouse Blvd. to Roberts' Systems 8500 on left.
A3 10 1 Hwy. 49-N for 10 miles, right on Carowinds Blvd. (1441) for 3 miles, left on Hwy. 51 for 2.1 miles to Sugar Creek Bridge.
B1 3 1 Hwy. 49-N for 8 miles, right on Hwy. 160 for 2.8 miles, right on Gold Hill Rd. (98) at Tega Cay sign for 1.2 miles, right on gravel road into Duke Power Company substation (TLD & Air CNS #212, need key).
B1 2 2 Hwy. 49-N for 6.5 miles, right on Pleasant Hill Rd. (1109) for .5 miles, right on Youngblood Rd. (1102) for 1.6 miles, left on McKee Rd. (1100) for 1.2 miles, left on
^ Bankhead Rd. for .4 miles, left on j T Bessbrook Rd. for .8 miles to end of road.
Aj
+
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'Page 7 of 13 V- DUKE POWER COMPANY ,
CATAWBA NUCLEAR STATION HP/0/B/1009/04 i ENCLOSURE 5.3 1 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (Mi) h DESCRIPTION i
B1 4 3 Hwy. 49-N for 8 miles, right on Hwy. 160 for 3.9 miles, right on Das Rd. (99) for 1.9 miles to last gravel road on right in sharp curve before Lake Wylie Dam, left through fence for .2 miles to substation.
TLD on right of inner substation (TLD CNS
- 235).
B1 2 4 Hwy. 49-N for 8 miles, right on Hwy. 160 for 2.8 miles, right on Gold Hill Rd. (98) at Tega Cay sign. Enter Tega Cay following i
Tega Cay Dr. for 2.6 miles, right on Windjammer Dr. for .6 miles to circle, right at circle for .2 miles, left on Kiwi t
Po'.nt for .2 miles to end of road.
i B1 4 5 Hwy. 49-N for 8 miles, right on Hwy. 160 for 3.9 miles, right on Das Rd. (99) for
- j. -
1.6 miles, left on Gray Rock Rd. (251) for
.7 alles to Lake Wylie Dam. Walk through plant to upstress side of the das (Water l
CNS #211).
B1 4 6 Hwy. 49-N for 8 miles, right on Hwy. 160
' for 3.9 miles, right on Das Rd. (99) for 1.6 miles, left on Gray Rock Rd. (251) for
.7 miles to Lake Wylie Dam. Go to river access on downstream side of dam.
B2 8 1 Hwy. 49-N for 10 miles, right on Carowinds Blvd. (1441) for 1.3 miles, left on Choate Circle for .3 miles. TLD is on the inside of fence left of the guardhouse (TLD CNS
- 246).
B2 4 2 Hwy. 49-N for 8 miles, right on Hwy. 160 for 2.8 miles to the Home Federal Savings and Loan on left side of road. TLD on barbed wire fence approximately 50 yds.
B2 5 3 Hwy. 49-N for 8 miles, right on Hwy. 160 for 2.8 miles, left on Gold Hill Rd. (98) for 1 mile, stop at the intersection of V Whitley Rd.
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Page 8 cf 13 m'
(' DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCI4SURE 5.3 PREDETERMINED SAMPLING LOCATIONS
~
', ZONE & RADIUS (Mi) No. DESCRIPTION B2 10 4 Hwy. 49-N for 10 miles, right on Carowinds Blvd. (1441) for 3 miles,1 tit on Hwy 51 for 3 miles, right on Hwy. 521 (Polk St.)
for 2.9 miles, right on Dorman Rd. for 1.1 elles, stop at the state line.
B2 5 5 Hwy. 49-N for 8 miles, right on Hwy.160 for 5.6 miles, right on Sutton Rd. (49) for 1.1 miles to the intersection of Gray Rock Rd. (251) .
B2 7 6 Hwy. 49-N for 8 miles, right on Hwy. 160 for 7.1 miles, right on Lee St. for .1 miles, left on Self St. for approximately 100 yds. TLD at Fort Mill Municipal Water Supply on right behind Springs Mill (TLD CNS #247, Water CNS #213).
. ,s B2 10 7 Hwy. 49-N for 8 miles, right on Hwy. 160 for 10 miles through Fort Mill to the Sugar
- Creek Bridse.
C1 4 1 Hwy. 274-5 for 3.8 miles, left on Mt.
Gallant Rd. (195) for 5.2 miles, left on India Hook Rd. (30) for .9 miles to the
' S.C. Wildlife Resources Dept. on left (TLD CNS #236).
l C1 5 2 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 5.6 miles to Red Burketts Body Shop on right.
C1 4 3 Hwy. 274-5 for 3.8 miles, left on Mt.
Gallant Rd. (195) for 3 miles, right on Homestead Rd. (657) for 2.5 miles to end of road. TLD is straight across at intersection of Twin Lake Rd. (TLD CNS
- 237).
1 C1 5 4 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 3 miles, right on Homestead Rd. (657) for 2.5 miles to end of road.
(< C1 4 5 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 1.3 miles, right on West Oak Dr. (962) for 1.2 miles to end at fork. TLD on left at fence (TLD CNS #238).
n._
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Page 9 of 13
.f N j DUKE POWER COMPANY ,
CATAWBA NUCLEAR STATION
. . HP/0/B/1009/04 ENCLOSURE 5.3 l PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (M1) No DESCRIPTION C1 5 6 Hwy. 274-5 for 5.1 miles, left on Hwy. 161 for 2.2 miles to fork in road, left at fork for .1 miles, S.C. National Guard Armory en left side of road.
C1 5 7 Hwy. 274-S for 5 miles to Carter Lumber Company.
C2 10 1 Hwy. 274-S for 5.1 miles, left on Hwy.161 for 2.2 miles to fork in road, left at fork on Celanese Rd. (50) for 8.2 miles to the ,
intersection of Springdale Rd.
C2 7 2 Hwy. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 8.5 miles to the j intersection of Cherry Rd. Go to Rock Hill
,s .
Municipal Water Supply across intersection on left (Water CNS #214)..
i
.l, ,
C2 7 3 Hwy. 274-8 for 9.2 miles, right on Herlong Ave for .3 miles to Piedmont Medical Center emergency entrance to back of hospital. TLD on fence at back right corner of Liquid Oxygen storage area (TLD
.CNS #248).
4 C2 10 4 Hwy. 274-8 for 5.1 miles, left on Hwy. 161 for 5.7 miles, right on Mt. Gallant Rd.
(195) for 1.5 alles, right on Hwy.21-121 Bypass for 2 miles, to the Fast Fare on left at the intersection of Springsteen Rd.
C2 10 5 Hwy. 274-S for 5.1 miles, left on Hwy.161 for 1.3 miles, right on Rawlinson Rd. (56) for 1.8 miles, left on Hwy. 5 for 1.6 miles, right on Heckle Blvd. (901) for 3.3 miles to end of road, left on Hwy. 72 for 1.2 miles, right on dirt road across from Wayne's Auto Service. Go .1 miles to Duke Power Company substation on left (TLD & Air !
CNS #217, need key).
C2 8 6 Hwy. 274-S for 5.1 miles, left on Hwy.161 for 1.3 miles, right on Rawlinson Rd. (56)
! ht_ ,/ for 1.8 miles, left on Hwy. 5 for .5 miles to Rock Hill Career Development Center on i
right. TLD on transmission tower in front of building (TLD CNS #249).
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Page 10 of 13 i
, , DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERt!INED SAMPLINC LOCATIONS 2ONE & RADIUS (Mi) No' . DESCRIPTION C2 10 '7 Hwy. 274-5 for 5.1 miles, left on Hwy. 161 for .1 miles, right on Adnah Church Rd.
(81) for 2.9 miles, right on Hwy. 5 for .2
- miles, left on Eastview Rd. (102) for 3.2 miles, right on Hwy. 322 for .1 miles, left on Falls Rd. for .9 miles to the
~
intersection of Oak Park Rd. (103).
C2 7 8 Nw y. 274-S for 3.8 miles, left on Mt.
Gallant Rd. (195) for 7.6 miles, left on Hwy. 161 for 1.1 miles, left on Hwy. 21 for
.4 miles, left on Grier McGuire Rd. for .5 miles to end of road.
D1 5 1 Hwy. 274-S for 5 miles to Carter Lumber Company. TLD on fence near gate (TLD CNS
- 239).
v -
-i D1 4 2 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 2.3 miles, left on Paraham Rd.
(54) for 1.5 miles to transmission tower on
D1 5 3 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 2.3 miles, left on Paraham Rd.
(54) for .6 miles, right on Harper Rd.
(815) for 1.4 miles to Allison Creek Bridge.
D1 5 4 . Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 3 miles. TLD on left at j beginning of fence (TLD CNS #241).
D2 10 1 Hwy. 274-S for 5.1 miles, left on Hwy. 161 for .1 miles, right on Adnah Church Rd.
(81) for 2.9 miles, right on Hwy. 5 for .2
! miles, left on Eastview Rd. (102) for 1 mile, right on Holland Rd. (157) for .7 miles, right on Turkey Fara Rd. (1172) for 1.2 miles, left on Russell Rd. (536) for .2 miles.
i 1
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5 l Page 11 of 13
~x DUKE POWER COMPANY ,
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING IDCATIONS ZONE & RADIUS (Mi) h DESCRIPTION D2 10 2 Hwy. 274-S for 5.1 miles, left on Hwy. 161 for .1 miles, right on Adnah Church Rd.
(81) for 2.9 miles, right on Hwy. 5 for .3 siles, left on Billy Wilson Rd. (1451) for 2.2 miles, right on Tbrkey Fara Rd. (1172) for .8 miles, left on Banfield Rd. for .3 miles to Fishing Creek Bridge.
D2 10 3 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 3.4 miles, left on 3wy. 49-S for 5 miles. Stop at Pantry on left.
D2 10 4 Hwy. 274-S for 1.2 miles, right on Campbell Rd. (80) for 3.4 miles, left on Hwy. 49-S for 5.2 miles, left on North Congress St.
(64) for .7 miles, left on Hwy. 5 for .2 miles to Duke Power Company Appliance Center on left. TLD on fence in back (TLD j CNS #250).
D2 10 5 Hwy. 274-5 for 1.2 miles, right on Campbell Rd. (80) for 3.4 miles, left on Hwy. 49-S for 1.7 miles, right on Old Limestone Rd.
(172) for 4.3 miles to and of road.
El 5 1 Hwy. 274-5 for 1.2 miles, right on Campbell Rd. (80) for 3.4 miles to the intersection of Hwy. 49.
El 5 2 Hwy. 49-S for 3 miles, right on Paraham Rd.
(54) for .7 miles to transmission tower on left after bridge (TID CNS #242).
El 5 3 Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 2.3 miles, left on Kingsburry Rd. (114) for .4 miles to transmission tower on left (TLD CNS #243).
El 5 4 Hwy. 274-N for 2.1 miles, left on Hwy. 55 i
for 2.3 miles to the intersection of Kingsburry Rd. (114).
E2 5 1 Hwy. 274-S for 1.2 miles, right on Campbell
\,_/ Rd. (80) for 2.3 miles, right on Paraham Rd. (54) for .9 miles to the intersection of Dr. Nichols Rd. (819),
i i
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Page 12 of 13
- j. .
- t. DUKE POER COMPANY .
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIDSURE 5.3 PREDETERMINED SAMPLING IDClifIONS ZONE & RADIUS (Mi) No. DESCRIPTION E2 10 - 2 Hwy. 274-N for 2.1 miles, left on Hwy. 55 '
for 7.4 miles to Duke i. wor Company Appliance Center on left. TLD on fence in back of building (TLD CNS #251).
E2 10 3 Hwy. 274-N for 2.1 miles., left on Hwy. 55 for 7.3 miles to the Pantry on left at the intersection of Hwy. 321 (behind Pantry).
F1 4 1 Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 1.5 miles to Bethel School. TLD on side of small building in back (TLD CNS #244).
F1 5 2 Hwy. 274-N for 2.1 miles, left on Hwy. 55 for 1.5 miles, right on Bethel School Rd.
(152) for 1 mile to the intersection of Holland Dr.
F1 4 3 Hwy. 274-N for 3.4 miles, left on Glenvista Rd. to Crowders Creek boat landing. TLD to east. of parking lot (TLD CNS #245).
F1 4 4 Hwy. 274-N for 3.1 miles to River Hills Plantation rear entrance at Hamilton's Ferry Rd. TLD behind green building on right corner (TIa CNS #230).
I i
F1 5 5 Hwy. 49-N for 2.9 miles to Sherer Hemorial Presbyterian Church parking lot on left.
F1 4 6 Hwy. 49-N for 4.1 miles to River Hills Plantation entrance guardhouse (TLD CNS
- 231).
F1 5 7 Hwy. 49-N for 3.6 miles, left on Montgomery Rd. for 1 mile. Stop in horseshoe curve i
near lake.
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l F2 10 1 Hwy. 274-N for 4.2 miles, left on Hwy. 557 l for 2.2 miles, right on Ridge Rd. (27) for j 5 miles to Bowling Green Presbyterian I
Church.
I v F2 5 2 Hwy. 274-N for 4.2 miles, left on Hwy. 557 for .6 miles to Pine Grove Baptist Church.
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Page 13 of 13 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
- HP/0/B/1009/04 ENCIOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS ZONE & RADIUS (MI) h DESCRIPTION F3 10 1 Hwy. 274-N for 4.2 miles, left on Hwy. 557 for .9 miles, right on Oakridge Rd. (435) at Bethel Fire Dept. for 5.4 miles to the intersection of Hwy. 274 (in N.C.)
F3 10 2 Hwy. 274-N for 5 miles, right on Pole Branch kd. (279) for 5.8 miles to Friendship Baptist Church on left.
F3 10 3 Hwy. 274-N fo: 5 miles, right on Pole Branch Rd. (279) for 2.8 miles, right on Hwy. 273 for 3 miles to Allen Steam Plant Bridge.
F3 14 4 Hwy. 274-N for 5 miles, right on Pole Branch Rd. (279) for 2.8 miles, right on Hwy. 273 for 7.2 miles into Belmont, right
. on Catawba St. for .6 miles, left at next j light for .2 miles to Belmont Municipal N_v Water Supply (Water CNS #218).
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CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.5 FIELD MONITORING DATA SHEET Date Team Members / Call Sign Inst. Type /No.
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Smear Sample Location Time Survey Taken Dose Rate (mR/hr) Activity (CCPM) eumuus M
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DUKE POWER COMPANY -
CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIDSURE 5.6 SAMPLE TIME REQUIRED FOR MINIMUM SAMPLE VOLUME FLOW RATE MINIMUM REQUIRED SAMPLING TIME IN MINITTES CFM LPM -
.5 = 14 . . . . . . . . . . . . . . . . . 71 1.0 = 2 8 . . . . . . . . . . . . . . . . . 36 -
1.5 = 42 . . . . . . . . . . . . . . . . . 24 2.0 = 56 . . . . . . . . . . . . . . . . . 18 2.5 = 70 . . . . . . . . . . . . . . . . . 15 3.0 = 84 . . . . . . . . . . . . . . . . . 12 3.5 = 99 . . . . . . . . . . . . . . . ... 11 4.0 = 113 . . . . . . . . . . . . . . . . . . 9 4.5 = 12 7 . . . . . . . . . . . . . . . . . . 8 4
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2 NOTE: When estimating time required to get a minimum volume of l'x 10 8 al if flow rate for the air sampler in use is not on table, so to next Lower f1w rate. The LPM are rounded off to the conservative side.
Example: Air Sampler flow rate = 106 LPM. Minisua time 11 minutes 3
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DUKE POWER COMPANY Page 1 of 2
- CATAWBA NCULEAR STATION
!. HP/0/B/1009/04 1 ENCLOSURE 5.7 l
FIELD MONITORING TEAN WORK SHEET FOR DETERMINING IODINE ACTIVITY j'
-Team Members Date Air Sampler No.
. Team Call Sign Canberra No.
AIR SAMPLE INFORMATION ANALYSIS RESULTS A B C D E F Sample ID. Air Sampler Flow Rate Iodine Activity Dose Rate Results No./ Time / Location Run Time (Min) (LPN). Microcuries/m1 . ares /hr Reported By:
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Column A) Number of Sample / Time it was Taken/ Sampling Location (ex. A0-2-10).
Coluna B) Length of time the air sampler ran. '
Column C) Air sampler setsr flow rate.
iolumn D) Activity from Canberra.
, Volumn E) Dose rate from Canberra.
Column F) Signature of person that calls in results to FMC.
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DUEE POWER COMPANY Page 2 of 2 f^ CATAWBA NUCLEAR STATION
( HP/0/B/1009/04 -
ENCLOSURE 5.7 OPERATOR GUIDELINES 5.6.1 NCA and Detector Set-Up 5.6.1.1 Disconnect DC power cord from unit.
5.6.1.2 Turn the contrast switch on the front of the unit clockwise to the ON mode.
5.6.1.3 Place sample holder with Na-22 check source onto the detector.
5.6.1.4 Press TEST SYSTEM. -
5.6.1.5 Press EN17,R to begin test.
5.6.1.6 14 test failed, press CLEAR ENTRY and remove the instrument from service.
5.6.1.7 If test passed, press E m R.
5.6.2 Collecting and Measuring Filter Cartridges NOTE: Record data on Field Monitoring Team Work Sheet for Determining
.s Iodine Activity (Sample Enclosure 5.6).
s ! - -
5.6.2.1 Press ANALYZE FILTER SAMPLE.
5.6.2.2 Press ERIER.
5.6.2.3 For each sample:
5.6.2.3.1 Place cartridge with the recognizable side toward the detector (in small poly bas) in sample holder.
5.6.2.3.2 Put detector and sample holder in shield.
~
- 5.6.2.3.3 Press ENTER to accept ID number. I 5.6.2.3.4 ' Press ENTER to accept current Flow Rate (LPM).
Otherwise, change number and press ENTER.
5.6.2.3.5 Press ENTER to accept current Flow Time (ein). .
Otherwise, change number and press ENTER. !
1 l 5.6.2.3.6 If the volume is determined to be too small,
! resample, press ENTER and return to Step 5.6.2.3.
l 5.6.2.3.7 Press ENTER to start Collect / Analyze.
) '
5.6.2.3.8 Report / Record Iodine activity (uci/al) and
\ l dose rate (aree/hr). '
V 5.6.2.3.9 Press NEXT SAMPLE.
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l 5.6.2.3.10 Label the cartridge and retain for later analysis.
5.6.3 After sampling completion, turn the contrast switch counter-clockwise to I
the STAND-BY mode.
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,, , . . Page 1 of 1 1 DUKE, POWER COMPANY -
CATAWBA NUCLEAR STATION HP/0/B/1009/04 TSC FIELD M N O GbRGANIZATION t
! POSITION NAME BUSINESS PHONE HOME PHONE i
Field Monitoring Coordinators:
Primary: C. V. Vray Alternates: Don Sexton Rick Theriault TSC Radio Operators:
Primary: P. W. Sturgis
! Alternate: Earl Russell
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Field Monitoring Teams:
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All Health Physics personnel with Field Monitoring Training.
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DUKE POWER COMPANY '
CATAWBA NUCLEAR STATION HP/0/B/1009/04 -
ENCLOSURE 5.9 EMERGENCY VEHICLES 5.9.1 The two designated emergency vehicles are the I&E and Health Physics vans.
The two vehicles are to be obtained (as directed by the FMC) by doing the following.
5.9.1.1 I&E Van 5.9.1.1.1 Obtain keys from the emergency kit.
5.9.1.1.2 If the vehicle is off-site request the FMC to contact
, the vehicle by TSC radio, have the vehicle to return to site immediately and obtain use when it returns.
5.9.1.2 Health Physics Van 5.9.1.2.1 Obtain keys from the emergency kit.
f 5.9.1.2.2 If the vehicle is off-site request the FMC to
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contact the vehicle by TSC radio, have the vehicle return to site insediately dad obtain d
use when it returns.
5.9.2 Obtain any other Station vehicle (if available) as directed by the FMC.
5.9.3 Voluntary use of personnel vehicles is another alternative that may be considered but should be a last option.
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Form 34731 (R9-86)
(1) IDNo.HP/0/B/ cd9/03 m DUKE POWER COMPANY Change (s)_,' n to PROCEDURE PROCESS RECORD 0 PREPARATION (2)* STATION cATAtmA met.wAn RTATTnw (3) PROCEDURE TITLE PERSONNEL / VEHICLE MONITORING FOR EMERGENCY CONDITIONS (4; PREPARED BY N - ' DATE 4 (5) REVIEWED BY
- DATE Cross-Disciplinary Revi By N/R -
/
(6) TEMPORARY APPROVAL (If Necessary) s By (SRO) DATE N
By -
DATE '
(7) APPROVED BY L*- DATE I I .
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(8) MISCELLANEOUS
,-g ' Reviewed / Approved By DATE I D# Reviewed / Approved By DATE -
(9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes, are included. -
Attach additional pages,if necessary.)
ADDITIONAL CHANGES INCLUDED. ges O No " <
(10) COMPARED WITH CONTROL COPY DATE -
COMPLETlON /.
(11) DATE(S) PERFORMED
~
(12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate! '
O Yes O N/A Listed enclosures attached? ^'
O Yes O N/A Data sheets attached, completed, dated and signed?
Oyes O N/A Charts, paphs, etc. attached and properly dated, identified and marked?
Oyes O N/A Acceptance criteria met?
VERIFIED BY DATE _
,N1) PROCEDURE COMPLETION APPROVED DATE
[
%d (14) REMARKS (Attach additional pages,if necessary.)
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c HP/0/B/1009/05 DUKE POWER COMPANY '
CATAWBA NUCLEAR STATION
-- PERSONNEL /VERICLE MONITORING
-a ;m FOR EMERGENCY CONDITIONS
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, 1.' O PURPOSE
,:? ;.
- To provide guidance for personnel and vehicle monitoring during a site
, evacuation resulting from a radiological emergency and to describe the
.s - responsibilities of the Reserve Personnel / Personnel Monitoring (RP/PM)
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Leader concerning tnat monitoring.
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2.0 REFERENCES
I J " 2.1 HP/0/B/1003/31, Operation and Calibration: Eberline Model E-140N 3.
Portable Count Rate Meter 2.2 HP/0/B/1004/06, Personnel Decontamination 2.3 HP/0/B/1004/21, Equipment Decontamination 2.4 HP/0/B/1009/09, Guidelines for Accident and Emergency Response
~V 2.5 HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the C,}
- Event of a Radiciodine Release -
i 2.6 RP/0/A/5000/10, Conducting a Site Assembly or Evacuation 1
,s - 2.7 System Health Physics Manual i,
2.8 Catawba Nuclear Station Directive 3.0.7 g 2.9 Catawba Nuclear Station Directive 3.8.3 2.10 Catawba Nuclear Station Emergency Plan i'
t
, 3.0 LIMITS AND PRECAUTIONS 3.1 If monitoring teams,are expected to be exposed to I-131 in excess of 70 MPC (6.1 x 10 7 pCi/ml), and as directed by the Surveillance
. and Control (S & C) Coordinator, each team member should ingest one L
tablet of Potassium Iodide.
, ve 3.2 Ensure that the radiation monitoring equipment has been battery 1 checked and source response checked as per Reference 2.1.
~
3.3 If emergency vehicle is found to be contaminated as per Reference
' - --' 2.9, and alternative transportation is not available, that vehicle
- may be released if needed for assistance and be decontaminated per
, Step 4.5.2.1.5 at the first opportunity.
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3.3.1 If available, an H.P. Technician should accompany the contaminated emergency vehicle.
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HP/0/B/1009/05 Page 2 of 4
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4.0 PROCEDURE 4.,1- When directed by the S & C Coordinator, the RP/PM Leader shall be responsible for implementing this procedure along with his/her other responsibilities as outlined in Reference 2.4.
4.2 Upon initiation of a site assembly, the RP/PM Leader should identify and dispatch, when necessary, personnel monitoring teams to the following locations:
NOTE: Manpower shall be supplied with respect to the nature of the accident and the availability of Health Physics personnel. Monitoring teams should be supplemented, relieved, or secured as practical.
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4.2.1 On-site assembly areas as listed in Reference 2.8.
4.2.2 Personnel Access Portal (PAP) 4.2.3 Evacuation Facility (s) as listed in Reference 2.8 (two teams if both locations are used).
NOTE: Evacuation Facility monitoring teas (s) are not dispatched until initiation of a site evacuation.
(
-s' 4.3 On-Site Assembly Area Monitoring Teas (s) 4.3.1 Monitoring team (s) dispatched to the on-site assembly areas shall monitor radiation levels in the area. If radiation levels reach 2 ares /hr, relocate personnel in an area with lower dose rate (relocation should always be in the direction of the PAP),
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4.3.1.1 Notify the RP/PM Leader of any corrective actions taken.
4.4 PAP Monitoring Team l
4.4.1 Obtain the Personnel Monitoring Kit from the Temporary i Administration Building (Temp. Admin.) and go to the PAP.
4.4.2 Contact the RP/PM Leader upon reaching the PAP.
l 4.4.3 Ensure all personnel receive proper monitorir.g as they exit through the PAP (portal monitors and portable count rate meters).
4.4.3.1 If an individual is found to be contaminated per Reference 2.9:
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HP/0/B/1009/05 Page 3 of 4 4.4.3.1.1 l Dress the individual in appropriate protective clothing and decontami-nate per Reference 2.2.
4.4.3.1.2 Notify the RP/PM Leader of all cases of personnel contamination.
4.4.3.2 If background radiation levels in the area render the portable count rate meters
(> 240 eps) and/or the portal monitors (alarms) useless, contact the RP/PM Leader who shall:
4.4.3.2.1 Coordinate with the S & C Coordinator the rel.ocation of the monitoring team to an area of lower background where personnel
. monitoring and control can continue.
4.4.3.2.2 Obtain an emergency radio transmitter / receiver from temp.
admin.
4.4.3.2.2 Notify the S & C Coordinator of corrective actions taken.
., 4.5 Evacuation Facility Monitoring Teas (s) e' 4.5.1 Obtain vehicle socitoring equipment from the Personnel Monitoring Kit.
4.5.2 As directed by the RP/PM Leader, perform random monitoring of employee vehicles.
4.5.2.1 If a vehicle is found to be contaminated per Reference 2.9:
j 4.5.2.1.1 Prevent further movement of the vehicle.
4.5.2.1.2 Post the vehicle as a contaminated
- area.
l 4.5.2.1.3 Monitor all vehicles in the area for contamination.
4.5.2.1.4 Provide general information on contamination surveys to the RP/PM Leader.
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4 HP/0/B/1009/05 Page 4 of 4 1
N 4.5.2.1.5 Decontaminate the vehicle per Reference 2.3.
4.5.3 Upon site evacuation and receiving notification of the Evacuation Facility (Alpha and/or Bravo) to be utilized, the RP/PM Leader shall dispatch the monitoring teas (s) to the Evacuation Facility where they shall:
4.5.3.1 Verify their arrival with the RM/PM Leader.
4.5.3.2 Locate the Personnel Survey Kit (see Evacuation Facility Layout Drawings, Enclosure 5.1) and prepare to monitor incoming personnel.
4.5.3.3 Ensure that personnel are properly monitored and readied for release.
4.5.3.1. If applicable, take necessary actions per step 4.4.3.1.
4.5.3.4 List all personnel's names, social security numbers, and Health Physics badge numbers on the Evacuation Personnel Dose Record Sheet (Enclosure 5.2). This form should be used to determine any dose commitment at a later time.
4.5.3.5 If warranted, monitor employee vehicles and take necessary actions per step 4.5.2.1.
4.5.3.6 Notify RP/PM Leader or the S & C Coordinator of all actions taken.
5.0 ENCLOSURES 541 Sample of Evacuation Facility Layout Drawings 5.2 Sample of Evacuation Personnel Dose Record l
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NF/0/5/I009/05 g Enclosure 5.1 s
Evacuation Facility Layout Drawing i
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OFFICE E
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Enclosuro 5.2 EP/0/3/1009/05 Page -
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- EVACUATION P n50NNEL DOSE RECORD 86 SOCIAL g,p N sEcatz1T men Bands -
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Form 34731 (R9-86) (1) ID Nc)IP/0/B/1009/06 DUKE POWER COMPANY Change (s) O to I I
PROCEDURE PROCESS RECORD a incorporated j PREPARATION CATAWBA NUCLEAR STATION (2) STATION ALTERNATIVE METHOD FOR DETERMINING DOSE RATE WITHIN THE (3) PROCEDURE TITLE REACTOR BUILDING (4) PREPARED BY OATE O (5) REVIEWED BY = DATE #7 ff V f &
Cross Disciplinary Review By N/R -
(6) TEMPORARY APPROVAL (If Necessary)
By (SRO) DATE By -
DATE (7) APPROVED BY d' DATE I I (a) MISCELLANEOUS f, Reviewed / Approved By DATE i i D Reviewed / Approved By DATE (9) COMMENTS (For procedure reissue indicate whether additional changes, other then previously approved changes, are included.
Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. ONo
{es (10) COMPARED WITH CONTROL COPY DATE
, COMPLETION l (11) DATE(S) PERFORMED l
(12) PROCEDURE COMPLETION VERIFICATION.
O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate?
O Yes O N/A Listed enclosuris attached?
O Yes O N/A Data sheets attached, completed, dated and signed?
Oyes O N/A Charts, graphs, etc. attached and persperfy dated, identified and marked?
O Yes O N/A Acceptance criteria met?
j VERIFIED BY DATE l
113) PROCEDURE COMPLETION APPROVED DATE V
(14) REMARKS (Attach additional pages,if necessary.)
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Form 18855 (3-80)
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DUKE POWER COMPANY ALARA EVALUATION CHECKLIST (1) Station CATAWBA NUCLEAR STATION Unit: 1 2 3 Other: SHARED (2) Checklist Applicable to: HP/0/B/1009/06 (3) ALARA Evaluation Check those items below which were considered applicable during the preparation and ~
review of this document.
Flushing and draining were used to minimize source - strength and con-tamination levels prior to performing an operation.
Permanent and/or movable shielding was specified for reduction of levels.
Use of permanent or temporary local exhaust ventilation systems was used for control of airborne contamination.
m X Operation was designed to be completed with the least practicable time
!. spent in the radiation field.
\s X Appropriate tools and equipment were specified for the operation to be performed.
I X The operation was designed considering the minimum number of people necessary for safe job completion.
. I Remote handling equipment and other special tools were specified to reduce external dose.
Contamination - control techniques were specified.
The operation was designed to be conducted in areas of as low an exposure as practicable. -
Additional ALARA considerations were:
i ALARA Principles were not considered since the procedure did not involve work in a radiation area.
, (5) Prepared by: M_/of A M Date /-9M (6) Reviewed by: '
a, Date //f
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4 remissesapsen DUKE POWER COMPANY -
NUCLEAR SAFETY EVALUATION CHECKUST (1) STATION. CATAWBA NUCLEAR STATION N :1 2 3 OTHER: CNADFM i
PR CHANGE, (2)EVALUM10N OR TEST / EXPERIMENT): APPLICABLETO(/0/B/1009/06 HP ALTERNATIVE METh0DDESCRIPTION OR AND G SENUMBER OF NS RATE WITHIN THE REACTOR BUILDING (3) SAFETY EVALUATION-PART A The item to which tNs evaluation is W represent:
owe ElNo A change to the station or procedures as desenbod h the FSAR: or a test or expenment not de-
, screed h the FSAR7 Affected FSAR Seenon(s) are: S*2 D*Et 3-e .
(n j If the answer to the abme is "Yes" identify the aNected section(s) of the FSAR. Attach additonal shoots as necessary (4) SAFETY EVALUATION-PART B l
0We E No WE this item require a change to the station Technical Specifications? Affected Tech. Specs. Sec-tion (s)are: see name 3.
If the answer to the abme is "Yes," idonefy the specification (s) eNected and/or attach the af4* aNa page(s) with the change (s) incicoled. Tech. Spec. changes reques NSRS sd NRC approval prior to use.
(5) SAFETY EVALUATION-PART C As a result of the item to which this evah wing is a(34 aNa-O Yes SNo WW the probabWty of an accident pronously evaluated h the FSAR be increened? Explan1.
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Oyes X1No WM the consequences of an accident previously evaluated in the FSAR be increased? Explain: _
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> DUKE POWER COMPANY NUCLEAR SAFETY EVALUATION CHECKLIST HP/0/B/1009/06 THIS PROCEDURE HAS BEEN REVIEWED AGAINST THE FSAR AND TECHNICAL SPECIFICATIONS AND NO CHANGES TO THESE DOCUMENTS ARE REQUIRED.
FURTHER, NO INCREASE IN PROBABILITY, CONSEQUENCE, OR POSSIBILITY OF AN ACCIDENT OR EQUIPMENT MALFUNCTION HAS BEEN OBSERVED AND THE MARGIN OF SAFETY OF ANY TECHNICAL SPECIFICATION WILL NOT BE CHANGED.
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION ALTERNATIVE METHOD FOR DETERMINING i
DOSE RATE WITHIN THE REACTOR BUILDING 1.0 PURPOSE 3 This procedure describes an alternative method for determining the dose rate within the Reactor Building in the event the Reactor Building monitor is inoperable.
2.0 REFERENCES
2.1 System Health Physics Manual 2.2 HP/0/B/1000/02 Taking, Counting and Recording Surveia i 2.3 Memorandum For File, " Variables Used in HP/0/B/1009/06", dated January 23, 1984.
! 3.0 LIMITS AND PRECAUTIONS t
3.1 This procedure is written for use under abnormal conditions which
. could involve extremely high radiation levels.
4 Only Health Physics management should authorize the use of this 1 procedure when needed and should provide appropriate surveillance i and control.
l 3.2 Check that survey instrument (s) to be used have been calibrated and response checks have been performed.
l 3.3 The method described below for determining the Reactor Building dose rate is an approximation and consideration shall be given to interference to background sources in the area.
4.0 PROCEDURE 4.1 Method Using Dose Rate at Upper Personnel Hatch 4.1.1 Using a high range survey meter, obtain the dose rate at
{ the upper personnel hatch by placing the meter's detector in contact with the center of the hatch's outside door.
NOTE: Consider use of extendable probe instruments to limit dose.
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~~'.) 4.1.2 Determine the Reactor Building dose rate from the ,
following equation.
RB = 661 x RH RB = Reactor Building Dose Rate (R/hr)
RH = Survey Meter Dose Rate at Upper Personnel Hatch (R/hr) 661 = 1 2 * .001293 g/cm 3 -
21.67 cm + 2.7 E-2 cm3 /g 4.2 Record results on appropriate HP forms as per Reference 2.2.
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5.0 ENCLOSURES N/A
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, ~ Form 34731 (3 34) (1) ID No.HP/0/3/1009/09 DUKE POWER COMPANY Changels) O to PROCEDURE PROCESS RECORD 3 lacorporated PREPARATION
, C) STATION Catawba Guidelines for Accident and Emergency Response C) PROCEDURE TITLE (4) PREPARED BY DATE /,/f[f f C) REVIEWED BY d I DATE /
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Cross Disciplinary Review By N/R , -
C) TEMPORARY APPROVAL (if Necessary)
By (SRO) Date By Date (7) APPROVED BY d' DATE lb
, .,C) MISCELLANEOUS
-. Reviewed /Approwd By Date Reviewed /Ar, proved By Date COMPLETION C) DATEts) PERFORMED (101 PROCEDURE COMPLETlON VERIFICATION O Yes O N/A Check lists and/or blanks proserly initiated, signed, dated or filled in N/A or N/R, as appropriate?
O Yes C N/A Listed enclosures attached?
O Yes O N/A Data sheets attached, eompleted, dated sad signed?
Oyes O N/A Charts, ysphs, etc. ettached and prone ly dated, identified and marked?
' Oyes ON/A Acceptance criteria met?
VERIFIED BY DATE
, (11) PROCEDURE COMPLETION APPROVED DATE t:
i Q REMARKS
. . _ _ _ _ _ _ _ , _ _ _ . . . ~ . _ _ _ _ _ . _ . . , , . _ . _ . - - _ _ _ . . . _ _, . , . . . . _ _ , _ _ _ _ _ _ _ _ _ . _ _ _ , , . _ . _ _ . . . _ _ _ _ , _ _ _ _ _ . , - _ . . _ _ _
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HP/0/B/1009/09 DUKE POWER COMPANY CATAWBA NUCLEAR STATION GUIDELINES FOR ACCIDENT AND EMERGENCY RESPONSE 1.0 PURPOSE 4
1.1 To pre.?ide guidance for notification / activation of the Health Physics Organization in the event of an emergency situation.
1.2 To assure proper assignment of responsibility. -
1.3 To give general guidance for initial response of the Health Physics organisation.
1.4 To give general guidance for continuing response of the Health Physics organization.
2.0 REFERENCES
2.1 HP/0/B/1001/12, Technical Specifications Gaseous Waste Sampling and Analysis.
. .y 2.2 MP/0/B/1009/02,* Investigation of Possible Overexposure, Personnel Contamination, and/or Unusual Radiological Occurrences.
f' 2.3 HP/0/B/1009/04, Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station.
2.4 HP/0/B/1009/05, Personnel / Vehicle Monitoring for Emergency Conditions. ,
- 2.5 HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within
- the Reactor Building.
2.6 HP/0/B/1009/07, In-plant Particulate and Iodine Monitoring Under Accident Conditions.
I 2.7 HP/0/B/1009/08, Contamination Control During Transportation of Contaminated Injured Individuals.
2.8 Hf/0/B/1009/12, Quantifying Gaseous Release Through Steam Relief ;
Valves Under Post-Accident Conditions.
2.9 HJ/0/B/1009/13, Off-Site Dose Projection - Uncontrolled Release of Radioactive Material through the Unit Vent.
i 2.10 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled i Release of Liquid Radioactive Material.
2.11 HP/0/B/1009/15, Offsite Dose Projections - Uncontrolled Release of Gaseous Radioactive Material other than through the Unit Vent.
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/ 2.12 HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the
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Event of a Radiciodine Release.
2.13 HP/0/B/1009/17, Post Accident Containment Air Sampling System.
2.14 HP/0/B/1009/18, Offsite Dose Projections.
2.15 HP/0/B/1009/19, Emergency Radio System Operations, Maintenance, and Comumunication.
2.16 HP/0/B/1009/21, Abnormal Unit Vent Sampling.
2.17 RP/0/A/5000/11, Protective Action Recommendations Without the OAC.
2.18 RP/0/B/5000/12, Control of Assessment and Repair Teams.
2.19 Catawba Nuclear Station Emergency Plan.
2.20 System Health Physics Manual.
2.21 Catawba Nuclear Station, Station Directive 2.8.1, Reporting Requirements.
2.22 Catawba Nuclear Station, Station Directive 3.8.4, Onsite Emergency Organization.
, 3.0 LIMITS AND PRECAUTIONS ,
3.1 This procedure shall only be initiated at the direction of Health Physics Supervision.
3.2 This procedure may be initiated in part or whole, depending on the type and severity of emergency.
3.3 This procedure provides general guidance for initial response. Any particular situation may require actions not addressed in this procedure.
i j 3.4 For incidents occurring during backshifts, Health Physics shift personnel shall be responsible for on-site response only until directed otherwise by the Station Health Physicist.
4.0 PROCEDURE l
4.1 Upon notification of an emergency condition, the Station Health Physicist shall activate the Health Physics organization by notifying one or all of the following:
4.1.1 Surveillance and Control Coordinator.
4.1.2 Support Functions Coordinator.
! " , 4.1.3 Staff Coordinator.
4.1.4 Shift Technician (To advise, if during back shift).
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i 4.2 Individual coordinators will notify alternates and supervisors to be under their direction during the emergency, and will make arrangements through the supervisors for the notification of non-exempt personnel.
4.3 If the emergency is classified above the Notification of Unusual Event category, the Station Health Physicist shall proceed to the Technical Support Center (TSC), and coordinate the overall Health Physics response. Enclosures 5.2 and 5.3 provide general guidelines for response.
4.4 When notified to respond to an emergency, the Surveillance and Control Coordinator shall assume alternate responsibility for the Station Health Physicist, and shall activate the S&C Coordinator identified in Reference 2.18 who will act according to Enclosures 5.4 and 5.5.
4.5 When notified to respond to an emergency, the Support Functions Coordinator shall assume alternate responsibility for the Station Health Physicist and shall activate the Support Functions Coordinator identified in Reference 2.18 who will act according to Enclosures 5.6 and 5.7.
4.6 When notified to respond to an emergency, the Staff Coordinator
.cx shall act according to Enclosures 5.8 and 5.9.
(* 4.7 When notified to respond to an emergency, the Field Monitoring .
Coordinator shall act according to Enclosures 5.10 and 5.11.
4.8 When notified to respond to an emergency, the Operation Support Center (OSC) Supervisor shall act according to Enclosures 5.12 and 5.13.
5.0 ENCLOSURES 5.1 Guidelines For Planned Emergency Exposures 5.2 Station Health Physicist - Initial Response 5.3 Station Health Physicist - Continuing Response 1
l 5.4 Surveillance and Control Coordinator - Initial Response i
5.5 Surveillance and Control Coordinator - Continuing Response 5.6 Support Functions Coordinator - Initial Response i
5.7 Support Functions Coordinator - Continuing Response 5.8 Staff (Data Analysis) Coordinator - Initial Response j 5.9 Staff (Data Analysis) Coordinator - Continuing Response S
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5.10 Field Monitoring Coordinator - Initial Response 5.11 Field Monitoring Coordinator - Continuing Response 5.12 OSC Health Physics Supervisor - Initial Response 5.13 OSC Health Physics Supervisor - Continuing Reaponse 5.14 Reserve Personnel / Personnel Monitoring Leade: Response 5.15 OSC Response Personnel Dose Record Form 5.16 Procurement of Helicopters for Aerial Environmental _ Surveillance 4
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<~g HP/0/B/1009/09 f ENCLOSURE 5.1 GUIDELINES FOR PLANNED EMERGENCY EXPOSURES 5.1.1 Obtain the verbal or written approval of the Emergency Coordinator to exceed planned maximum limits.
5.1.2 If it is necessary to remedy a situation immediately hazardous to life and property, an individual (Duke Power personnel, or Outside Services) may receive exposure up to:
Whole Body 5 rems (25 res)*
Skin of the Whole Body 30 rems (125 res)*
or Thyroid Extremities 75 rems
- Doses up to this limit may be authorized by the Recovery Manager.
5.1.3 If it is necessary to save lives or prevent loss of lives and/or extensive damane to property, an individual may volunteer to receive exposure up to:
Whole Body 25 rems (75 res)*
Skin of the Whole Body 150 rems or Thyroid
,, Extremities 375 rems t
-_.
- Doses up to this 1Leit may be authorized by the Recovery ,
. Manager, Station Manager or Emergency Coordinator. For application of these exposures, extensive damage to property should be considered to result in loss of life or the inability to control or mitigate the accident with the assurance that life can be protected.
5.1.4 If possible, the individual (s) should be selected by the following criteria:
- 5'.1.4.1 Personnel should be volunteers or professional rescue j personnel.
i 5.1.4.2 Personnel should be broadly familiar with the potential i consequences of such exposure.
5.1.4.3 Women capable of reproduction should not take part in these actions.
j 5.1.4.4 All factors being equal, volunteers absve the age of 45 should be selected.
i 5.1.5 Exposure shall be maintained ALARA.
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5.1.6 Internal exposure should be minimized by the use of the best available respiratory protection, and contamination should be controlled by the
! s. , use of available protective clothing.
5.1.7 All exposures (permissible, planned maximum, planned emergency and
! accidental) shall require documentation and an occupational dose penalty if necessary.
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~S HP/0/B/1009/09
' ENCLOSURE 5.1 GUIDELINES FOR PLANNED EMERGENCY EXPOSURES 5.1.8 Exposures above the guidelines of 5ection 5.1.3 should be authorized by the Recovery Manager, Station Manager or Emergency Coordinator and will require a medical decision as to whether the individual may continue in radiological work and should be limited to once in a lifetime.
5.1.9 Reports of planned emergency exposures shall be reported as per Catawba Nuclear Station Directive 2.8.1 (Reporting Requirements).
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. HP/0/B/1009/09 ENCLOSURE 5.2 ,
, STATION HEALTH PHYSICIST
. INITIAL RESPONSE 5.2.1 Assemble supporting asterials and take to TSC.
5.2.2 The Station Health Physicist shall as necessary:
5.2.2.1 Establish the exposure limit for blanket dose extension, for Exposure Class 1 to a maximum of 1000 mrem /qtr; for Exposure Class 3 to a maximum of 2500 mRes; for Exposure Class 2 personnel (pregnant females) they shall not be extended above their 500 mrem limit, and should be reassigned to work locations in the Administration Building until radiation levels are evaluated.
5.2.2.2 Govern planned emergency exposures by Enclosure 5.1 (Guidelines For Planned Emergency Exposures).
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5.2.2.3 Coordinate the overall Health Physics response.
5.2.2.4 Recommend protective action on-site for assembled personnel and those with work duties.
5.2.2.5 Recommend off-site protective action to the Emergency Coordinator until the CMC (Crisis Management Center) is
'l activated. . .
5.2.2.6 Initiate, as necessary, HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the Event of a Radiciodine Release.
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/. ~3 4 ENCI.0SURE 5.3 STATION HEALTH PHYSICIST -
CONTINUING RESPONSE 5.3.1 Interface with the CMC when it is activated.
5.3.2 Coordinate Health Physics shift rotation and augmentation of personnel and equipment.
5.3.3 Should evacuation be required; coordinate the identification of "Non-Essential" personnel with other TSC groups.
5.3.3.1 All females should be given first consideration due to limited use in a radiological exposure situation.
5.3.3.2 Sufficient personnel should be retained to support need for backup personnel.
5.3.4 Direct trending of available information to support Health Physics TSC response.
5.3.5 When CMC is in place, continue Protective Action assessment and recommendations as a confirming response.
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- / ))' ENCLOSURE 5.4 l
-,. SURVEILLANCE AND CONTROL COORDINATOR .
INITIAL RESPONSE 5.4.1 Assemble supporting materials and take to TSC.
5.4.2 Establish radiological access controls for the Station and Control i Room.
5.4~.2.1 Initiate, as necessary, HP/0/B/1009/07, In-Plant Patciculate and Iodine Monitoring Under Accident Conditions.
5.4.2.2 Initiate, as necessary, HP/0/B/1009/08, Contamination Control During Transportation of Contaminated Injured Individuals.
5.4.2.3 Initiate discussions by need for Buddy System for radiological conditio.as. ,
t 5.4.3 If the emergency is classified above the Notification of Unusual ,
Event category:
- 5.4.3.1 Send the following personnel as necessary to the Operations Support Center (OSC): -
^
., 5.4.3.1.1 One Supervisor to coordinate Health Physics i support and comunanicate with the TSC and shall act according to Enclosures 5.12 and 5.13.
5.4.3.1.2 One Technician to provide job coverage (sampling, operation, maintenance, etc.).
5.4.3.1.3 Two Technicians to monitor and report plant radiological status.
5.4.3.1.4 Two Technicians to provide fire / medical emergency / rescue tese/ damage control coverage. !
5.4.3.2 Direct sufficient personnel to the Administra-tion Building, DRC office, as staging area.
5.4.3.3 Identify a Supervisor or Lead Technician as Reserve j
- Personnel / Personnel Monitoring Leader and he/she shall act I according to Enclosure 5.14.
t 5.4.3.4 Proceed to the TSC and coordinate Surveillance and Control
! response, with emphasis upon OSC activities.
l 5.4.3.5 Request TSC Security staff to provide locations of officers remaining on post. Evaluate esposure potential for these !
officers and recommend protective actions as necessary.
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HP/0/B/1009/09 ENCLOSURE 5.5 -
SURVEILLANCE AND CONTROL COORDINATOR CONTINUING RESPONSE 5.5.1 The S&C Coordinator shall, as necessary:
5.5.1.1 Initiate through RP/PN Leader HP/0/B/1009/05, Personnel / Vehicle Monitoring for Emergency Conditions, when a site assembly occurs due to radiological conditions.
5.5.1.2 Initiate, as necessary, HP/0/B/1009/17, Post Accident Containment Air Sampling System.
5.5.2 Provide direction and support to the OSC Health Physics Supervisor:
5.5.2.1 Coordinate in plant and on-site monitoring in support of TSC needs.
5.5.2.2 Keep 08C Supervisor appraised of TSC events and activities that may require OSC response (planned maintenance, operation, sampling).
5.5.2.3 Coordinate with OSC and TSC groups to ensure adequate pre planning occurs to limit radiation exposures.
's 5.5.2.4 Obtain additional emergency hit items and supplies to j support OSC if needed.
5.5.3 ' Monitor dose rate in TSC. Initiate discussion with Station Health Physicist regarding the need to evacuate the TSC should dose rate exceed 5 mR/hr and be expected to continue.
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ENCI.08URE 5.6 SUPPORT TUNCTIONS COORDINATOR INITIAI, RESPONSE 5.6.1 Assemble supporting asterials and take to TSC.
5.6.2 Evaluate the need to establish an alternate location for sample analysis.
5.6.3 Establish a coynt room sample priority list if emergency radiological sampling is in progress or is going to begin.
5.6.4 Initiate, as necessary, HP/0/B/1009/02, Investigation of Pcssible Overenposure, Personnel Contamination, and/or Unusual Radiological Occurrences.
5.6.5 If the emergency is classified above the Notification of Unusual Event category:
5.6.5.1 Establish alternate dosimetry issue points for personnel and high range dosimetry, as necessary.
5.6.5.2 Issue blanket dose extensions for OSC personnel, to the limit established by the Station Health Physicist.
I 5.6.5.3 Provide representatives from Dosimetry and Records Control in the OSC to .
I 1 5.6.5.3.1 Record the following inforestion on the OSC J Response Personnel Dose Record Form (Enclosure 5.15) as emergency response personnel enter the 08C.
5.6.5.3.1.1 Name 5.6.5.3.1.2 Health Physics Badge Number 5.6.5.3.1.3 Social Security Number 5.6.5.3.1.4 Exposure class 5.6.5.3.1.5 Birthdate 5.6.5.3.1.6 Age 5.6.5.3.1.7 Work Group 5.6.5.3.1.8 Quarterly and yearly dose to date 5.6.5.3.1.9 Permissible lifetime dose to date 5.6.5.3.1.10 Total lifetime dose to date
- r. s NOTE: This may be obtained at the first available opportunity.
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SUPPORT FUNCTIONS COORDINATOR INITIAL RESPONSE 5.6.5.3.2 As personnel leave the OSC to enter a radiation field, dosimeters shall be checked for reseroing and the following information recorded on the OSC Response Personnel Dose Record Form (Enclosure 5.15):
5.6.5.3.2.1 Date and Time Out 5.6.5.3.2.2 Dosimeter Reading-Out 5.6.5.3.3 As personnel return to the OSC from entering a radiation field, dosimeters shall be checked for reseroing and the following information recorded on the OSC Response Personnel Dose Record Form (Enclosure 5.15):
5.6.5.3.3.1 Date and Time In 5.6.5.3.3.2 Dostmeter Reading In 5.6.5.3.3.3 Retotal of quarterly dose .
5.6.5.4 Proceed to the TSC and coordinate Support Tunction Response.
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ENCLOSURE 5.7 '
SUPPORT FUNCTIONS COORDINATOR ~
CONTINUING RESPONSE -
5.7.1 Ensure collection and retention of collected samples is adequate to ,
reconstruct data following the emergency. -')
5.7.2 Acquire additional anti-contamination clothing, dosimetry, Ti respiratory or monitoring equipment from:
Existing Station Stock CMC Admin and Logistics Groups '
5.7.3 Direct implementation of HP/0/B/1001/12, Technical Specifications
~
r' Gaseous Waste Sampling and Analysis and/or HP/0/B/1069/21, Abnormal ' '.
Unit Vent Sampling as necessary to collect containment and unit vent samples.
All sampling will be coordinated with OSC Health Physics -
personnel to determine habitability and RWP requirements.
5.7.4 Retrieve radiation instrumentation from Instrument Issue area and c stage in DRC office.
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> S ENCLOSURE 5.8 STAFF (DATA ANALYSIS) COORDINATOR '
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INITIAL RESPONSE
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Assemble supporting materials and take to TSC.
f.7 g f- 5.8. ( ,
~ 5.8.1.1 Review any assessments made using RP/0/A/5000/11, j
Protective Action Reconnendationa Without the OAC.
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,, 5.8.2 Initiate the following procedures as necessary.
5.8.2.1 HP/0/B/1009/13, Off-Site Dose Projection - Uncontrolled
.. f , ' Release of Radioactive Material through the Unit Vent.
- 5.8.2.2 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled Release of Liquid Radiasctive Material.
- s 5.8.2.3 HP/0/B/1009/15, Offsite Dose Projections - Uncontrolled O
Release of Gaseous Radioactive Material other than through the Unit Vent.
5.8.2.4 HP/0/B/1009/18, Offsite Dose Projections.
5.8.3 -
Assume the duties of the Data Analysis Coordinator if the emergency is classified above the Notification of Unusual Event Category and:
, 5.8.3.1 Proceed to the TSC.
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, according to Enclosure 5.10 and 5.11.
i , ~ 5.8.3.3 Initiate the following procedures as necessary:
PI 5.8.3.3.1 HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within the Reactor
. Building.
5.8.3.3.2 HP/0/B/1009/12, Quantifying Gaseous Release
, through Stesa Relief Valves Under Post-Accident 4
Conditions.
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- 5.8.3.4 Provide special evaluation in areas such as shielding, -
{ off-c.ite consquences of a containment loss or stems
- generator tube rupture, BRA, etc.
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~'s ENCLOSURE 5.9 ,
STAFF (DATA ANALYSIS) COORDINATOR CONTINUING RESPONSE 5.9.1 Evaluate the need to recalculate dose projections based upon:
5.9.1.1 Enown changes in meteorological status (wind speed, wind direction, AT, precipitation).
5.9.1.2 Enown changes in EMF readings.
5.9.1.3 Projected change in meteorological conditions.
5.9.2 Evaluate total effect of dose projections when makin.g multiple releases (containment, vent releases, etc.).
5.9.3 Evaluate total effect of dose projections when releases are expected to continue for longer than two hours, or to otherwise be effected by extended evacuation times.
5.9.4 When the CMC is established, all dose projections and recommendations will be coordinated with the CMC Off-Site Radiological Support Section to assure consistency.
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. -~g HP/0/B/1009/09 I, 3 ENCLOSURE 5.10 FIELD MONITORING COORDINATOR INITIAL RESPONSE 5.10.1 Assemble supporting materials to take to' TSC.
5.10.2 Initial Response 5.10.2.1 Activate the field monit. ing organization by:
5.10'.2.1.1 Notifying the TSC Radio Operator to report to the TSC and initiate HP/0/B/1009/19, Emergency Radio System Operations, Maintenance, and Communications.
5.10.2.1.2 Field Monitoring Team (FMT) members will be organized by the RPPM Leader, as per Enclosure 5.14, as follows:
Team Call Sinn Number of Members Transportation Alpha 2 Land Vehicle -
Bravo 2 Land Vehicle Charlie 2 Land Vehicle Delta 2 Land Vehicle
( ; Echo 1 Helicopter nil / Foxtrot 2 (Onsite Team) 5.10.2.2 Proceed to the TSC.
5.10.2.3 Obtain~ plant radiological status and evaluate the potential or existence of an off-site release of radioactive material (liquid or gaseous).
5.10.2 4 Obtain meteorological information and determine initial
- sample direction.
5.10.2.5 Determine the need for aerial environmental surveillance based on plant radiological status and meteorological information, 5.10.2.5.1 If immediately needed, obtain helicopter support per Enclosure 5.16, Procurement of Helicopters for Aerial Environmental Surveillance.
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. s HP/0/B/1009/09 I. ', ENCLOSURE 5.10 ,
FIELD MONITORING COORDINATOR INITIAL RESPONSE 5.10.2.5.2 If the possibility exists for future need, put helicopter support on standby per Enclosure 5.16.
5.10.2.6 Determine plume location (width) based on stability class (establish estimated plume location on 10 mile radius map).
~
5.10.2.7 Dispatch on-site monitoring team, Foxtrot, up to the exclusion area boundary fence at the estimated plume location. '
5.10.2.7.1 Upon the completion of on-site monitoring, dispatch Foxtrot to the H.P. Assembly area or OSC if the assembly area has been evacuated.
5.10.2.8 Dispatch Alpha Team to the 0.5 mile radius to traverse the plume at it's estimated arc.
.. s l' ' t-?' 5.10.3 Based on stability class, wind direction, wind speed, and the time since release (time since trip), dispatch 8, C, and D teams as follows:
5.10.3.1 Dispatch Bravo Team to criss-cross the left side of the plume.
5.10.3.2 Dispatch Charlie Team to criss-cross the right side of the plume.
5.10.3.3 Dispatch Delta Team to a point at the centerline of the plume.
5.10.3.4 Instruct FNT's to take, as needed, special samples per HP/0/B/1009/04.
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ENCLOSURE 5.11 FIELD MONITORING COORDINATOR -
CONTINUING RESPONSE 5.11.1 Continuing Response 5.11.1.1 Maintain the 10 mile radius map by:
5.11.1.1.1 Posting current FNr locations.
5.11.1.1.2 Posting latest instrument survey results for each monitoring location.
5.11.1.1.3 Confirm and illustrate the approximate plume shape and location based on the accumulated field data.
5.11.1.2 Continue field monitoring strategies by:
5.11.1.2.1 Reviewing plant radiological status, field data and meteorological information approximately every 15 minutes for changes which might affect field monitoring strategies.
5.11.1.2.2 Advise FMT's on public protective actions and conditions they.should be aware of while Q' in the area.
5.11.1.3 Advise the Data Analysis Coordinator'of field monitoring results.
i
- 5.11.1.4 Maintain an organized file of all sample results/ data generated from FMT activities.
5.11.1.5 Maintain FMT equipment and supplies including protective clothing, liquid nitrogen, etc.; and schedule shift coverage.
5.11.2 CMC Turnover l 5.11.2.1 Once CMC is established, coordinate turnover of FMT's to CMC control.
5.11.2.2 Turnover of TSC FMT's to CMC Control shall occur at the intersection of SC 274 and SC 49. Should plume location interfere, alternate turnover location may be established.
, 5.11.2.3 Once CMC has assumed control of Flff's, notify the Data l
Analysis Coordinator and dissolve TSC field monitoring organization.
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HP/0/B/1009/09 ENCLOSURE 5.12 '
L OSC HEALTH PHYSICS SUPERVISOR INITIAL RESPONSE f
5.12.1 Assemble supporting materials and take to OSC.
5.12.2 Contact OSC Operation Supervisor and coordinate Health Physics support for OSC activities. Assist in implementation of RP/0/B/5000/12, Control of Assessment and Repair Teams.
'5.12.3 Provide immediate job coverage as necessary. Give due consideration to the fact that plant conditions may be unstable and radiological conditions unknown. _
5.12.4 Provide immediate Health Physics coverage as necessary to support Fire Brigade, damage control, medical emergency and other emergency activities.
5.12.5 Direct technicians to obtain prelf-inary radiological information availabic in Control Room.
5.12.5.1 Emphasis should be placed upon determining the areas of the plant experiencing increasing radiation levels.
3,, 5.12.6 Based upon initial Control Room indications, direct technicians to i ^. ; monitor and report radiological status which will support OSC U activities. .
5.12.7 Establish control over all OSC personnel radiation exposure and limit i to blanket dose extension levels.
5.12.7.1 All activities which cause these levels to be approached or exceeded, require pre planning and coordination with TSC S&C Coordinator.
5.12.8 Direct assignment of additional dosimetry to provide adequate monitoring for the conditions expected.
5.12.9 Direct the use of protective clothing to limit the spread of 4
contamination consistent with the conditions expected.
5.12.10 Obtain additional instrumentation to support OSC activities (Teletector, neutron instrument alpha instrument, friskers), if necessary.
5.12.11 Require each exit from OSC to Auxiliary Building "ue preceeded by a briefing on task to be done and radiological conditions expected when applicable.
5.12.12 Coordinate Health Physics activities for assessment and repair teams in accordance with RP/0/B/5000/12.
(O 5.12.13 Post blanket dose extension values.
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ENCLOSURE 5.13 ,
OSC HEALTH PHYSICS SUPERVISOR CONTINUING RESPONSE 5.13.1 Maintain routine contact with TSC S&C Coordinator to provide update on OSC activities and to receive plant status reports.
5.13.2 Obtain thru Support Functions Coordinator additional dosimetry / protective clothing / emergency kit items necessary to support OSC activities.
5.13.3 Coordinate OSC activities requiring pre-planning.
~
5.13.3.1 Emphasis should be placed upon:
Dosimetry (Whole Body & Extremities)
Protective Clothing Route to and from task Respiratory equipment .
Need for Buddy System because of safety hazard (radiological and non-radiological)
Establishing dose limits and/or dose rate considerations for high exposure jobs on unknown situations
.. s Communications equipment Additional monitoring instrumentation 5.13.4 Monitor dose rate in OSC. Should General Area reach 5 mR/hr.,
initiate discussion with S&C Coordinator on the need to evacuate the OSC, should dose rate be expected to continue.
5.13.5 All RE-ENTRY efforts should consider the special problems that may exist:
High geana fields Increased Beta fields High Contamination levels High airborne rad levels f
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Page 1 of 2 HP/0/B/1009/09 l C'- ENCLOSURE 5.14 j f RESERVE PERSONNEL / PERSONNEL MONITORING LEADER RESPONSE , I 5.14.1 Assemble all Health Physics personnel not initially required for i
emergency response. Non-essential personnel should be evaluated for '
use in the emergency.
I 5.14.2 Identify personnel and/or personnel monitoring teams for the '
following locations.
5.14.2.1 Field Monitoring 5.14.2.1.1 Select eleven (11) Catawba Nuclear Station Field Monitoring Team (FNI) members to be organized as follows: _
Team Call Sign Number of Members Transportation Alpha 2 Land Vehicle Bravo 2 Land Vehicle Charlie 2 Land Vehicle Delta 2 Land Vehicle Echo 1 Helicopter Foxtrot 2 (Onsite Teem) 5.14.2.1.2 Instruct FMT's to complete checkout steps 7s from HP/0/B/1009/04, Environmental
,\ a' Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear
, Station.
i 5.14.2.2 All on-site assembly areas are identified in Station Directive 3.0.7.
5.14.2.3 PAP Area.
5.14.2.4 Evacuation Facility (Alpha or Bravo). Two monitoring teams if both locations are used.
, 5.14.3 Initiate, as necessary, HP/0/B/1009/05, Personnel / Vehicle Monitoring for Emergency Conditions.
~
5.14.4 Initiate random monitoring of vehicles located in the upper and lower parking lots starting with vehicles nearest the affected unit. The i
monitoring team identified in Step 5.14.2.3 should be used for this purpose.
5.14.5 Coordinate with the TSC Surveillance and Control Coordinator on relocating personnel monitoring teams if background radiation renders normal monitoring locations unfit.
5.14.6 Supervise Health Physics efforts at the Evacuation Facility (s) as per
_ Reference 2.2.
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5.14.7 Provide direction to reserve Health Physics personnel:
5.14.7.1 Direct and control personnel in the staging area (DRC office in the Administration Building).
5.14.7.2 Coordinate with Surveillance and Control Coordinator to provide additional manpower, as necessary.
5.14.7.3 Coordinate with Support Functions Coordinator to provide additional manpower, as necessary. _
5.14.7.4 Direct activities of Field Monitoring Teams if relieved by CMC personnel.
5.14.7.5 Begin scheduling activities for Health Physics personnel.
5.14.7.6 Support OSC Supervisor with major activities as required.
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, HP/0/B/1009/09 -
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, ENCLOSURE 5.15 OSC RESPONSE PERSONNEL DOSE RECORD FORM Name: HP Badge No.:
Social Security No.: Exposure Class:
Birthdate: Age: Work Group:
- Quarterly Dose to Date: ares
- Yearly Dose to Date: aren Permissible Lifetime Dose to Date: aren Total Lifetime Dose to Date: ' ares Date/ Time Dosimeter Reading
- Quarterly Dose Total Comments Out In Out (area) In (area) m/
- Current Quarter Dose aren Plus Today's Dosimeter Dose area.
- Current Yearly Dose ___ area Plus Today's Dosimeter Dose area.
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HP/0/B/1009/09
. ENCLOSURE 5.16 j -
PROCUREMENT OF HELICOPTERS FOR AERIAL ENVIRONMENTAL SURVEILLANCE Inland Airways, Myrtle Beach, S.C., is under contract to Duke Power Company to furnish one helicopter upon request and an additional helicopter within six hours following notification. Once a helicopter is requested, there is a maximum elapsed time of three hours for the helicopter to arrive at Catawba Nuclear Station or other dispatched locations. ,
Helicopter service is limited to daylight hours and adequate flying weather.
The helicopters will hold three people, the pilot and two passengers. To I
perform surveys, instrumentation may limit the passenger space.
To obtain helicopter (s) for emergency service contact:
Office Home I NOTE: These contacts are in Duke Power Company Transmission Dept., Line w
., Division.
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. 6 Form 34731 (R9 86) (1) ID No.HP/0/8/1009/16 DUKE POWER COMPANY Change (s) O to
, PROCEDURE PROCESS RECORD 1 incorporated PREPARATION ,
. (2) STATION Catawba (3) PROCEDURE TITLE Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release !
(4) PREPARED 8Y '#I A'^#'A DATE ' b /87 (5) REVIEWED 8Y ~ -
a- DATE '
//" // /
Cross Disciplinary Review 8y N/R '
4
'. /
(6) TEMPORARY. APPROVAL (if Necessary)
By (SRO) DATE By - -
DATE (7) APPROVED 8Y _ DATE ! $
(8) MISCELLANEOUS Reviewed l Approved 8y DATE
') _ Reviewed / Approved By DATE -
(9) COMMENTS (For procedure reissue Indicate whether additional changes, other then previously approved changes, are included.
Attach additional pages,if necessary.) ONo ADDITIONAL CHANGES INCLUDED.9 4 1119Yes (10) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED ll (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate?
O Yes O N/A Listed enclosures attached?
O Yes O N/A Data sheets attached, completed, dated and sicnod?
Oyes O N/A Cherts, graphs, etc. attached and properly dated, identif'wd and marked?
O /es ON/A Acceptance criteria met?
VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED DATE
('
(14) REMARKS (Attach additional pages,if necessary.) !
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CATAWBA NUCLEAR STATION DISTRIBUTION OF POTASSIUM IODIDE TABLETS IN THE EVENT OF A RADI0 IODINE RELEASE l.0 PURPOSE This procedure provides information necessary to distribute Active Potassium Iodide (KI) tablets to in-plant personnel in the event of a release of radiciodine. Also, it outlines storage and supply information to assure sufficient quality and quantity of thyroid blocking material.
2.0 REFERENCES
2.1 HP/0/B/1001/21, Operation and Calibration: Canberra Fastscan-Body Burden Analysis 2.2 System Health Physics Manual 2.3 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases of Radioiodine 1977 2.4 NCRP Report No. 65; Management of Persons Accidentally Cottaminated With Radionuclide 1980
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v_./ 2.5 NUREG 0654 2.6 May 16, 1983 letter from L. Lewis to C. T. Yongue.
Subject:
Oconee Nuclear Station HP Procedure HP/0/B/1009/12,-File: GS/05-750.01.
i 3.0 LIMITS AND PRECAUTIONS 3.1 KI shall not be administered to a person who knows he (she) is allergic to iodide.
4
, 3.2 If a person has an allergic reaction or has severe side effects f
from KI tablets, they should stop taking KI tablets and consult a doctor or public health authority for instructions.
l . 3.3 Personnel shall be advised not to deviate from the prescribed dosages i
and dosage rates.
3.4 Best results are achieved when KI tablets are administered immediately (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) after an exposure, although administration as late as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an emergency will provide some protection.
3.5 Discolored or disfigured tablets, tablets that have reached the expiration date listed on the bottle, and bottles of KI with loose tops shall be discarded.
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' 3.6 Hands must be free of radioactive contamination prior to handling the
! KI tablets. .
4.0 PROCEDURE 4.1 Responsibilities For Distribution 4.1.1 The Station Health Physicist, in conjunction with available medical advice, shall control the distri-bution of KI tablets.
4.1.2 Persons suspected of having been in the affected area prior to the detection and during the release, persons present in the affected area and persons who will enter the area while a significant amount of radioiedine is present will be instructed by the Health Physics Supervision to immediately register at the KI distribution center (for example, the Technical Support Center).
4.1.2.1 A significant amount of radiciodine for short duration in-plant exposure is that amount taken into the body that would result in a dose of 10 res or more. For example, exposure to approximately 700 weighted MPC-hours, or 4.5 x 10 e uCi/al airborne I-131 for one hour,
-s would result in a dose of 10 rem.
s ,/; 4.1.2.2 A significant amount of radioiodine for emergency workers in the field is 70 MPC (6.1 x 10 7 pCi/al) I-131.
4.2 Registration of persons exposed to a signif'icant amount of radio-iodine.
4.2.1 When persons notified by Health Physics arrive at the distribution area, record appropriate data per Enclosure 5.1.
4.2.2 With the approval of the Station Health Physicist, the Health Physics representative shall give one (1) tablet to each person and instructions concerning the use of the tablet. Then issue to each person one bottle containing nine (9) KI tablets, and the package insert for the use of the tablets (refer to Enclosure 5.2 for an example of the General Manufacturers Guidelines).
4.2.2.1 Tablets are to be taken only as directed, one (1) tablet per day for the length of the emergency.
4.2.2.2 After the initial dose of KI, subsequent doses will be taken daily. Tablets should be taken as r- ,
near a 24-hour schedule as possible.
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- placed upon the proper use of these i- tablets.
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4.2.3 Tablets removed from a full bottle of KI should be stored in a 10 al plastic. vials. The expiration date on the bottle -
from which the tablets were taken and the name of the Health Physics representative shall be recorded on the 10 ml vials. Tablets stored in 10 ml plastic vials should then be used for single tablet initial issuance of KI to affected persons.
4.2.4 As directed by the Field Monitoring Coordinator (FMC) or-the S&C Coordinator, team members shall ingest one (1) tablet of Potassium Iodide.
4.2.4.1 The FMC and/or S&C Coordinator will provide the information for Enclosure 5.1 and will ensure that distribution of KI per Step 4.2.2 is accomplished by team members.
4.3 Thyroid Burden Analycis Following Radiciodine Exposure 4.3.1 All persons-receiving KI tablets should receive a thyroid
- scan. If the number of people render this step impractical, the Count Room Supervisor will select a representative sample of persons who received KI tablets from Enclosure 5.1.
NOTE: Distribute XI before performing thyroid scan.
Thyroid scans immediately after an accident
\q,1 could lengthen KI distribution time and cause .
confusion among personnel.
4.3.2 Records of thyroid scan shall be maintained.
4.4 Storage Requirements 4.4.1 There are three major storage requirements:
4.4.1.1 Store in a temperature range of 59'F to 86*F.
4.4.1.2 Store in a low humidity area (avoid di. rect exposure to liquids).
4.4.1.3 Store in an area protected from exposure to light.
4.4.2 Upon receiving a shipment of KI tablets, boxes shall be opened as soon as possible and bottles examined to ensure
, that an air-tight seal has been maintained. Bottles shall be returned to boxes, and boxes shall be sealed shut to avoid exposure to light.
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[ 4.4.3 To ensure a sufficient supply of tablets, a minimum of 1,000 bottles with 14 tablets per bottle should be ,
maintained on site.
4.5 Shelf Life and Changeout of KI Tablets 4.5.1 Thyro-Block TM tablet bottles are labeled with an expiration date at the factory. As tablets reach the expiration dates, the tablets shall be discarded.
4.5.2 Replacement tablets should be ordered at least three (3) months prior to the date of expiration listed on the bottles of KI.
4.5.3 Upon receiving a shipment of KI tablets,-supplies should be shifted in order to use older tablets before new tablets.
5.0 KNCLOSURES 5.1 Sample of Potassium Iodide Tablet Distribution Data Sheet 5.2 Manufacturers Guideline's for Thyro-81ock " Tablets and Solution
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' Enclosure 5.1
[~~~) POTASSIUM IODIDE TABLET DISTRIBifrION DATA SHEET ar .
BADGE DATE & TIME OF DATE & TIME OF NUMBER NAME DEPARDtENT {
SUSPECTED EXPOSURE INITIAL ISSUANCE l
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HP/0/B/1009/16 Enciesura 5.2 Page 1 of 2
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Posent peekage sneest For THYRU BLOCK" POTASH 100:04 gwenounced poe> TASS +em EYteh4ree teetweviates:lut TABLETS and A0LUTIN U.S.P.
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU. IN A AADIATION EMERGENCY, RADIOACTIVE IODINE COULD Bh". .
RELEASED INTO THE AIR. POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU.
IF YOU ARE TdLD TO TARE THIS MEDICINE.TAKE IT ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. MORE WILI. NOT HELP YOU AND MAY IN-CREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUC !! YOU KNOW YOU ARE ALLERGIC
- 1D JODIDE. ISEE SIDE EFFECT8 BELOW.I
) . - - INDICATIONS
, THYROID DLOCKING* IN A RADIATION EMERGENCY
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DIRECTIONS FOR USE 1
. Use only as directed by Stsee er loosipublic health authorities la the event of a radiadon emergency.
I DOSE Te!dete: ADULTS AND CHILDREN 1 YEAR OF AOE OR OLDER: One (1) tablet once a day.Crushforsmall@11 BABIES UNDER EAR OF AGE:
One. half (Its tablet enee a day. Crush fireL Se!ution: ADUL'11 AND CHILDREN I YEAR OF AOE OR OLDER: Add 6 drope to one.
half glass of thi nid and drink each day.
BABIES UNDER 1 YEAR OF AGE:
Add 3 drops le a smaR ameest of Ik luid onceaday. ~
fee e.7 dasere forme Take for 10 days unless directed otherwien by Sta;e or local public heekh setheriuse.
Store at c~. trolled room temperature between 16* and 30'C (fet*
to 86*F). Keep container tightly elooed and protect from light De nct see the solution ifit appears brownish la the nw Je of the bottle.
- l WARNING Potasslum iodide sheaf not be used by people eCerste te ledide.
Racp out of the reach of children. la esse of overdose er aDergic reaction, rent art a physicina er the public health authority.
DESCRIPTION
/.. '
Each TilYlto.!!!/)CKTM TABLFT containe 130 mg of potassium lodide.
U Each dre.p of THYROBLOCKWSOLUTION conteine 21 ma of -
potasniem iedide.
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HP/0/B/1009/16 l Enclosure 5.2 i Page 2 of 2 s .
HOW POTASSIUM 10010E WORKS .
Certain forme ofiodios help your thyreld gland work right. h!oet 2"ople get the ledia6 by need from foods like lodiud salt or i neh. The thyroid see " store" er hold only a certain amount of ledine.
In a redientes emergency, radioactive lodine may be released in the air. This meterial may be breabd or swanowed. It may enter the thyroid gland and damage it 'lle damage would pro, bebly not show itself for years. Children erv amet likely to have thyroid damage, if you take pesaseless ledide, it wiu fill.up your thyroid gland.
This reduces the chance that harmful radiunctive iodine wiu enter the thyroid gland.
WHO SHOULO NOT TAXE POTAS$10M 100:0E ne only people who should not take potassium iudido are people .
who haos they are eDergie to lodide. You niey take potesnium lodida even if you are taking medicines for a thyroid problem (for eaaraple, a thyroid hermone or entithyroid drugt. Pregnant and nursing wessen and bebies and children may also take t!ar drug.
HOW AND WHEN TO TAKE POTASSIUM 10010E Potassium ledido should be takes as soon as poem 1,le e4.r public health officials teu you. You should take one does every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. More will not help you because & thyroid can " hold" on.
13 Emited annouste of iodine. Larger doses wiU increase the risk of side effects You wiu probably be told not to take the drug for more thaa 10 days.
SIDE EFFECTS UeueUy. side effects of potassium lodide happen wl.ca people A. ,
take higher doses for a long time. You should be careful not to W tene more than the recommended does or take it for longer than you are told. Side effecte are unlikely because of the low duee sad the short thee you wiu be saldag the drug.
Puesible side effects laelude ekla tsahoe, swelling of b seUvaty glands, and
- ledisse"(metallic taste, burning mouth and thrvet, eers teeth and guana, symptosas of a head cold, and scan 4hnes esemach upset and diarrheat. .
A few have as allergic reacties with more serique symp, te:se, c6ald be fever and joint paine, or aweuing of perte of the face and body s'id at times severe ehertne=e J brasth requit.
lag immediate medical ettenties.
Taking ledis;e may rarely enese everactivity of the thyrnid adond. underactivity of b thyroid gland, or enlargement of b thyroid gland Igoiters.
WHAT TO 00 IF SiOE EFFECTS OCCUR If the eide effects are severe or if you have en euererw n artiun.
etop taking potassium Iodide. Then, if ponWble, cou a doctor or pubbe heelth authority for lastructions.
HOW SUPPLIED .
TilYMOBLOCKW TABLETS (Futanium I.idiJe. lj.S.I'J bot-Lies ef 14 tab'. eta (NDC 0037 0472 20J Esch white. nound. ecored tablei contains 130 eng potassium iodide.
TilYllOUI.0CKm SOLUTION iPotassium ladid, No!stion.
U.S.P.I 30 n.' ti 11. osJ ligl.t resiatant, meesur 4 drop dispensing unite 'NDC 0%7 4267 253. L*ech drop contains 21 rng potanium
- riitde WALLACg LA80RAf 0Rit. -
(Jewsme. of I CAP 1f 84W ALLACE. INC Cua.6any New Jett.ey oust i D;
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' Form 34731 (R946)
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t (1) lO No. RP/0/B/1009/17 DUKE POWER COMPANY Change (s) O to y PR,0CEDURE PROCESS RECORD o jncorporated k .> PREPARATION CATAWBA NUCLEAR STATION (2) STATION (3) PROCEDURE TITLE POST-ACCIDENT CONTAINMENT AIR SAMPLING SYSTEM (4) PREPARED BY
- t- e DATE '
(5) REVIEWED BY > DATE 7 g '
( / /
Cross Disciplinary Review By N/R --
_g (6) TEMPORARY APPROVAL (if Necessary)
By (SRO) DATE By DATE (7) APPROVED BY dL_* DATE I
.t (8) MISCELLANEOUS 8 1
Reviewed / Approved By DATE ,
- ~ .
\;j' Reviewed / Approved By 17 ATE .
(9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously approved changes, arejncluded.
Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. Oyes E!INo (10) COMPARED WITH CONTROL COPY DATE
, i COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or fi!!ed in N/A or N/R, as appropriate?
O Yes O N/A Listed enclosures attached?
Oyes O N/A Data sheets attached, completed, dated and signed?
Oyes O N/A Charts, graphs, etc. attached and properly dated, identified and marked?
O Yes O N/A Acceptance criteria met?
VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED DATE i
]
\14) REMARKS (Attach additional pages,if necessary.)
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION POST-ACCIDENT CONTAINMENT AIR SAMPLING SY$ TEM 1.0 PURPOSE To describe a method for obtaini g a containment air sample after a nuclear reactor accident using the Nuclear Post-Accident Containment Air Sampling System (PACS).
2.0 REFERENCES
2.1 CP/0/B/8800/13, Chemistry Procedure for the Preparation of Thiosulfate Solution for Post Accident Gas Sampling 2.2 HP/0/B/1000/06, Emergency Equipment Tunctional Check and Inventory 2.3 HP/0/B/1009/06, Alternative Methods for Determining Dose Rate Within the Reactor Building 2.4 OP/1/A/6450/10, Containment Hydrogen Control Systems n 2.5 OP/2/A/6450/10, Containment Hydrogen Control Systems 2.6 RP/0/B/5000/12, Control of Assessment and Repair Teams 2.7 Duke Power Company Nuclear Station Post-Accident Containment Air Sampling System II Manual, File No.: CNM-1210.09-0218001 2.8 NuReg-0737 II.B.3 Post-Accident Sampling Capability 2.9 Post-Accident Containment Air Sampling System - Qualifications, File No.: CN-134.10 3.0 LIMITS AND PRECAt.TrIONS 3.1 Exposure from the samples have the potential to be very high; therefore, appropriate surveillance and control of personnel shall be provided by Health Physics when taking samples. Entry and exit
, route to sample panel and control panel area are to be determined
- "oy Health Physics surveys.
- 3.2 The Recire Puso shall never be used at any pressure other than 0" of Hg.
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t 4 3.3 Noving the Selector switch (#9) free one mode to another stops all current system operations. Depressing the Activate pushbutton (#10) starts operation of the newly selected mode.
3.3.1 Numbers within parentheses (ex. #9) are locations on
- Enclosure 5.6 and on the control panel.
3.3.2 (SP) to the left of the enclosure step number requires a person to go to the sample panel.
3.4 The Radiation Monitor (#3) on the control panel should provide background levels of radiation prior to, during, and after sampling, and an indication of contamination within the system or panel for progressive samples. _
3.5 If the needle of the Radiation Monitor (#3) exceeds the upper and of the meter scale while the lower scale (mR/hr) is being used, immediately tuza the selector knob to the higher scale (R/hr).
3.6 If the Radiation Monitor (#3) reading cannot be reduced below 10 R/hr do not return to the sample panel, but contact the Reserve Personnel / Personnel Monitoring Leader (RPPM) immediately for further instructions.
i 3.7 If problems with the Radiation Monitor (#3) are evident (e.g. no
,- indication of radiation on the meter), notify the RPPM and rely on (v.. S ;
Health Physics surveys to determine access to the sample panel.
3.8 If thiosulfate comes in contact with the skin during preparation, transferal or dilution, wash the affected area as soon as possible
]j with soap and lukewarm water. Consult station nurse for further 4
instructions.
, 3.8.1 Do not use NA0H solution and/or sodium thiosulfate crystals (Na:S 0s-5H 0) if the expiration dates on their labels have been exceeded, i
4 3.8.2 Chemistry should prepare NAOH solution and sodium thiosulfate crystals (Na:S 0s-5H ) per Reference 2.3.
3.9 Dispose of contaminated syringes, septums, rubber gloves, etc. , in i appropriate radioactive waste receptacles.
3.10 Individuals that have been trained on this procedure are the individuals qualified to use this procedure. Individuals shall be trained and tested every six (6) sonths and documented in Reference 2.9.
3.11 Due to the nature of this procedure, a Working Copy shall be used
- to ensure compliance.
l 4.0 PROCEDURE i .
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4.1 yollow steps on the RPPM PACS Checklist (Enclosure 5.1).
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4.2 Follow steps on Post-Accident Containment Air Sampling Set-Up .
(Enclosure 5.2).
4.3 Follow steps on Taking Post-Accident Containment Air Samples !
(Enclosure 5.3) and complete Post-Accident Containment Air Sample i Data Sheet (Enclosure 5.4) for each containment air sample request. '
4.3.1 If applicable, determine containment dose rate per Reference 2.3.
4.4 Ensure the isotopic analysis of each containment air sample and its associated Enclosure 5.4 are submitted to the Station Health 3 Physicist. !
~
4.5 Follow steps on Post-Accident Containment Air Sampling Shut-Down (Enclosure 5.5).
4.6 File enclosures and associated calculations in the Health Physics Satellite Master File, 4.7 Connect an appropriate transfer container and drain the sump by turning the Key Lock switch (#48) to Sump Pump. Accompanying power light should illuminate.
4.8 Reinventory OSC kit after use per Reference 2.2.
?' 5.0 ENCIDSURES *
. A.
5.1 RPPM PACS Checklist 5.2 Post-Accident Containment Air Sampling Set-Up 5.3 Taking Post-Accident Containment Air Samples 5.4 Sample of Post-Accident Containment Air Sample Data Sheet 5.5 Post-Accident Containment Air Sampling Shut-Down 5.6 Post-Accident Containment Air Sampling Control Panel (PACP) Diagram 5.7 Post-Accident Containment Air Sampling Sample Panel (PASP) Diagram 1 . 5.8 Incation of PACP and PASP Y
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ENCLOSURE 5.1 .
RPPM PACS CHECELIST i Date/ Time / Unit Check Action 5.1.1 After completion of Team Personnel Lists of Reference 2.6, select at least one qualified individual based on PACS training and NSA training (refer to Reference 2.9 Health Physics file 134.10-4 or the OSC Health Physics Notebook).
Select another individual to accompany the other. Consider:
- Age
- Accumulated exposure
- Sex
- Ability to carry 100 lbs. together
- Respiratory printout 5.1.2 Consider the following for the PACS:
- MSA SCRA's
- Operable breathing air hookups
- Throat sikes
,r',: - Portable instrumenta (PIC-6A, Teletector) 4
.)
- High range dosimetry .
- Extremity dosimetry
- To and from route to PACS ENF-2 Control Roon readout 1 EMF-1 Control Room readout
- Flashlight
- - Radios
- Control Points 5.1.3 Request assistance in acquiring needed equipment from the Technical Support Center (TSC).
5.1.4 Prepare Ccuating Room to receive sample. Consider:
l
- RCZ setup
- Shielding
- Disposal of sample
- MCA setup i - Personnel
- Dosimetry (high, extremity) 5.1.5 If necessary, complete dose extension forms.
5.1.6 Obtain a High Radiation Area key.
i 7 5.1.7 Have equipment prepared for conditions at PACS. Consider:
- Taping wheels on porta pig
- Bagging loose items 4
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- T HP/0/B/1009/17 ENCIDSURE 5.1 ,
RPPM PACS CHECKLIST Check Action 5.1.8 Inform selected individuals of precautions, Safety and Health Physics concerns and then have them obtain the sample.
5.1.9 Remain in contact with the technicians throughout the sampling. They should report problems and data as they get them.
~5.1.10 Complete Enclosure 5.4 and route to Counting Room before the analysis takes place.
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a ENCLOSURE 5.2 POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP Date/ Time / Unit Check Action 5.2.1 Inform the Shift Supervisor that gas sampling will be performed and that one Hydrogen Analyzer will need to be inoperable during sampling. Request that Operations complete the Setup Section for Post-Accident Containment Air Sampling of procedure OP/1/A/6450/10_ or OP/2/A/6450/10 (see Reference 2.4 or 2.5).
5.2.2 After notification that Operations has completed the PACS Setug Section, obtain the Post-Accident Containment Air Sampling Equipment located in the OSC Emergency Kit.
The equipment should be the following:
Quantity Ites 4
1 - Post-Accident Control Panel (PACP) Key 2 - 500 al Nalgene bottle labeled "2.42 x 10,3H Na0H" 2 - vials of .3 en Na:S 03 - 5H 0
- i 2 - 500 al Nalgene bottle labeled " Iodine Sample"
'2 / 2 - 100 al gas bomb ,
2 - 60 ml Nalgene bottle - labeled " Iodine Sample" 1 - Stop watch 5
5.2.3 Prepare thiosulfate solution by adding one vial of i
Na:S3 0s-5H 0 to one bottle of Na0H. Shake vigorously until all of the crystals are dissolved. Relabel as
" Thiosulfate".
5.2.4 Verify that the Selector switch (#9) is in the Off position. '
- 5.2.5 Nove the System Purae toggle switch (#20) to the Normel
- position.
1 5.2.6 Nove the Gas Purae toggle switch (#16) to the center position.
5.2.7 Nove the Refill toggle switch (#24) to the Off (down) position.
5.2.8 Turn Key Lock switch (#48) to Power On. Accompanying power light should illuminate.
t 5.2.9 Turn the Radiation Nonitor (#3) On by moving the toggle
, switch (located below the meter) to the Ug position.
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- ENCLOSURE 5.2 POST-ACCIDENT CONTAINHENT AIR SAMPLING SET-UP Check Action 5.2.10 Turn the Radiation Monitor (#3) selector to BATT and verify that the needle is in the " red test region" on the right end of the scale. If reading is below the test region, rely on Health Physics surveys to deteomine access to the sample panel.
5.2.11 Select the appropriate rate so that the needle is on the meter scale by first turning the selector knob to higher scale (R/hr) and, if necessary, to the lower scale (nR/hr).
(SP) 5.2.12 Open all four (4) service valves DI, VI, Na and TS by turning handles one-quarter turn counterclockwise. The DI, VI, and Na valves are located on the outside upper left side of the sample panel, and the TS valve is located on top of the sample panel.
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ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Date/ Time / Unit Check Action (SP) 5.3.1 Pour thiosulfate solution into the thiosulfate tank, located on top of the sample panel. Leave the cap off of the thiosulfate tank after transferring the thiosulfate solution (Refer to Section 5.2.3 for preparing more solution).
(SP) 5.3.2 Attach an " Iodine Sample" bottle to the sample panel by inserting the plastic hose into the bottle located on i
the lower left side of the panel. Disconnect the quick connect connector on the lower side of the sample panel and replace with a gas bomb.
5.3.3 Turn Key Lock switch (#48) to on,.
.. . 5.3.4 Turn Selector switch (#9) to System Purne.
V 5.3.5 Depress Activate pushbutton (#10).
5.3.6 Depress Evac pushbutton (#17) (Evac light should illuminate) and watch the vacuum gauge (#6) drop to l -25" of Ha.
4 5.3.7 When the vacuum gauge (#6) reaches -25" of Ha, depress the Stop pushbutton (#19).
,, 5.3.8 Press down the Gas Purae toggle switch (#16) and watch the vacuum gauge (#6) swiftly rise to +5" of Hz.
5.3.9 When the vacuum gauge (#6) reaches +5" of Ha, return toggle switch (#16) to center position and depress the Stop pushbutton (#19).
5.3.10 Depress the Evac pushbutton (#17) and watch the vacuum gauge (#6) drop to 0" of Hz.
5.3.11 When vacuum gauge (#6) reaches 0" of Ha, depress the Stop pushbutton (#19).
l 5.3.12 Depress M pushbutton (#18) and wait for thirty (30) i-seconds.
i
, 5.3.13 Depress Stop pushbutton (#19).
5.3.14 Press up the Gas Purae toggle switch (#16) and wait three 4
(3) minutes.
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,,, CATAWBA NUCLEAR STATION 4 .\ HP/0/B/1009/17 ENCLOSURE 5.3 .
TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Check Action 5.3.15 Return.the toggle switch (#16) to the center position.
5.3.16 Turn Selector switch (#9) to Solution Chanseout. l 5.3.17 Record the Radiation Monitor (#3) reading as a background reference: R/hr 5.3.18 Depress Activate pushbutton (#10). -
5.3.19 Depress Flush pushbutton (#22) and hold five (5) seconds.
, 5.3.20 Depress Purge pushbutton (#23' , and hold ten (10) seconds.
5.3.21 Depress Empty pushbutton (#21) and hold for thirty (30) seconds.
5.3.22 Nove the Refill toggle switch (#24) to ON (up) position and wait two (2) minutes and then move the toggle switch back to the Off (down) position.
(, i 5'.3.23
~s Turn Selector switch (#9) to Dilution Volume' Evacuation.
5.3.24 Depress the Activate pushbutton (#10) and watch the vacuum gauge (#6) drop to -25" of A .
5.3.25 When the vacuum gauge (#6) reaches -25" of Ha, turn Selector switch (#9) to Sample Recire.
5.3.26 Depress Activate pushbutton (#10) and wait for five (5)
- minutes.
5.3.27 Record sample line temperature reading (#4): 'C 5.3.28 Record sample inlet line pressure (psis) reading (#5):
Psig
- 5.3.29 Depress Sample pushbutton (#11) and wait for ten (10) i seconds.
5.3.30 Depress Trap pushbutton (#12) and wait for thirty (30) seconds.
5.3.31 Enter time of sample trap: (ex. 1355) 5.3.32 Turn Selector switch (#9) to Sample Dilution.
/ - 5.3.33 Depress Activate pushbutton (#10).
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5.3.34 Depress Slow pushbutton (#13) and watch the vacuum gauge (#6) rise to 0" of Ha.
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TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Check Action 5.3.35 When the vacuum gauge (#6) reaches 0" of Ha, depress the Stop pushbutton (#14).
5.3.36 Depress the Recire pushbutton (#15) and wait for five (5) minutes.
(SP) 5.3.37 Disconnect the quick connect on the gas bomb outlet side, wait five (5) seconds and disconnect the-gas bomb.
Replace the quick connect connector.
5.3.38 Depress the Stop pushbutton (#14).
5.3.39 Turn Selector switch (#9) to solution Chanaeout.
5.3.40 Depress Activate pushbutton (#10). 1 5.3.41 Depress the TS Sample pushbutton (#25).
5.3.42 Depress and hold the Empty pushbutton (#21) for five (5)
^ -
minutes. Thiosulfate should transfer into the TS sample
,j bottle.
5.3.43 Depress h pushbutton (#23) and hold thirty (30) seconds.
5.3.44 Depress TS Sample Grab pushbutton (#26).
5.3.45 Turn Selector switch (#9) to System Purae.
5.3.46 Depress Activate pushbutton (#10).
5.3.47 Repeat steps 5.3.6 through 5.3.15 as needed until no noticeable decrease is observed on the Radiation Monitor
(#3) from one purge to the next. Check blank in steps 5.3.6 through 5.3.15 each tire tsc step is performed.
5.3.48 Record the Radiation Morij i (#' reading: R/He 5.3.49 Turn Key Lock switch (#48) to Off. _f (SP) s.3.50 Disconnect and tightly cap the " Iodine Sample" bottle.
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. .. Page 4 of 4 DUKE POWER COMPANY CATAWBA NUCI. EAR STATION HP/0/B/1009/17 ENCI.0SURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Check Action l 1
5.3.51 Determine the Thiosulfate Sample Volume (TSV) and record i this value as TSV: el j l
5.3.52 Using standard chemistry laboratory techniques and under a '
sample hood, transfer 50 al of the " Iodine Sample" into the 60 ml Nalgene bottle. Contact Radwaste Chemistry for instructions on disposal of excess sample.
5.3.53 Place the 60 al " Iodine Sample" bottle and the gas bomb into a shielded container as needed.
5.3.54 Using a monitoring instrument (such as the R02A or PIC-6A) take a contact dose rate reading on the top of the gas bomb and on the side of the " Iodine Sample" bottle:
R/hr gas bomb, R/hr " Iodine Sample" 5.3.55 Transfer the " Iodine Sample" and gas bomb to the Health Physics Counting Room for isotopic analysis.
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.. CATAWBA NUCLEAR STATION i HP/0/B/1009/17 ENCLOSURE 5.4 .
SAMPLE OF POST-ACCIDENT CONTAINMENT AIR SAMPLE DATA SHEET Date/ Time: / Unit Prepared By: Emergency - Drill (Circle One)
First Radiation Monitor Reading from 5.3.17 R/hr Sample Line Temperature from 5.3.27 *C Sample Inlet Line Pressure from 5.3.28 psis Sample Trap Time from 5.3.31 Second Radiation Monitor Reading from 5.3.48 -
R/hr contact reading on gas bomb from S.3.55 R/hr (Top)
Contact reading on " Iodine Sample" bottle from 5.3.55 R/hr (Side)
Containment Sample Volume --
293*K (14.7 psig + psig)
CSV = 1.4 al X (273'C + 'C)*K 14.7 psig j = al at standard temperature and pressure Section volume of CSV trapped in " Iodine Sample" bottle --
50 al X 1.0101 = al SV I= al (CSV) X al (TSV) where: 50 mi sample size + Thiosulfate Sample Volume from 5.3.51 1.0101 = 1 + .99, thiosulfate is 99% efficient for removing iodine Section volume of CSV trapped in gas bomb --
SVg= al (CSV) X .009 =_ al where: .009 = 100 al gas bomb + 11194 al volume of dilutica i
Station Health Physicist Date
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Page 1 of 1 DUKE POWER COMPANY CATAWBA NUCIEAR STATION
' HP/0/B/1009/17 ENCLOSURE 5.5 .
POST-ACCIDENT CONTAINMENT AIR SAMPLING SHUTDOWN Date/ Time / Unit Check Action 5.5.1 Turn Seles:or switch (#9) to Oy.
5.5.2 Turn Radiation Monitor (#3) Off.
(SP) 5.5.3 Replace the top to the TS tank. -
(SP) 5.5.4 Close all four (4) service valves DI, VI, N2 and TS by turning handles one-quarter turn clockwise.
5.5.5 Request that Operations complete the Shutdown Section for Post-Accident Containment Air Sampling of procedure OP/1/A/6450/10 or OP/2/A/6450/10 (see Reference 2.4 or 2.5).
5.5.6 Notify Shift Supervisor of sampling completion and that the H Analyzer used during sampling is not required for sampling.
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"} HP/0/B/1009/17 ENCLOSURE 5.6 .
POST-ACCIDENT CONTAINMENT AIR SAMPLING CONTROL PANEL (PACP) DIAGRAM
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', ENCLOSURE 5.8 .
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Form 34731 (R946) ~ (1) ID No.HP/0/B/1009/18 DUKE POWER COMPANY Change (s) O to -
., PROCEDURE PROCESS RECORD 0 incorporated PREPARATION (2) STATION Catawba (3) PROCEDURE TITLE Offsite Dose Projections (4) PREPARED BY #* C 8 /l* / S~f DATE (5) REVIEWED BY DATE 82 Cross Disciplinary Re ew 8y N/R -
y (6) TEMPORARY APPROVAL (if Necessary)
By (SRO) DATE By DATE (7) APPROVED BY d' DATE I I (8) MISCELLANEOUS Reviewed / Approved By DATE
{j , Reviewed / Approved By DATE (9) COMMENTS (For procedure reissue indicate whether additional changes, other then previously approved changes, are included.
Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. %[Yes ONo (10) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate?
O Yes O N/A Listed enclosures attached?
- , O Yes O N/A Data sheets attached, completed, dated and signed?
Oyes O N/A Charts, paphs, etc. attached and properly dated, identified and marked?
Oyes ON/A Acceptance criteria met?
VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED DATE I
- 4) REMARKS (Attach additional pages,if necessary.)
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.- f HP/0/B/1009/18 DUKE POWER COMPANY CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTIONS 1.0 Purcose To describe a method for projecting dose commitment from a noble gas and/or iodine release, through the containment, the unit vent and/or the steam relief valves, during an emergency. -
2.0 References 2.1
'l HP/0/B/1000/10, Determination of Radiation Monitor Setpoints 2.2 HP/0/B/1009/06, Alternative Method For Determining Dose Rate Within The Reactor Building 2.3 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled Release of Liquid Radioactive Material l
2.4 HP/1/B/1009/17 Unit 1 Post-Accident. Containment Air Sampling System
.v -
2.5 HP/0/B/1009/21. Abnormal Unit Vent Sampling 2.6 CNS Technical Specification 3.6.1.2 2.7 Offsite Dose Calculation Manual (ODCM) i 2.9 Regulatory Guide 1.4 "
Assumptions used For Evaluating The Potential Radiological Consequences of a. Loss of Coolant Accident For Pressurized Water Reactors" 2.9 Regulatory Guide 1.109, "
Calculations of Annual Doses to Man From Routine Releases of Reactor Effluents For The Purpose of Evaluat-ing Compliance With 10 CFR Part 50, Appendix I" 2.10 NuReg-0396
- EPA 520/1-78-016. " Planning Bcsis For The Development of State and Local Government Radiological Emergency Response Plans In Support of Light Water Nuclear Power Plants" 2.11 NuReg-0654, FEMA-REP-1,Rev.1, " Criteria For Preparation And Evaluation of Radiological Emergency Response Plans And Preparedness in Support of Nuclear Power Plants" 2.12 Letter from F.G. Hudson, September 30, 1985, re: Release Rate Information for McGuire and-Catawba Nuclear Station (Files CN-134.10) 2.13 CatawbaNUC-0306)
Nuclear Station Class A Computer Model Validation (Files
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1 HP/0/B/1009/18 Page 2 3.0 Limits and Precautions 3.1 This procedure is an alternative method of dose assessment to th Catawba Class A Atmospheric Dispersion Model computer code.
3.2 This procedure applies to releases made from Catawba Nuclear Station only. Many of the values contained in this procedure ar site specific.
3.3 It is assumed that the whole body dose from an iodine release is very small compared to the thyroid dosel therefores iodine whole body dose is not considered here.
4 3.4 This procedure considers all releases to be ground level releas-f es and that meteorological data are 15 minute avera02s.
i 3.5 Once a zone has been added to the list of affected zones, it shall not be removed except under the direction of the Dose Assessment Coordinator.
3.6 Once the Crisis Management Center (CMC) has been activated, the doses calculated by the Technical Support Center (TSC) dose
-. assessment group, should be compared with those calculated by th CMC before an evacuation recommendation is made.
V ,
4.0 Procedure 4.1 Meteorology Assessment
! 4.1.1 Acquire the following information and record on the Dose Assessment and Meteorology Worksheets (Enclosures 5.1 and 5.2, respectively):
1 l 4.1.1.1 Lower tower wind speed (WS) in miles per hour.
4.1.1.1.1 Use upper tower wind speed if lower j tower wind speed is not available.
. 4.1.1.2 Upper tower wind direction in degrees from North l (North = 0 ).
i 4.1.1.2.1 Use lower tower wind direction if upper tower wind direction is not available.
4.1.1.2.2 If the wind speed or wind direction can not be obtained from plant sys-tems, obtain them from the National l Weather Service (phone 704-399-6000).
l If the NWS information is unavailable
'/ then obtain data from McGuire Nuclear
[ Station Control Room (73 or 78, then 875, then ext 4262, or 4263, or 4264)
__.- .a _ . _ . 1 -.__ _.-. _ __ . _ .. _ . _ _ _ _ _ _ _ . - _ . . _ . , - _ _ ,
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1; HP/0/B/1009/18 l Page 3 ,
4 4.1.1.3 Temperature gradient (L1T) in degrees centigrade 4.1.1.4 Using Enclosure 5.3, record the stability class based on 41T.
4.1.1.4.1 If the temperature gradient is unknown, the following applies:
If between 1000 - 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, use stability class DI If between 1600 - 1000 hoars, use stability class G.
4.1.1.5 If necessar>, use forecasted meteorological data for calculating doses due to changing meteorolog ical conditions.
i 4.1.2 Determgne the atmospheric dispersion paramters, X/Q (sec/m ), for .5, 2, 5 and 10 miles (record on Enclosure 5.1):
4.1.2.1 Using fl,T, determine the two hour relative
,/ concentration.value(C '
H i
4.1.2.2 Convert the Cg values to X/Q:
X/G = H WS 1
i 4.1.3 Using Enclosure 5.4 circle on Enclosure 5.1 the protective action zones (PA2), based upon wind speed and
- wind direction.
i 4.1.4 Recheck meteorology conditions approximately every 15 minutes to ensure that other sectors have not been
! affected.
4.2 Source Term Assessment - Steam Relief Valve (Enclosure 5.5) 4.2.1 Determine the Sub-Noble Gas Release Rates, SQNG(Ci/sec),
by the following method
SQ NG
= R/hr X 1 X LBM X CF Ci VOPEN lbm R/hr
,"", where l R/hr = EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, EMF 11, EMF 12, EMF 13 reading l V0 PEN = time the valve is open in seconds i
LBM = lbm released for the time the i
e 1ai- -.4- = ~ - *'% * . e. e
-, . - - - - - ~ ~ - - - - w-=, -----,---e-b-ww.. + e. v w, . , h-w w
. . . . l- ' .
_, - . HP/0/B/1009/18 3- Page 4 l .
valve was open CF = the correction factor per Enclo-sure 5.6.
4.2.2 Determine the Noble Gas Release Rate, Q #"
NG i
G ' NG( M 27) + SONG ( " '
- NG " SQ (EMF 29)
- 4.2.3 Determine the Iodine release rates Q g (C1/sec)
Og = Q I'*
NG
- where
- i. Irat = ratio of 1131eqv./Xe133eqv. from Enclosure 5.7 4.2.4 Record Q and Q g on Enclosure 5.1.
NG 4.3 Source Term Assessment - Containment (Enclosure 5.0) 4.3.1 Determine the Noble Gas Release Rate, QNG' "' "d on one of the following methodst
- 4.3.1.1 Based on an EMF reading, wherel .
v Q *
- NG "
wheret i
EMF = 39(L), if EMF 39(L) < 1E7 cpm, EMF = 39(H), if EMF 39tL) is offscale and ENF39(H) > 100 cpm,
- . EMF = 53A or 538, if EMF'9(H) is offscale, CF = the correction factor per Enclosure 5.9 LR = Leak Rate,(ml/hr),
by one of the following methods:
! based on containment pressure:
LR = RLR (from Enclosure 5.10) based on an opening in containment:
LR = Q1C (from Enclosure 5.11) based on design leak rate:
1 LR = 2.449E6 (Reference 2.13)
I i 4.3.1.2 Based on PACS sample, wherel N. ;
j Q ^ *
- NG "
- i wherel
> 4 6 e ,+. 4 e ,
-w=,,.e -+-u.,,- ,--.-,-3,,- --,-.,-w .m,.$
HP/0/B/1009/18
-\ Page 5 PACS = uCi/ml (Reference 2.4)
CF = 2.78E-10 CLllt, sec uCi LR = Leak rate, as determined in step
, 4.3.1.1 above 4.3.2 Determine the Zodine Release Rate O g(C1/sec) based on or of the following methods) -
Based on Q NG I 4.3.2.1 Qg=GNG
- I#**
where Q = Noble Gas Release Rate as determined in step 4.3.1 above Irat = ratio of 1131eqv./Xe133eqv. from Enclosure 5.7.
~
' / .
4.3.2.2 Based on EMF 401
! Q = /\ CPM x 9.82E-20 Ci hr min x LR Lipin sec al cpe where:
41, CPM = reading from EMF 40 Z1 min = the' time interval for EMF 40 ob-servation(normally15mgnutes).
i 9.82E-20 = 4.0E-5 uC1/com x .25 min /ft ,
(inverse o5 EMF flow rate) x 3.53E-5 ft /m1 x 1C1/1E6uct x 1hr/3600sec.
4.0E-5 = correlation factor for EMF 40 from Reference 2.'1.
l LR = Leak rate, as determined in step l 4.3.1.1 above i
4.3.2.3 Based on PACS samples Q g = PACS x CF x LR l wheret -
PACS = (uC1/ml) (Reference 2.4)
- CF = 2.78E-10 ELjr.
sec uC1 r-- --.----..,,,n, -
- . ,,.,, , , , ,, , ,n_n, ..p-,a nm.,-.--- ,..-,,.en,wn_, -,,,-.,.---n,_.n-_ _ . . _ . _ , , . , , - - - - , - - - - - - -
.-__ _ . , _~
< l
. l l
HP/0/8/1009/18
, , Page 6 LR = Leak rate as determined in step 4.3.1.1 above
, 4.3.3 Record GNG ""d 01 n Enclosure 5.1.
4.4 Source Term Assessment - Unit Vent (Enclosure 5.12) 4.4.2 Determine the Noble Gas Rei tase Rate, Q "' *** '
one of the follwing methodst NG 4.4.1.1 Based on as EMF reading, wherel
~
GNG = EMF x CF x CFM wherel EMF = 36(L) if EMF 36(L) < 1E7 cpr.
EMF = 36(H) if EMF 36(L) is offscale and EMF 36(H) > 100 cpm, EMF = 54 if EMF 36(H) is offscale, CF = the correction factor per Enclosure 5.1*
, ., CFM = unit vent flow rate (ft / min) 4.4.1.2 Based on unit vent sample, wherel QNG = Unit Vent Sample x CF x CFM-wheral Unit Vent Sample = (uC1/ml) per reference 2.5 CF = 4.72E-4 C1 min _al sec f t* uCi CFM = unit vent flow rate (f t 3/ min:
4.4.8 Determine the Iodine Release Rate, Q g(C1/sec), based on one of the following methodst 4.4.2.1 Based on G NG I Og=Qgg X Irat wherel Q o e as e ease ate as e erm ned ir NG =
step 4.4.1 above f- .
Irat a ratio of 1131eqv./Xe133eqv. from
- s/
Enclosure 5.7.
- 4.4.2.2 Based on EMF 373 e
- ?', Y ,*% '
e 4-a -
g Y '
HP/0/B/1009/18
- .. Page 7
/\ CPM X 1.11E-13 Ci min _ min x CrM = Q I 41 min sec ft" cpm where:
LiCPM = reading from EMF 37 41 min = the time interval for EMF 37 ob-serva t ion ( normally 15 minutes)3 1.11E-13 = 4.OE-5 uC1/ cpm x 0.1667 min /f t (inverse of EMF flow rate) x 1Ci/1E6uCi x 1 min /60sec.
4.0E-5 = correlation factor for EnF37 from Reference 2.1._
CFM = unit vent flow rate (f t /3 min) 4.4.2.3 Based on anit vent sample:
Og = Unit vent sample x 4.72E-4 Ci min _ml x CFM sec ft" uCi where Unit vent sample = (uC1/ml) (Reference 2.5)
( -
CFM = unit vent flow rate (ft / min 4.4.3 Record G NG and Qg on Enclosure 5.1.
4.5 Dose Assessment (Enclosure 5.1) 4.5.1 Determine the total Noble Gas and Iodine Release Rates (TQ NG and TQ g ) from all releases.
4.5.2 Determine the Projected Whole Body Dose Rate, DRwb (rem /hr), due to noble gases for .5, 2, 5 and 10 miles:
DRwb = 33.'6 rem m 3 x TQNG * *#U hr C1 4 . where:
33.6 is the adult whole body dose 5 "v'r'5""
factor from Reference 2.9 in rem a hr C1 4.5.3 Determine the Projected Whole Body Dose, Dwb(rem), due to noble gases for .5, 2, 5 and to milest l l
Dwb = DRwb X 2 hr l where:
dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period i !,
s- 4.5.4 Determine the Projected Thyroid Dose Rate, DRct(rem /hr),
due to iodine for .5, 2, 5 and to miles
--e=' +* .g a 4 e u. m ne
- - - -,er~.d.. y%_ --, ,. ,,_,.,,,-ry.,7_.,y_. . . - . . _ , . , . - , . _ - . . . . . , . - , , _ - , , , , _ . , _ . - , - . . , , , _ ._-.___y..,
3 l
HP/0/B/1009/18 Page 8 DRct = X/G x TQ g x 2.26E6 rem a j hr C1 wheret 2.26E6 is the child thyroid dose cogversion
, factor from Reference 2.13 in rem m
)
hr Ci 4.5.5 Determine the Projected Thyroid Dose, Dct(rem), due to iodine for .5, 2, 5 and to miles:
Det = DRct X 2 hr .
wheret dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period 4.6 Protective Action Recommendations (Enclosure 5.14):
4 .~ 6 .1 Record the next sequential report number.
4.6.2 Circle the PA2s and the actions for the current and pre-vious protective action recommendations.
, , 4.6.3 If the projected dose in a PA2 is < 1 rem whole body
) or < 5 rem thyroid, then recommend no protective action (action A).
4.6.4 If the projected dose in a PAZ is 1 - 5 rem whole body or 5 - 25 rem thyroid, then recommend evacuate l children and pregnant women and shelter others(action j B and E).
4.6.5 If the projected dose in a PAZ is > 5 rem whole body or > 25 rem thyroid, then recommend evacuate everyone (action C).
4.6.6 If the dose rate at the site boundary is >= 5.0E-4 rem /hr whole body, then recommend an Alert.
4.6.7 If the dose rate at the site boundary is >= .05 rem /hr whole body or >= .25 res/hr thyroid, then recommend a Sit Area Emergency if readings last 30 minutes.
4.6.8 If the dose rate at the site boundary is >= .5 rem /hr whole body or >= 2.5 rem /hr thyroid, then recommend a Sit Area Emergency if readings last 2 minutes.
4.6.9 If the dose rate at the site boundary is >= 1 rem /hr whol body or >= 5 rem /hr thyroid, then recommend a General Emergency.
. .s/
D
HP/0/B/1009/18 Page 9*
( , ,
5.0 Enclosures 5.1 Sample of Source Term and Dose Assessment Worksheet 5.2 Sam;1e of Meteoro1gy Worksheet 5.3 Two-hour Relative Concentration Factors (C g) 5.4 Protective Action Zones Determination 5.5 Sample of Source Term Assessment - Steam Relief Valves 5.6 EMF 26 EMF 27 EMF 29, EMF 29 or EMF 10, EMF 11. EMF 12, EMF 13 Noble- Jan Correction. Factor 5.7 1131eqv./Xe133eqv. Ratio 5.8 Sample of Source Term Assessment - Containment 5.9 Containment Noble Gas Correction Factor -
5.10 Cont ainment Leakage Rate versus Pressure 5.11 Containment Leakage Rate versus Pressure and Size Opening 5.12 Samp le of Source Term Assessment - Unit Vent 5.13 Unit Vent Noble Gas Correction Factor 5.14 Samp le of Recommended Protective Action Report t '.,
I
.J
DUKE POWER COMPANY CATAWBA NUCLEAR STATION
'l HP/0/B/1009/18
- Enclosure 5.1 Meteorology, Source Term and Dose Assessment Unit Report #
Reactor Trip / Projection based on data on /
(cate/ time) (date/ time)
Prepared By:
Meteorology Assessment Current E) Hypothetical Wino Speed sph Wind Direction degrees from Nor-Temperature Gradient (LST' C Stability Class A C D E F G
~
Miles .5 1 2 4 5 7 8 PAZ A0 B1 El AlC1D1F1 B2 A2 C2 D2 E2 F2 F3 A3 Total Source Term Assessment Current Hypothetical Steam Relief Containment Unit Vent Total (C1/sec)
Encl. 5.5 Encl. 5.8 Encl. 5.12 C1/sec + C1/sec + C1/sec = = TQ NG C1/sec + Ci/sec + C1/sec = = TQ 3
t..
Dose Assessment bd=X/Q us
<---< Adult whole body <---< >---> Child thyroid >-_->
Rhr --
thi Dome = 2 x DRwb = 33.6 x TQ X/Q 3 TO x 2.26E6 = DRet x E = Dot (rem) (rem /hr) (C1/se59 (sec/m ) (C!/sec) (rem /hr) (ret Distance miles
=E x = 33.6 x TQ gg .5 TQ x 2.26E6 = x E= _
2 x = 33.6 x TQ gg E TO x 2.26E6 = x E
E x __ = 33.6 x TO S TQ x E.26E6 = x t
=E x NG
33.6 x TO NC 10 TO x 2.26E6 = x E
E x = 33.6 x TQ 1 TO x 2.26E6 = x E
NG
8 x = 33.6 x TQ gg 4 TO x 2.2&E6 = x E
E x = 33.6 x TQ gg 7 TO x E.26E6 = x E
E x = 33.6 x TQ S TQ x 2.26E6 = x E
NG --
Field Data Adult whole body Child thyroid Location Dose Rate Ehr Dose Location Dose Rate Ehr Dose res/hr rem rem /hr rem Emergency Drill
, a * ** ,
3 .
. . . . -. .. - - . . - . ~ . - . ~
.. DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.2 Meteorology i
Unit . Repor t #
(date/ time)
Prepared'By I
Wind speed _______ mph Wind direction _______ 'N HT
_______ 'C s,
( ,
Default data
'J wind speed _ ______ mph 1000 to wind direction _______ 'N 1600 hrs.
3 stability class ___ D___
1 i wind speed __ _____ mpn
}
l 1600 to wind direction _______ 'N 1000 hrs.
i stability class _ __G___
1 i,
i Notes If the wind speed or wind direction cannot be obtained from plant
, systems, obtain them from the National Weather Service (704) 399-6000. If the NWS information is unavailables then obtain data from the MNS Control Room.
I f
l 1
..7
- yr ry- w v 7* -y wee +v q wwwp-++9---fwe-p eir- gem
- 'Te w om- ., ,,P**m-*eNNePDwe*N'w-FF* * " " "7 TNTW**** * * * ' " " ' " " * * * * * * ' " * " '
4
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ilP/0/8/1009/18 DIKE 70ME ColeANT Emelesere 5.3 Tue-home salative Concentraties Factars(Cg )
e Temperature Stability Distance (Miles) .
Gradient (C) Class .5 1 2 3 4 5 6 7 8 9 10
- 1) AT<-0.6 A 1.45-5 1.2E-6 5.9E-7 4.1E-7 3.2E-7 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7
- 2) -0.6 FAT (-0.5 C 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.IE-6 8.3E-7 7.8E-7
- 3) -0.5<AT(-0.2 D 3.8E-4 1.4E-4 4.95-5 .7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6
- 4) -0.2 FAT (+0.4 E 6.95-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 1.lE-5 9.7E-6
- 5) +0.4 FAT (+1.2 F 1.1E-3 5.IE-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.lE-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5
- 6) +1.2 FAT C 1.3E-3 1.IE-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 MDIE: If AT is unavailable use: 100&-.600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />
. See Stability m === D 1600-1000 hours use Stability Class G
~
DUKE POWER COMPANY
/' CATAWBA NUCLEAR STATION HP/0/B/1009/18 "
Enclosure 5.4 Protective Action Zones Determination Determine the affected zones (based on wind direction) from the table beloi and record on Enclosure 5.1 NOTE: If wind' speed is less than or equal to 5 mph, the affected zones for O - 5 miles shall be A0,A1 B1 C1,D1.E1.F1 Wind Direction PAZ's (degrees from North) 0 - 5 miles - 5 - 10 miles 0.1 -
22 A0,C1,D1, C2 D2 22.1 -
73 A0,C1 D1 E1 C2 D2,E2,F2 73.1 -
108 A0,C1,D1,E1.F1 D2,E2,F2,F3 108.1 - 120 A0,D1.E1.F1 D2,E2,F2,F3 120.1 - 159 A0,E1.F1 D2,E2,F2,F3.A2
.. . I' 159.1 - 207 A0,E1,F1,A1 E2,F2,F3,A2 B2 207.1 - 247 A0,F1 A1,B1 F2,F3 A2 B2 i 247.1 - 265 AC,A1,B1 F3 A2,82,A3,C2 265.1 - 298 A0,A1,B1,C1 A2,82 A3,C2
. 298.1 - 338 A0,B1 C1 82 A3,C2,D2
- - 4 338.1 - 360 A0,B1,C1 D1 B2,C2,DE I.
l l
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. - - - - + , - - .
,3_r,_~.,__,-. _y.-%__-,,-.-w.m,--.r, .-.-.,m-%.-._y . _ . - _ , . .- _.-.. y_ .,_ y,, , r.___ , . _ __ _ - _ - - - - - - - - - -
- 5 DUKE POWER COMPANY f-' '
CATAWBA NUCLEAR STATION
! HP/0/B/1009/18 .
Enclosure 5.5 Source Term Assessment - Steam Relief Valves Re; ort # ,
Reactor Trip / Projection based on data on /
}
(date/ time) (date/ time)
Calculations based on Melted Core LOCA ,
NOBLE GAS based on EMF 26 or EMF 10 SC g R/hr X 1 X lbm X Ci =
Q 3
sec lba R/hr see 1
( Enc l .- 5. 6 )
- . +
based on EMF 27 or EMF 11 R/hr X 1 X lbm X Ci =
Q
! see Ibn R/hr sec
! - - (Encl. 5.6)
. +
l based on EMF 28 or ENF12 R/hr X 1 X 1ha X Ci =
Q I see Ibn R/hr sec
- (_' - - (Encl. 5.4)
. ,. +
based on EMF 29 or EMF 13 R/hr X 1 X 1ha X C1 =
Q sec 1he R/hr sec
.- - (Encl. 5.6) l Total from all Steam Relief Valves. Og.= CL/sec IODINE From all Steam Relief valves l- Gg l
i Og X 1131eqv./Xe133eqv. ratio = C1/sec (Encl. 5.7)
Emergency
- Drill Prepared by:
l l
1
DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.6 EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, EMF 11. EMF 12, EMF 13 Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor based on Metted Core or LOCA 10 3.622 la 3.971 2,4 4.041 2.e 4.029 2,24 3.332 2,48 2.647 1100 2.438 1250 2.438
- 2,500 2.438 2,720 2.438
- units in C1 lbm R/hr Enclosure 5.6 is th5 correg.ston factor per Reference 2.13 x 2.83E4 ft 313* *"I #I *
- 1ba 1E6 al
.41 = specific gravity of steam per Reference 2.13 1
i i
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l L'
l DUKE POWER COMPANY l
[; CATAWBA NUCLEAR STATION i
HP/0/B/1009/18 .
Enclosure 5.7 1131eqv./Xe133eqv. Ratio Time Since Trip (hrs) Ratio based on Ratio based on LOCA Meltes Core (Column 1) (Column 2) !
10 2.74E-3 2.24E-3 12 3.42E-3 9.6eE-3 14 3.82E-3 1.59E-2 18 4.34E-3 2.85E-2
{
124 4.79E-3 7.52E-2 148 4.84E-3 1.11E-1 I
1100 5.06E-3 1.33E-1 l' 125o 6.55E-3 1.80E-1 15oo 1.02E-2 2.90E-1 :
1720 1.44E-2 4.33E-1 !
- Enclosure 5.7 is from Reference 2.13
,r\
\q)- ,
Notes For unit vent releases in which Irat is utilized to determine I-131 equiv. concentration, apply the appropriate correction from the table below .
- 1. M , use column 1 (based on LOCA). -
- 2. LOCA throuah charcoal filters, divide column 1 value by 100.
- 3. Core damane, use column 2 (based on Core Melt).
- 4. Cara damane throuah charcoal filters, divide column 2 value by 100.
- 5. Tube ruoture, divide column 1 value by 1,000. ,
i 6. New fuel accident. divide column 2 value by 6oo.
l 7. Old fuel accident, divide column 2 value by 600.
I
- 8. Gas decav tank, assume no radiciodine released, only noble gases are
! considered to be released from gas tank.
i 4
my*
- + , - --,ww ,+n-w,! --,,rw,,..--w-g-,,,wnn,.n,-,,.w,,,-e,,.,w----w,-r,o.,__--a-w-,----,-,-,-.e-r-,w- ,~,- - n - ,- ~~-w-~~----w-e--=-w--~-s--*-~ne
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DUKE POWER COMPANY l CATAWBA NUCLEAR STATION ,
HP/0/B/1009/18 Enclosure 5.8 Source Term Assessment - Containment Report #
Reactor Trip / Projection based on data on '
/
(date/ time) (date/ time)
Calculations based on Melted Core LOCA Containment pressure osig LR = ml/hr LR based on Realistic Leak Rate (check one) 1" 2" 4" 6" -8" 12 " - 18" 34" diameter opening (circle one) Personnel Hatch opening Equipment Hatch opening Design Leak Rate (2.449E6)
NCBLE GAS based on (Check onel EMF 39(L) EMF 39(H) EMF 53 if < 1E7 cpm if > 100 com O ir 39<H> is orr sca:
! ! cpm NG or X R/hr (Encl. 5.9)
X ml/hr =
Q see based on PACS sample uC1/m1 X 2.78E-10 Ed_hr, X ml/hr =
Q sec uCL sec IODINE based on
. NG 0 1
Q X 1131eqv./Xe133eqv. =
Q sec ratio (Encl. 5.7) see based on EMF 40 LR
/\ cpm X 9.82E-20 Cl he min X ml/hr =
Q
/\ min sec mi cpm see based on PACS sample uC1/m1 X 2.7EE-10 C1_hr. X ml/hr = Cl sec uCL see Emergency 0 Drill Prepared by:
l V -
i N _ ,' ' -
4 l HF/0/8/1009/18 DUEE POWEE COMPANY l Enclosure 5.9 Catawba Contalement Noble Gas Correction Factor Time Since IMF 39(L) EMF 39(H) ENF 53
Malted Core IACA Malted Core
>0 6.394E-18 6.672E-17 5.56E-14 1.429E-13 3.781E-10 1.190E-9
), I2 6.394E-18 4.448E-17 5.56E-14 1.003E-13 3.114E-10 5.894E-10
>4 6.394E-18 3.058E-17 '
5.56E-14 1.232E-13 2.780E-10 4.726E-10 f 78 6.394E-18' 2.113E-17 5.56E-14 1.195E-13 2.446E-10 3.392E-10 l
>24 6.394E-18 1.112E-17 . 5.56E-14 7.339E-14 2.335E-10 1.890E-10 T48 6.394E-18 1.056E-17 5.56E-14 6.060E-14 2.335E-10 1.668E-10
>100 6.394E-18 1.390E-17 5.56E-14 5.599E-14 2.335E-10 1.612E-10
>250 6.394E-18 1.446E-17 5.56E-14 5.588E-14 2.335E-10 1.557E-10 4
. >500 6.394E-18 9.730E-18 5.56E-14 5.560E-14 2.335E-10 1.251E-10 T720 6.394E-18 6.394E-18 5.56E-14 5.560E-14 2.335E-10 1.056E-10 1
units la ci he units la ci he units in ci he
, sec al eye sec al cps sec mL E/he i
3 Enclosure 3.9 is the correlation factor per Esference 2.13 Xg, E 1E al e
e l
DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 .
Enclosure 5.10 Containment t.eakage Rate Versus Pressure PSIG ml/hr 10 2.330E4 3.175E4 12 14 5.821E4 18 9.779E4 110 1.114E5 111 1.164E5 _
2,12 1.199E5
, 113 1.235ES 114 1.260E5 115 1.285E5
- Enclosure 5.10 fs the realistic leakage rate (m /sec) per Reference 2.12 X 1E6 ml/m X 3600 sec/hr. X 0.07 (0.07 per Reference 2.6).-
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DUKE POWER COMPANY e '
CATAW8A NUCLEAR STATION HP/0/B/1009/18 i
Enclosure 5.11 Containment Leakage Rate Versus Pressure and Size Opening
- For 1" opening
>L.25 2.209EB >5.0 3.908E8 >12.5 5.862E8
>2.50 2.889ES >7.5 4.588E8 >15.0 6.287EB
>3.75 3.483E8 >10.0 5.268E8 For 2" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 8.496ES >5.0 1.512E9 >12.5 2.243E9
>2.50 1.121E9 >7.5 1.784E9 >15.0 2.464E9
>3.75 1.342E9 >10.0 2.022E9 -
For 4" opening
>1.25 3.144E9 >5.0 5.692E9 >12.5 8.496E9
>2.50 4.248E9 >7.5 6.797E9 >15.0 9.176E9
>3.75 5.098E9 >10.0 7.731E9 For 6" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr i
>1.25 7.137E9 >5.0 1.291E10 >12.5 1.937E10
>2.50 9.516E9 >7.5 1.529E10 >15.0 2.124E10
>3.75 1.138E10 >10.0 1.716E10
. For 8" opening 4 ,,h PSIG ml/hr PSIG
' ' ml/hr PSIG ml/hr
\ . >1.25 1.257E10 >5.0 2.243E10 >12.5 3.381E10
>2.50 1.648E10 >7.5 2.634E10 >15.0 3.568E10
>3.75 1.971E10 >10.0 3.042E10 4 For 12" opening PSIG al/hr PSIG ml/hr PSIG ml/hr
! > 1. 25 - 2.719E10 >5.0 5.012E10 >12.5 7.476E10
! >2.50 3.738E10 >7.5 5.947E10 >15.0 8.156E10 t
>3.75 4.452E10 >10.0 6.712E10 For 18" opening-
,, PSIG ml/hr PSIG ml/hr PSIG ml/hr 1
>1.25 5.52EE10 >5.0 1.003E11 >12.5 1.529E11
>2.50 7.476E10 >7.5 1.189E11 >15.0 1.665E11
>3.75 8.836E10 >10.0 1.351E11 I For 34" opening
' PSIG ml /.hr PSIG ml/hr PSIG ml/hr
>1.25 1.869E11 >5.0 3.398E11 >12.5 5.132E11
>2.50 2.583E11 >7.5 4.078I11 >15.0 5.607E11
>3.75 3.093E11 >10.0 6.599E11 For Personnel Hatch opening -
. PSIG ml/hr PSIG ml/hr PSIG ml/hr l >1.25 2.379E12 >5.0 4.690E12 >12.5 6.967E12
>2.50 3.398E12 >7.5 5.573E12 >15.0 7.646E12 i >3.75 4.111E12 >10.0 6.37PE12 For Equipment Hatch opening l PSIG ml/hr PSIG ml/hr PSIG ml/hr <
l >1.25 1.121E13 >5.0 2.022E13 >12.5 3.059E13 !
s./ >2.50 1.478E13 >7.5 2.379E13 >15.0 3.398E13
>3.75 l 1.767E13 >10.0 2.719E13 1 i
N e Enclosure 5.11 is the containment leakage for an gpening size in i
s utandard cubic feet per min (scfe) X 2.83E4 al/ft X 60 min /hr.
! . . . .._. m ._._. -
DUKE POWER COMPANY ,
CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.12 Source Term Assessment - Unit Vent-Report #
Reactor Trip / Projection based on data on /
, (date/ time) (date/ time)
Calculations based 3 n Melted Core LOCA CFM = ft / min NOBLE GAS based on (ceck one)
EMF 36(L) EMF 36(H) EMF 54 if < 1E7 cpm if > 100 cpm if 36(H) is offscale EMF CF CFM Q NG cpm 3
or X X ft =
QL 3
R/hr (Encl. 5.13) min sec based on I Unit Vent Sample
[*.} 3 -
uCi/ml X 4.72E-4 Ci min _ml X ft ,
gL ,
sec ft" uCi min sec IODINE based on NG I Q1 X 1131eqv'./Xe133eqv. =
Qi sec ratio (Encl. 5.6) sec based on .
Licpm X 1.11E-13 Ci min _ min X ft ,
g1 ;
Limin see ft" cpm min see based on Unit Vent Sample 3
uCi/mi X 4.72E-4 Ci min _ml X ft ,
gL see ft" uCi min sec I Emergency Drill Prepared by:
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HP/0/B/1009/18 DUEE POWER COMPANY Enclosure 5.13 Catawbe Unit Vent Noble Gee Correction Factor t i
! Time Since EMF 36(L) EMF 36(H) EMF 54 1 Trip (bra) based on based on based on
!~
[j LOCA Malted Core 14CA Melted Core LOCA Melted Core
~
>0 1.086E-11 ' 1.133E-10 9.44E-8 2.426E-7 2.358E-4 1.887E-3 T2 1.086E-11 7.552E-11 9.44E-8 1.704E-7 2.358E-4 1.179E-3
>4 1.086E-11 5.192E-11 9.44E-8 2.091E-7 2.358E-4 9.905E-4 78 1.086E-11 3.587E-11 9.44E-8 2.030E-7 2.358E-4 6.367E-4 i >24 1.086E-11 R.888E-11 9.44E-8 1.246E-7 2.358E-4 2.931E-4 I48 1.086E-11 1.794E-11 9.44E-8 1.029E-7 2.358E-4 2.405E-4 f >100 1.086E-11 lt.360E-11 9.44E-8 9.676E-8 2.358E-4 2.358E-4 I250 1.086E-11 2.454E-11 9.44E-8 9.487E-8 2.358E-4 2.358E-4 l <-
a'
>500 1.086E-11 1.652E-11 9.44E-8 9.440E-8 2.358E-4 2.358E-4 1720 1.086E-11 1.086E-11 9.44E-8 9.440E-8 2.358E-4 2.358E-4 units in Ci sin.y units in Ci sin units in ci sin 3
sec f t' cpm see it cpe ,
sec ft R/hr 2
3 Enclosure 5.13 is the correlation factor per Reference 2.13 X 2.83E4 mi min m ft 60 sec IE6 al i
i
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b DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.14 Recommendea Protective Action Report To: Emergency Coordinator Report #
The recommended protective actions for the public are Current Previous Miles PAZ Actions
.5 A0 Actions A B C E A B C E 1 B1 El A B C E A B_ C E 2 Al C1 D1 F1 A B C E A B C E 4 B2 A B C E A B C E 5 A2 C2 D2 E2 F2 A B C E A B C E 7 F3 A B C E -
A B C E 8 A3 A B C E A B C E A - No protective action is recommended at this time.
B - Remain indoors with windows closed, turn off air conditioners and ,
other ventilation, monitor EBS stations. Control access. (Action E also).
(,_ \ C - Evacuate all affected zones, seek designate,d shelter.
Q' E - Pregnant women and children evacua,te and go to designated shelter. ,
- - based on field data.
Emergency Classification based on Radioloolcal Data Recommend Alert b Recommend Site Area Emergency if readings last 30 minutes b Recommend Site Area Emergency if readings last 2 minutes b Recommend senerai Emergency Comments:
i
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Dose Assessment Coordinator Date/ Time b Emergency Drill 9
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ei Form 34731 (R9-86) (1) ID No. HP/0/B/1009/11
, DUKE POWER COMPANY Change (s) O to
~'s PROCEDURE PROCESS RECORD o incorporated PREPARATION (2) STATION Catada (3) PROCEDURE TITLE Emergency Radio System Op'eration. Maintenance, and Conununication (4) PREPARED BY - N- '
DATE / ( f7 (5) REVIEWED BY C DATE /* ~N Cross Disciplinary Review By N/R (6) TEMPORARY APPROVAL (If Necessary)
By (SRO) C/ ATE By DATE (7) APPROVED BY. DATE l!
(8) MISCELLANEOUS
-- Reviewed / Approved By DATE cv :-)
Reviewed / Approved By DATE C) COMMENTS (For procedure reissue Indicate whether additional changes, other then previously approvedp, are included.
Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. Iv yes ONo (TO) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION O Yes O N/A Check lists and/or blanks properly initialed, signed, dated or filled in N/A or N/R, as appropriate?
, O Yes O N/A Listed enclosures attached?
OYss O N/A Data sheets attached, completed, dated and signed?
Oyes O N/A Charts, paphs, etc. attached sad properly dated. Hentified and marked?
O Yes O N/A Acceptanc criteria met?
VERIFIED BY DATE
['" PROCEDURE COMPLETION APPROVED DATE Q/
l (f 4) REMARKS (Attach additional pages,if necessary.)
,r- , . _ . - -
- - , , . . . - . . , - _ , . _ _ . . . , . _ . , _ . . _ . _ _ ~ , _ _ . - ,-...,.._.--.9..-, . . - - . - _ . . _ . . . - . . - _ _ _ - _ _ _ _ _ _ _ _ _ _ _
HP/0/B/1009/19 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY RADIO SYSTEM OPERATION, MAINTENANCE, AND COMMUNICATION 1.0 PURPOSE To describe the Emergency Radio System activation, maintenance and use during an emergency event or drill.
2.0 REFERENCES
2.1 HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory 2.2 HP/0/?/1009/04 Environmental Monitoring for Emergency Conditions within the ten mile radius of Catawba Nuclear Station 2.3 FT/0/B/4600/06 Emergency Drills 2.4 Crisis Management Plan, Implese. ting Plans, 5.3.6 Nuclear Technical Services Group 2.5 DPC Form 06005, Radio Operators Manual .
b.
N. / 3.0 LIMITS AND PRECAUTIONS 3.1 The Emergency Radio Network is specifically limited to use in an emergency drill, event, or operability check.
3.2 The Technical Support Center'(TSC) Base Station Remote Radio should be used to support operability checks of " Porta-Mobile" Field Monitoring Team Radios.
3.2.1 Emergency Radio System Base Stations and County / State Coded Squelch Radios are checked for operability by PT/0/B/4600/06 (Reference 2.3).
3.3 The following locations have radio capabilit'ies for temporary i emergency communications between:
3.3.1 Control Room and Allen Plant Steam rotation (Evacuation Point) - Production and Transmission Frequency 47.98 MHz 3.3.2 Nuclear Production PAP (Badging Office) and Security Base Station (located in Control Room) or TSC Security Representative - Dedicated Security Frequency NOTE: Relay messages through Security radio closest to locations in Step 3.3.2.
g 3.4 Emergency radio system operates on FM low-band dedicated frecuency of 48.50 MHz except where noted in Sample Enclosure 5.1.
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HP/0/B/1009/19 Page 2 of 4 r,
3.5 Use telephone numbers listed in Sample Enclosure 5.1 as primary -
communication links between TSC/ CMC and the following Evacuation Points:
3.5.1 Allen Steam Station 3.5.2 Newport Transmission Line Maintenance Building 3.6 .Use HP/0/B/1009/04 (Reference 2.2) as information guide for field monitoring locations, directions and sampling.
4.0 PROCEDURE 4.1 General Guidance for Emergency Radio Communication 3 4.1.1 Operate radios in accordance with Duke Power Company
" Radio Operators Manual", (Reference 2.5).
., 4.1.1.1 Use call signs and identifiers listed in Sample Enclosure 5.1.
4.1.1.2 Use Sample Enclosure 5.3 (Examples of Emergency Radio Communications) as format guidance for contranications ,
f~ 4.1.2 , Minimize the length of transmissions by using code numbers 4
y,';) -
and/or words listed in Sample Enclosure 5.2 as practicable.
4.1.3 Minimize the number of transmissions by:
4.1.3.1 Speaking slowly and distinctly in a slightly louder than normal voice.
4.1.3.2 Transmitting numbers one digit at a time except when reporting even thousands or time (hundreds of hours) as practicable.
4.1.3.3 Using phonetic alphabet listed in Enclosure 5.2 when transmitting letters or when spelling words.
4.1.4 Precede transmissions with the message "this is a drill" during emergency drills.
4.2 Location of Emergency Radios 4.2.1 Obtain radios from storage locations listed in Sample Enclosure 5.1.
4.3 Emergency Radio System Activation
. 4.3.1 Base Station Remote Radios V 4.3.1.1 Locatie antenna lead and plug into modular (telephone-type) receptacle.
, , . . , . .s . ... . .... , _ .. -- - -
~
~
HP/0/B/1009/19 Page 3 of 4 7-4.3.1.2 i Select AC s sitch on Base Station and energize -
by plugging power cord into AC receptacle.
4.3.1.2.1 Select DC switch on Base Station and energize by connecting DC leads to twin battery pack if AC power is not available.
4.3.2- " Porta-Mobile"/ Field Monitoring Team Radios 4.3.2.1 Turn power control switch to "0N" position.
4.3.2.2 Adjust squelch control knob clockwise until static is heard, then turn counterclockwise until static is just eliminated.
4.4 Emergency Radio System Operation 4.4.1 Base Station Remote Radios 4.4.1.1 Press key on microphone and hold to transmit messages; release key to receive transmissions.
4.4.1.2 Select " Intercom Mode" key for communication between the following Base Stations:
..s
'") 4.4.1.'2.1 Transmission Line Maintenance Building Base Station Remote.
4.4.1.2.2 Technical Support Center (TSC) Base Station Remote.
4.4.1.2.3 Nearsite Crisis Management Center' (CMC) Base Station Remote.
4.4.1.3 Signal County and/or State coded squelch radios to receive specific transmissions by keying the proper encoding numbers listed in Sample Enclosure 5.1.
4.4.1.4 Record sample resuirs received by the Radio Operator from Field Monitoring Teams on Enclosure 5.4 4.4.1.5 Inform the Field Monitoring Coordina*or periodically (e.g. every 10 minutes) of field data results.
4.4.2 " Porta-Mobile" FMT Radios l
4.4.2.1 Press key on microphone and hold to transmit messages; release key to receive transmissions.
f v 4.4.2.2 Hold microphone to the side of the mouth (at an angle) when transmitting. messages.
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- HP/0/B/1009/19 Page 4 of 4 4.5 Inoperable Radios -
4.5.1 Base Station Remotes 4.5.1.1 Contact Station Emergency Preparedness Coordinator to report problems with Base Station radio operation.
4.5.2 " Porta-Mobile"/ Field Monitoring Team Radios 4.5.2.1 Refer to HP/0/B/1000/06 (Reference 2.1) for problems with radios normally stored in Health Physics Emergency kits.
4.5.2.2 Use back-up " Porta-Mobile" radios in the event failures occur with primary " Porta-Mobile" radios.
5.0 ENCLOSURES 5.1 Radio Specific Data 5.2 Radio Code Signals 5.3 Examples of Emergency Radio Communications
.c f/.j) 5.4 Sample of Radio Operators Log Field Monitoring Survey Data 1
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.' Page 1 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
^
HP/0/B/1009/19 ENCLOSURE 5.1 -
RADIO SPECIFIC DATA i BASE STATION REMOTE RADIOS USER STORED OPERATED CALL SIGN IDENTIFIER
- 1. Technical Support Center TSC TSC KNHB778 Base One
- 2. Nearsite CMC (G.O.) WC2314 WC1222 KNHB778 Base Two COUNTY / STATE CODED SQUELCH RADIOS
, USER ENCODING NUMBER CALL SIGN IDENTIFIER
- 1. Gaston County EOC 26 KNBE486 Gaston County
- 2. York County EOC 41 236274 York County
- 3. Mecklenburg County EOC 21 kNBE481 Mecklenburg County
- 4. S;C. State FEOC 42 KB36274 S.C. State
- 5. N.C. SERT N/A KNBE482 N.C. State FIELD MONITORING TEAM RADIOS USER STORED CALL SIGN IDENTIFIER i t . Field Monitoring Team Temporary Admin. Bldg. KB36274 Alpha Team (Emergency Storage Room)
- 2. Field Monitoring Team Temporary Admin. Bldg. KB36274 Bravo Team (Emergency Storage Room)
- 3. Field Monitoring Team Temporary Admin. Bldg. KB36274 Charlie Team 1
(Emergency Storage Room)
- 4. Field Monitoring Team Temporary Admin. Bldg. KB36274 Delta Team (Emergency Storage Room) ,
- 5. Helicopter Team Temporary Admin. Bldg. KB36274 Echo Team (Emergency Storage Room)
- 6. Field Monitoring Team HEALTH PHYSICS KB36274 Foxtrot Team i
Instrument Issue (594' AUX) ,
TEMPORARY EMERGENCY USE RADIOS i
' TELEPHONE USER TYPE RADIO CALL SIGN IDENTIFIER FREQUENCY NUMBERS
- 1. Allen Steam Station Base Station KJZ783 Plant Allen 47.98 MHz MW 336-8525
,G Bell (704)825-2022
- 2. Newport Transmission Base Station WSP331 Newport 47.98 MHz MW 373-7309 Line Maint. Bldg. Trans. Bell 366-4777
\ -
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- - ~ -- -
Page 2 of 2 DUKE POWER COMPANY e' .
CATAWBA NUCLEAR STATION HP/0/B/1009/19 ,
ENCLOSURE 5.1 RADIO SPECIFIC DATA
- 3. Security (PAP) Handie-Talkie N/A Badging 467.475/462.475 X-2896 Office 467.525/462.525
- 4. Security (Control Base Station WRL557 Control 467.475/462.475 X-2339 Room) Room 467.525/462.525 X-2338
- 5. Security (TSC Handie-Talkie N/A Unit # 1 467.475/462.475 X-2326 Representative) 467.525f462.525 LEGEND: EOC -
Emergency Operations Center FEOC - Forward Emergency Operations Center SERT - State Emergency Response Team CMC -
Crisis Management Center
- .; PAP -
Personnel Access Portal WC -
Wschovia Center Offices
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- I Page 1 of 1 DUKE POWER COMPANY g
- CATAWBA NUCLEAR STATION
, HP/0/B/1009/19 ENCIDSURE 5.2 '
RADIO CODE SIGNALS CODE NUMBERS 1- Reporting On 2- Reporting Off 3- Stand By 4- VIP or Outsider Present 5-6-
7- Message Received and Understood or "Yes" 8- Repeat (Message not understood) 9- Cal 1.............................By Phone 10- Read (Reread) Meter 11- Relay Message to ........................
f 12- Fire (Give location) '
13- Check for Trouble 14- Nothing for You 15 - Give Your Location 16- Trouble Cleared 17- Cancel Call 18-19-
< ' ', 20- Radio Test (How do you receive my signal?)
(;j
. 21- Reque'st Assignment (Do you have anything for me?)
22- '
23-24- .I Have an Emergency Situation. Please Give Location. How Long Will It Take for You to Get into the Clear?
25-26-27-99- EMERGENCY ASSISTANCE NEEDED AT ..........
(Give location)(Use only when serious threat to life or safety exists)
CODE WORDS PHONETIC ALAPHABET OVER -
End of conversation and A- Alpha N- November awaiting reply B- Bravo 0- Oscar OUT -
End of transmission and C- Charlie P- Papa no answer is expected D- Delta Q- Quebec l CLEAR -
End of transmission and E- Echo R- Romeo no answer is expected F- Foxtrot S- Sierra NEGATIVE -
No or incorrect G- Golf T- Tango ROGER -
Affirmative or Yes H- Hotel U- Uniform STAND-BY -
Wait for further information I- India V- Victor i
or instructions J- Juliette W- Whiskey SAY AGAIN - Repeat last transmission K- Kilo X- X-Ray WRONG -
Message is being repeated L- Lima Y- Yankee back incorrectly M- Mike Z- Zulu WAIT -
Pause for a few seconds v
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g Page 1 of 2 DUKE POWER COMPANY r CATAWBA NUCLEAR STATION HP/0/B/1009/19 ,
ENCI.3SURE 5.3 EXAMPLES OF EMERGENCY RADIO COMMUNICATIONS NOTE: The following call signs and identifiers are for example only.
5.3.1 Example of' Base Station Signing On:
BASE: WQC 699 BASE 1 (BASE 2 for CMC) CODE 1 (Signing On)
BASE: BASE 1 to KA82139 (Team Name - Alpha, Bravo, Charlie, Delta. Echo or Foxtrot)
MOBILE: KA82139 ALPHA to BASE 1 CODE 7 (Go Ahead)
BASE: STANDBY FOR FURTHER INSTRUCTIONS MOBILE: CODE 7 (Message Received) KA82139 ALPHA OW BASE: WQC 699 BASE 1 OUT 5.3.2 Example of Field Monitoring Team Signing On: ,
MOBILE: KA82139 ALPHA to BASE 1 BASE: BASE 1 to ALPHA MOBILE: CODE 1 (Reporting On)
BASE: CODE 7 (Message Received) WQC 699 BASE 1 OW
, MOBILE: KA82139 ALPHA OUT
- ._)
5.3.3 Example of Field Monitoring Team Reporting Data:
MOBILE:. KA82139 BRAVO to BASE 1 BASE: BASE 1 to BRAVO MOBILE: IDCATION M , TIME 2015 HOURS DOSE RATE MEASUREMElff .02 mR/hr IODINE ACTIVITY 5.1 x 10 WCi/mi BASE:
WQC 669 BASE 1 OW NOTE: DATA is recorded by base station radio operator on Enclosure 5.5 of Procedure CP/0/B/4003/01.
5.3.4 Example of Base Station Operator Dispatching Field Monitoring Team to New Sampling Location:
BASE: WQC 669 BASE 1 to KA82139 CHARLIE MOBILE: KA82139 CHARLIE 'IT.AM to BASE 1 GO BASE: CHARLIE TEAM P.10CEED '1V LOCATION M-1 MEASURE AND. REPORT DOSE RATE AND IODINE ACTIVITY
, MOBILE: LOCATION M-1, CODE 7, CHARLIE OW BASE: WQC 669 BASE 1 OW p
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Page 2 of 2 DUKE POWER COMPANY
> ,c' CAT.WBA NUCLEAR STATION
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HP/0/B/1009/19 '
ENCLOSURE 5.3 EXAMPLES OF EMERGENCY RADIO COMMUNICATIONS 5.3.5 Example of Field Monitoring Team Signing Off:
MOBILE: KA82139 DELTA TEAM to BASE 1 BASE: BASE 1 to DELTA TEAM MOBILE: CODE 2 (Reporting Off)
BASE: CODE 7, WQ 669 BASE 1 OUT NOTE: BASE 1 r.hould sign off when all mobile teams have signe.1 off: ,
EXAMPLE: WQ 669 BASE 1 CODE 2 5.3.6 Example of Communication Check:
BASE: WQC 699 BASE l'(BASE 2 for CMC) CODE 1 (Signing On)
BASE: BASE 1 to KA82139 (Team Name - Alpha, Bravo, Charlie, Delta, Echo or Foxtrot)
MOBILE: KA82139 ALPHA to BASE 1 CODE 7 (Go Ahead)
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BASE: HOW DO YOU RECEIVE MY SIGNAL 7
.. / MOBILE: LOUD AND CLEAR KA82139 ALPHA OUT
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BASE: WQC 699 BASE 1 OUT -
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Form 34731 (R9-86) (1) ID No.HP/0/B/1000/06 r DUi"E POWER COMPANY Cha '(s ) O to PROCEDURE PROCESS RECORD l In.corporated i PREPARATION ,.
l (2) STATION CATAWBA NUCLEAR .
l (3) PROCEDURE TITLE EMERGENCY EQUIPMENT FUNCTIONAL CHECK AND INVENTORY (4) PREPARED BY - 8 dan 12-23-86 (5) REVIEWED BY DATE 12-23-86 Cross Disciplinary Review By N/R (6) TEMPORARY APPROVAL (If Necessary)
By (SRO) DATE By - DATE (7) APPROVED BY DATE IE ^f V
/
(8) MISCELLANEOUS
(- Reviewed / Approved By DATE -
Reviewed / Approved By DATE (9) COMMENTS (For procedure reissue indicate whether additional changes, other then previously approved chjnges, are included.
Attach additional pages,if necessary.) ADDITIONAL CHANGES INCLUDED. Eyes ONo
/-/9-37 (10) COMPARED WITH CONTROL COPY DATE COMPLETION (11) DATE(S) PERFORMED (12) PROCEDURE COMPLETION VERIFICATION
. O Yes O N/A Check lists and/or blanks property initialed, signed, dated or filled in N/A or N/R, as appropriate?
O Yes O N/A Listed enc!osures attached?
Oyes O N/A Data sheets attached, completed, dated and signed?
Oyes C J/A Charts, graphs, etc. attached and properly dated, identified and marked?
O Yes O N/A Acceptance criteria met?
VERIFIED BY DATE
., -(13) PROCEDURE COMPLETION APPROVED DATE (14) R E?.! AR KS (A:ne. 22:::.:as! ,:s;a:, i f .94aasser, .)
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T HP/0/B/1,000/06 DUKE POWER COMPAhT CATAWBA NUCLEAR STATION EMERGENCY EQUIPMENT FUNCTIONAL CHECK AND IhYENIORY 1.0 PURPOSE To provide for the availability and readiness of Emergency Equipment.
2.0 REFERENCES
. 2.1 HP/0/B/1005/08; Respirator Quality Assurance 2.2 HP/0/B/1009/19; Emergency Radio System Operations, Maintenance and Communicat'.ons -
2.3 Catawba Nuclear Station Directive 2.11.13 '
2.4 Catawba Nuclear Station Directive 3.2.2 2.5 Catawba Nuclear Station Directive 3.3.3 2.6 Catawba Nuclear Station Emergency Plan i ,
O 2.7 Catawba Nuclear Station Technical Specifications 6.8.1 2.8 Duke Power Company Radio Operator's Manual 2.9 Maintenance of Silver Zeolite Air Sampling Cartridges Letter; File: CN-768.01 2.10 10CFR 50 Appendix E 2.11 Technical Manual for Groban Gasoline Gen'erators i
2.12 Shelf-life of Health Physics Clothing; File: CN-766.00.
3.0 LIMITS AND PRECAUTIONS 4
3.1 Operation of Portable Generators 3.1.1 Avoid operating the unit while hands are wet or while standing in water.
3.1.2 Generators shall not be started while equipment is plugged into generator.
3.1.3 Low voltage rubber gloves should be worn while operating the generators. These gloves are stored with the generators.
~a 2.2 Ill: r :::11:2 :2r:rli;;n sha:: b di:;:2rkd if tha sa2: has bac:
br: ken.
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~ HP/0/B/1000/06 - i Page 2 of 7 3.3 Any radiation monitoring equipment (located in an emergensy kit) that must be removed fromi service for any reason shall be replaced as soon as possible.
3.4 Any emergency kit used during. training or for drill purposes shall
~
be reinventoried as soon as possible. The individual responsible for the training or drill shall be responsible for inventory and restocking of all on-site kits.
3.4.1 Off-site hits shall be reinventoried as above and a list of deviations shall be given to the Respiratory / Instrument Calibration (R/IC) Supervisor. R/IC shall be responsible for restocking off-site kits as soon as possible.
4.0 PROCEDURE 4.1 Monthly Emergency Equipment Check / Inventory 4.1.1 Portable Generator Check 4.1.1.1 Portable generators shall be considered acceptable for use if:
4.1.1.1 The oil level is at an acceptable level per Reference 2.11.
4.1.1.2' The generator starts and russ for at least 5 minutes.
4.1.1.3 The generator stabilizes after a
, portable air sampler is plugged into each of the generator outlets.
4.1.1.2 If generator is acceptable, shut off geserator and remove any excess gasoline'from the gas tank.
4.1.1.3 Document the operability of the generatets in the appropriate column on the Monthly /Q::arterly Emergency Equipment Check Sheet (Enclos re 5.1).
4.1.2 Two-Way Iow Band FM Radios 4.1.2.1 'Ibe radios shall be considered acceptable for use if:
4.1.2.1.1 Each radio transmits a message to another radio.
4.1.2.1.2 Each radio receives a message from another radio.
4.1.2.2 Document the operability of the radios in the appropraece 4re4 on Enclosi. ire 3.i.
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.HP/0/B/1000/06 Page 3 of 7 e ,,
4.1.2.3 Inoperable radios shall be removed frps servic's.
Contact Toddville Communica. tion Shop Planner for instructions on disposition for repair.
4.1.3 Batteries 4.1.3.1 All batteries shall be considered acceptable for use if:
4.1.3.1.1 The battery tester needle indicates
" good" when the battery is tested.
4.1.3.1.2 The battery appears,to be in good physical condition (no dents, corrosion, etc.).
4.1.3.2 Document battery check on Enclosure 5.1.
4.1.4 Portable Survey Instruments 4.1.4.1 Portable Survey Instruments shall be considered acceptable for use if:
4.1.4.1.1 The instrument battery checks.
~
4.1.4.1.2 'The instrument source checks in accordance with the instrument's operation procedure.
4.1.4.1.3 The instrument has no apparent physical damage.
4.1.4.1.4 The instrument has been calibrated within 3 months. +/- 7 days.
j 4.1.4.2' Document the instrument's operability on
[
Enclosure 5.1.
4.1.5 Portable Air Samplers 4.1.5.1 Air Samplers shall be considered acceptable for use if:
4.1.5.1.1 The sampler operates when plugged into an electrical outlet.
4.1.5.1.2 The calibration date on the sa=pler j is current.
I 4.1.5.1.3 The sampler has no apparent physical
,, damage.
1
- . _ _ . . . -. ..,. . . - _ , ,__.s-_.,_- , _ _ _ . _ . . _
HP/0/B/1000/06 Page 4 of 7 e
4.1.5.2 Doc. ament the sampler's operability on. Enclosure
~
5.1.
4.1.6 Respiratory Equipment ,
4.1.6.1 Respirato'ry equipment shall be considered acceptable for use. if:
4.1.6.1.1 The c:;uipment is in accordance with criteria stated in Reference 2.1.
4.1. 6.1. 2 The Emergency Self-Contained Breathing Apparatua (SCBA) are available at the following locations:
Locations M0aisum Units Control Roos 2 Upper Personnel Hatch 2 Iower Personnel Hatch 2 Health Physics Respiratory Storage Area 8 "w 4.1. 6.1.3 Six large cylinders of breathing
." J/ air (minimum.of six hours used for 5 people) are located in the Control Room along with 5 airline respirators and associated airline hoses.
4.1.6.2 Document operability of r,espiratory equipment in accordance with Reference 2.1.
, 4.2 Quarteriy Emergency Equipment Inventory / Inspection 4.2.1 Emergency equipment kits shall be incentoried quarterly
- and after each use using the appropriate Emergency Equipment Kit List of Contents (Enclosures 5.4 - 5.13) 4.2.1.1 Consult the Emergency Equipment Kit Location
- Sheet (Enclosure 5.2) for the locations of each kit.
4.2.1.2 Perform monthly checks as in deeps 4.1.1, 4.1. 3, 4.1.4, 4.1.5, 4.1. 6.
4.2.1.3 The quarterly operability check on two-way low band radios shall be performed as follows:
'- 4.2.1.3.1 Radios shall be checked from a point 10 miles from the plant in v
l accordance with Reference 2.8.
l
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HP/0/B/1000/06 Page 5 of 7
, m z-4.2.1.3.2 Contact shall be made frps the base station in the TSC to each of the radios.
4.2.1.3.3.
Each of the radios shall make contact with the base station.
NOTE: Base Call Sign - D02-778 Radio Call Signs - EB36274 (Alpha, Bravo, Charlie, Delta, Echo, Foxtrot, Emergency Vans) 4.2.1.3.4 DNument operability of radios on Enclosure 5.1.
4.2.1.4 Perform a functional check of the dosimeter charger / reader. The charger is acceptable for use if the charger light illuminates. .
. 4.2.1.5 Ensure that the leak and source check dates on the dosimeters are current.
{d. .i 4.2.1.6 " Ensure that the TLD's are ccrrent. TLD's are changed in January and July i 1 month.
4.2.1.7 Ensure the Potassium Iodide tablets have not
, exceeded their expiration date. (Reorder 2-87) 4.2.1.8 Ensure the seal on the silver zeolite cartridge packet is not broken and the cartridges are not
, damaged.
4.2.1.9 Ensure that all procedures are current with the Control Copy.
4.2.1.10 Ensure the flashlight bulb illuminates properly.
4.2.1.11 Check all protective clothing to ensure it has not exceeded the recommended shelf-life per Enclosure 5.15.
4.2.1.12 Ensure that GMR-I canisters have not exceeded their expiration date.
4.2.1.13 Document any deviations on the Emergency Equipment Deviation Authorization Sheet (Enclosure 5.14).
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HP/0/B/1000/06 Page 6 of 7 4.2.1.14 The Technician shall sign off Enclosure 5.1 and forward to the Respiratory / Instrument Calibration (R/IC) Supervisor.
4.2.2 Weather Information. Check 4.2.2.1 Quarterly a call shall be placed to the National Weather Service located in Columbia, SC at 803-794-2330 or 803-794-2593. If these numbers cannot be reached, an.alternati number in Charlotte (704-399-6000) may be used.
Obtain wind direction, wind. speed, and cloud cover from one of these sources for the vicinity of Catawba Nuclear Station.
4.2.2.2 Obtain the same information from the Control Roce.
4.2.2.3 Record this information on the Weather Information Form (Enclosure 5.3).
4.3 Deviation Authorization 4.3.1 The Station Health Physicist shall be made aware of any deviation recorded on Enclosure 5.14.
L..)
4.3.2 The Station Health Physicist shall have evaluated the consequences the deviation may have upon the capability to respond to an emergency situation.
T 4.3.3 Enclosure 5.14 shall be used to state the action taken to remedy the deviation, and to state the justification for taking that action.
.4.4 Upon completion of this procedure all required documentation will be filed in the Emergency Equipment Functional check and Inventory i
Iog, until the end of the quarter.
4.4.1 At the end of the quarter all of the required documentation will'he placed in the Health Physics Satellite Master File.
4.4.2 Sign off the FT printout and forward as per Reference 2.4.
- 5.0 ENCLOSURES 5.1 Sample of Monthly / Quarterly Emergency Equipment Check Sheet l 5.2 Sample of Emergency Equipment Xit Location Sheet l
5.3 Sample of Vesther Information Form 5.4 Sample of Recovery Xit List of Contents v
i I
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-HP/0/B/1000/06 -
Page 7 of 7 5.5 Sample of Environmental Survey Kit List of Contents ,
5.6 Sample of Environmental Survey Kit List 'of Contents (Helicopter) 5.7 Sample of Personnel Survey Kit List of Contents 5.8 Sample of Personnel Survey Kit List of Contents (Evacuation Facility) 5.9 Sample of Emergency Medical Kit List of Contents (First Aid Room) 5.10 Sample of Emergency Medical Kit List of Contents (Piedmont Medical Center) 5.11 Sample of Operations Support Center Kit List of Contents 5.12 $ ample of Technical Support Center Kit List of Contents 5.13 Sample of Fuel Transfer Kit List of Contents 5.14 Sample of Emergency Equipment Deviation Authorization Sheet 5.15 Sample of Recommended Shelf-life for Protective Clothing
- 5.16 Sample of Protected Area Survey Kit List of Contents
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Pass 1 of 2 CATAWBA NUCLEAR STATION MONTHLY / QUARTERLY EMERGENCY EQUIPMENT CHECK SHEET !
c . KP/0/B/1000/06 ENCLOSURE 5.1
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SIGNATURE /DATE Environmental Survey Kit - A ~
l Environmental Survey Kit - B l 1
E;vironmental Survey Kit - C Environmental Survey Kit - D Environmental Survey Kit - K -
R;ctvery Kit - Allen Rec:very Kit - Transmission Line Maint.
Recsvery Kit - Security Pap Area Pratscted Area Survey Kit L..oranel Survey Kit -Allen -
Parsinnel Survey Kit - Transmission Line Maint.
Paracanel Survey Kit - Security Pap Area l Emergency Medical Kit - First Aid ,
l Room 1
l Emergency Medical Kit - Piedmont Medical Center Oper tiona Support Center Eit T2chnical Support Center Kit Fuel Transfer Kit I
/
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. 1
s Page 2 of 2 HONTMLY/ QUARTERLY EMERGENCY EQUIPMENT
,e .
CHECK SHEET
' RP/0/B/1000/06 ,
ENCLOSURE 5.1
, ~
GASOLINE GENERATORS Generator Number Comments Signature /Date CHP-3163-SR CHP-3164-SR CHP-3165-SR CHP-3166-SR CHP-3167-SR %
PORTABLE RADIO TRANSMIITER - RECEIVERS
~
1 l
,. Radio Call Sign Comments Performed At Signature /Date c
l 10-Mile on Site EMERGENCY VAN (H.P.) ,
EMERGENCY VAN (I&E) ;
ALPHA CHP-3250 BRAVO CHP-3249 CHARLIE CHP-3248
~
DELTA CHP-3242 .
- ECHO CHP-3247 FOXTROT CHP-3243 nLPHA-1 CHP-3252 BRAVO-1 CHP-3244 CHARLIE-1 CHP-3245 O
DELTA-1 CHP-3251 IECHO-1 C19-1246 l l l l be: : -t ce-ns: ! !
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CATAWBA NUCLEAR STATION EMERGENCY EQUIPMENT LOCATION SHEET HP/0/B/1000/06 ENCLOSURE ~5.2 ,
KITS LOCATION Recovery Kits (4)
Evacuation Facilities (2) Allen Steam Station Transmission Line Maintenance Building Security Pap Area Temp. Admin. Building Environmental Survey Kits (Vehicle) (4) Temp. Admin. Building Environmental Survey Kit (Helicopter) (1) Temp. Admin. Building Protected Area Survey Kit Auxiliary Building.
Elev. 594 Room 551 Personnel Survey Kits (4)
Evacuation Facilities (2) Allen Steam Station Transmission Line Maintenance Buildi=g Security Pap Area Temp. Admin. Building Emergency Medical Kit (2) Aux. Building Fint Aid Room Piedmont Medical Center
~
Operations Support Center Kit Operations Support Center Technical Support Center Kit Technical Support Center Fuel Transfer Kit Temp. Admin. Building
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CATAWBA NUCIE.AR STATION WEATHER INFORMATION HP/0/B/1000/06 ENCLOSURE 5.3 National Weather Service control Room Wind Direction Wind Speed Cloud Cover
~
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Signature /Date
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CATAWBA NUCLEAR STATION ' '
RECOVERY KITS LIST OF C0hTENTS
~
HP/0/B/1000/06 '
i -
ENCIASURE~5.4 MINIMUM ITEM AMOUhT- !
List of Contents 1
Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Low /High Range Dosimeters (0-500 mR), (0-5R) 2 each !
Dose Cards 25 TLD Badges 6 Dosimeter Charger 1 Boundary Ribbon or Rope (50 yd. roll) 1 Masking Tape (roll) 1 Rain Suits (set) 2 Coveralls: Cotton 2 -
Gloves: Cotton (pair) 2 ,
Rubber (pair) 2 -
Shoe Covers: Disposable (pair) 2 Rubber (pair) 2 -
Hoods: Cotton 2 Poly Bass (Various) 12 Caution Signs w/ inserts 2 Legal Pad 1
- . I; Instrument / Smear Survey (pad) 1
'u Pens 2 ,
Grease Pencil and refills 1 - l Full Face Respiratior With GMR-I Canister (or equivalent) 2 H First Aid Kit 1 l Potassium Iodide Tablets Trans. Line Maint. 275 bottles Security PAP
- 150 bottles Allen Steam Station 275 bottles ~
KI Distribution. Data Sheet 100 Smears (box) 1 ;
NuCon Smears 30 ;
Flashlight 1 i Batteries (Size D). 10 l Scissors 1 !
Medication Envelopes Trans. Line Maint. 100 l
Security PAP 60 !
Allen Steam Station 100 Crisis Management Team Phone Directory ** 1 SLED Badges (Personnel and Vehicle each)** 100 Emergency Planning Zone Maps ** 3 i NP/0/B/1009/16 1 l
i
- Any Deviaticas will be documented on the Emergency Equipment Deviation l Authorization Sheet (Sample Enclosure 5.14). !
- These items ere found only in the Recovery Kits located at Allen Steam j w Station and Transmission Line Maintenance Building.
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l Page 1 of 2 CATAWBA NUCLEAR STATION ,
ENVIRONMENTAL SURVEY KITS' LIST OF CONIT.NTS ,
HP/0/B/1000/06
~
ENCLOSURE 5.5
~
MINIMUM ITEM AMOUhT List of Contents 1
' Eberline E-520 w/HP-270 Probe . 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Portable MCA** - 1 Eberline PIC 6A 1 Emergency Radio Transmitter / Receiver 1 Radeco H809V Air Sampler 1
, Gasoline Generator (Gasoline in Safety Cabinet) 1 s Low /High Range Pocket Dosimeter (0-500 mR), (0-5R) 2 each .
Dose Cards 25 TLD Badge 6 Dosimeter Charger 1
- Tull Face Respirator With GMR-I Canister (or equivalent) 2 Potassius Iodide Tablets (bottle) 2 Tyvek Disposable Coveralls 6 Tyvek Disposable Hoods .
6
.i Coveralls: Cotton .
. 4 Gloves: Cotton (pair) 8 Rubber (pair) (Size 7), (size 9) 2 each
- Shoe Covers: Disposable (pair) 4 Rubber (pair) 4 Hoods: Cotton 4 Sandwich Bags (box) 1 Poly Bass (Various Sizes) 6 Masking Tape (roll) 1 l , Compass 1 hreezers 1 Limnological Sampler 1 s Cubitainers 6 1 Liter Vide Mouth Bottles 5 Stopwatch 1 Battery Operated Latern 1 Flashlight 1 Batteries (Size D) 14 l
. Batteries (9 volt) 4 Batteries (6 volt) 1 Silver Zeolite Filter Cartridges 30 Particulate Filters 30 Filter Cartridges Labels & Bass 100
. Smears (box) 1 Nucon Soears 30 Instrument / Smear Survey (pad) 1 Nap of Ten Mile Zone Sectors 1 v' Legal Pad 1 Pen 2 Per=anent Marker 1
_ . . . ._ 4 ._.__. , . _ . . .. - . --
-. .__ _ - _ - . . L ._ . _. _
Page 2 of 2 .,
CATAWBA NUCIZAR STATION ENVIRONMENTAL SURVEY KITS" LIST OF CONTE.VIS '
HP/0/B/1000/06 ~
ENCLCSURE 5.5 MINIMUM ITEM AMOU.N*r Hand Spade 1 Grease Pencil and refills 1 Dize Roll 1 Scissors 1 Rain Suits - 3 Telephone location maps 1 l Field Monitoring Data Sheet 20 Field Monitoring Work Sheet 20 KI Tablet Distribution Data Sheet 1 Radio Operator Manual 1 .
CPD1 Key 1 Emergency Response Van Keys (Doors, Ignition & Generator) 1 set l SLED Badges (Personal - Vehicle) 4 Reflective safety Vests 2 HP/0/B/1009/04 1 HP/0/B/1009/16 1
, ., 7 ,, HP/0/B/1003/17 1
\{) .HP/0/B/1009/19 1
- Any Deviations will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
(
- This instrument is stored and maintained in the Health Physics Counting Room Area.
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CATAWBA NUCLEAR STATION . .
ENVIRONMENTAL SURVEY KITS LIST OF CONTENTS (Helicopter)
. HP/0/B/1000/06 ENCLOSURE 5'6 MINIMUM ITEM AMOUNT List of Contents 1 Eberline PIC-6A 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Iow/High Range Pocket Dosimeter (0-500 mR), (0-SR) 2 each Dose Cards 25 Field Monitoring Data Sheet - 20 TLD Badge 6 Dosimeter Charger 1 Full Face Respirator with GMR-I Canister (or equivalent) 2 Potassium Iodide Tablets (bottle) 2 KI Distribution Data Sheet 1 Stopwatch 1 Flashlight 1 Batteries (Size D) 10 Batteries (9 volt) 4 Ear Plugs (pairs) 6 Map of Ten Mile Zone Sectors 1 Legal Pad 1 t ' .'
Pen '
2 Rain Suita 2 Instrument /Seear Survey (pad) 1 Emergency Radio Transmitter / Receiver- 1 HP/0/B/1009/19 1 HP/0/B/1009/04 1 HP/0/B/1009/16 1 1
e
- Any Deviation will be documented or the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
%4Y
. Page 1 of 2.
CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS LIST OF CO.VITYrS '
HP/0/B/1000/06 .
ENCLOSURE 5.7 MINIMUM ITEM ,
AMOUNT List of Contents 1 Eberline E-140N v/HP-210 Probe (or epivalent)*** 2 Sample Slide Tray *** . 1 Exempt Source 1 Emergency Radio Transmitter / Receiver ** 1 Radio Operator Manual - 1 Low /High Range Dosimeters (0-500 mR/hr), (0-5 R/hr) 2 each Dose Cards 25 TLD Badges 2 Dosimeter Charger 1 Full Face Respirator With GMR-I (or equivalent) 2 .
Potassium Iodine Tablets (bottle) 2 KI Distribution Data Sheet 1 Coveralls: Cotton 6 Gloves: Cotton (pair) 6 Rubber (pair) 6 Shoe Covers: Disposable (pair) 6 y '. } Rubber (pair) 6 i-
' Hoods: Cotton . 6 Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bass (Various) 6 Seears (box) 1
, Nucon Smears 25 Instrument /Seear Survey (pad) '
1 Pens 2 Grease Pencil & Refills 1 Legal Pad 1 Scissors 1 Rsin Suits 3 Decon Kit 1
- 1) Rad Con I
, 2) Rad Wash
- 3) Paper Towels Scrub Brush )
- 4) j
- 5) Cotton Swabs
- 6) Fingernail Clippers
- 7) Phischex (12) al)
- 8) Personnal Decontaminatien Tor =s Batteries (Size D) 10 Station Directive 3.8.3 1 HP/0/3/1004/06 1 HP/0/B/1009/05 1
,j HP/0/3/1009/16 1 HP/0/B/1009/19** 1 ss- -.-n,- .. , - - .,
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.. Page 2 of 2, CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS LIST OF CONTENTS HP/0/B/1000/06 ENCLOSURE 5.7
- Any Deviation will be documented on the EmerSency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
- The Security PAP Area shall.have (3)'t-140N w/HP-210 Probe or equivalent -
and Sarple Slide Tray.
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CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS LIST OF CONTENTS
1
' (EVACUATION FACILITY) l s
- HP/0/B/1000/06 ENCLOSURE 5.8 MINIMUM ITEM , AMOUNT List of Contents 1 Eberline E-140N w/HP-210 Probe (or equivalent) 3 Exempt Source 1 Low /High Range Dosimeters (0-500 mR), (0-5R) 4 each Dose Cards 25 TLD Badges -
4 Dosimeter Charger 1 Potassium Iodide Tablets (bottle) 2 KI Tabist Distribution Data Sheet 1 Medication Envelopes 3 Coveralls: Cotton 6 .
Gloves: Cotton (pair) 6 Rubber (pair) 6 Shoo Covers: Disposable (pair) 6 Rubber (pair) 6 Hoods: Cotton 6 Disposable Coveralls 40
,-: . Bocadary Ribbon or Rope,(50 yd. roll) 1 Y ;. c )
Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bass (Various) 6 Seears (box) 1 Instrument /Seear Survey (' pad) 1 Pens . 2 Grease Pencil & Refills 1 Legal Pad 1 Decon Kit 1
- 1) Rad con -
- 2) Rad Vash l 3) Paper Towels
, 4) Scrub Brush
- 5) Cotton Swabs
- 6) Fingernail Clippers
- 7) Phisobox (125 al)
- 8) Personnel Decontamination Forms Scissors 1 l
Station Directive 3.8.3 1
, Evacuation Personnel Dose Record 50 Catawba Nuclear Station Telephone Directory 1 Batteries (Size D) 10 HP/0/B/1004/06 1 HP/0/B/1009/05 1 HP/0/B/1009/16 1 i ,
! .V *Any Deviation will be documented on the Emergency Equipment Deviatica l
.5:hori:stien Sh e: (2:sple E..:10:ura I . * *.) .
- , - ..~..,..e, :-,,.,:, - . , - - - - - - , - -- .- - - . _ - . - , - - ,
CATAWBA NUCLEAR STATION .
EMERGENCY MEDICAL KIT LIST OF CONTENTS I', . FIRST AID ROON
~, . HP/0/B/1000'/06 ENCIDSURE 5.9
~-
MINIMUM ITEM '
AMOUNT List of Contents 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source . 1 Poly Bass (various sizes) 6 Seears (box) '
1 1
Nucon Smears _ 25 Coveralls: Cotton 6 Gloves: Cotton (pair) 6 Rubber (pair) 6 Shoe Covers: Disposable (pair) 6 Rubber (pair) 6 Hoods: Cotton 6 Rain Suits 2 Tape, Radioactive Material 1 Tape, Masking 2" 1 Tape, Duct 2'- 1 Instrument /Seear Survey (pad) 1 r, Pens 2
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Legal Pad 1. .
Caution Signs w/ inserts 3 Radioactive Material Tags 50 Scissors 1
- Poly for Ambulances (bundles) 3 Batteries (Size D) 4 HP/0/B/1004/06 1 HP/0/B/1009/08 1 Low Range Dosimeters (0-300 mR) 2 TLD Badges 2 ,
- Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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CATAWBA NUCLEAR STATION .
' EMERGENCY MEDICAL KITS LIST OF CONIINI3
/- PIEDMONT MEDICAL CINIT.R HP/0/B/1000/06 .
ENCIDSURE 5.10 ,
MINIMUM '
ITEM AMOUNI List of Contents 1
' Eberline E-520 w/HP-270 Probe 1 Eberline E-140N V/210 Probe (or equivalent) . 1 Exempt Source 1 Poly Bass (various sizes) 14 Smears (box) -
1 Nucon Seears 25 Tape, Radioactive Material 1 Tape, Hasking 2" 2 Tape, Duct 2" 4 Instrument / Smear Survey (pad) 1 -
Caution Signs w/ inserts 5 Rad Rope 1 TLD Badges 10 Pocket Dosimeters (0-500mR) 10 7 Dose Cards 25 Dosimeter Charger 1
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Radioactive Material Tags 50
,3 / Floor and Vent Covering 1 Disposable Coveralls 25 -
Disposable Shoe Covers (pairs) 25 Disposable Hoods 10 Cubitainers 5 Decon Kit 1
- 1) Red Con
- 2) Rad Wash i~
- 3) ' Paper Towels .
4). Scrub Brush ,
- 5) Cotton Swabs
- 6) Fingernail Clippers
, '7) Phischex (125 al)
' 8) Personnel Decontamination Forms Cotton Gloves (pairs) 50 Rubber Gloves (pairs) 20 Batteries (Size D) 8 Grease pencils (box) 1 j Stanchions 4 Trash Receptacle 2 RP/0/B/1004/06 1 HP/0/3/1009/08 1 l
l *Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Er. closure 5.14).
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CATAWBA NUCLEAR STATION . Page 1 of 2-CPERATIONS SUPPORT CEN17.R KITS LIST OF CONITNTS
'fs HP/0/B/1000/06 ENCLOSURE 5.11 MINIMUM ITEM AMOUNT l
. List of Contents , 1,
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Coveralls: Cotton 40 ;
Gloves: Cotton (pair) 40 ;
Rubber (pair) 40 l Shoe Cevers: Disposable (pair) 40 Rubber (pair) 40 )
Hoods: Cotton 40 Full Face Respirators with GMR-I Canister (or equivalent) 10 Flashlights 11 Batteries. (Size D) 34 Batteries (9 volt) 20 Eberline PIC 6A 5 RN-14 w/HP-210 Probe 1 E-140N w/EP-210 Probe (or equivalent) 1 Exempt Source 1 Camera (Polaroid) 1 Polarold Film Pacs 2 Masking Tape (Roll) 2 Dosimeters (0-100R), (0-5R) 5 Dose Cards 25
. Dosimeter Charger 1
- l. Small Sample Bottles or Medication Envelopes 10 v Rain. Suits 5 Poly Bass (various sizes) 50 Radeco H809V Air Sampler 3 i
Silver Zeolite Filter Cartridges 30 i
Particulate Filters 30
- Filter Cartridge Labels 30 Potassium Iodide Tablets (bottle) 20 KI Distribution Data Sheet 10 .
RP/0/B/1004/06 , 1 Decon Kit
- 1
- 1) Rad con
- 2) Rad Wash
- 3) Paper Towels
- 4) Scrub Brush
- 5) Cotton Swabs -
- 6) Fingernail Clippers
- 7) Phisobox (125 al)
- 8) Personnel Decontamination Forms Instrument / Smear Survey (pad) 1 Telephone 2 Post-Accident Containment Air Sampling Equipment Kit 1 Pen (box) 1 Grease Pencil (and refills) (box) 1 Extension Cord (50 ft.) 2
~i , Extension Cords (25 ft.) 2
, Stopwatch 2
._) Large Battery Lanterns (with 6 volt batteries) 4 Plan- Ors.ing, I l
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Page 2 of 2-CATAWBA NUCLEAR STATION f., OPERATIONS SUPPORT CENTER KITS LIST OF CONITRIS HP/0/B/1000/06 *
- ENCIASURE 5.11 ,
MINIMUM '
ITEM AMOUhT OSC Response Personnel Dose Record Forms 125 Seears (box) 1
- Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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. Page 1 of 2 CATAVBA NUCLEAR STATION
, s. TECHNICAL SUPPORT CENTER KIT LIST OF CONIINTS HP/0/B/1000/06 ENCLOSURE 5.12 ,,
MINIMUM ITEM AMOUNT .
List of Contents 1 Coveralls: Cotton 20 Gloves: Cotton (pair) 20 Rubber (pair) 20 -
Shoe Covers: Disposable (pair) 20 Rubber (pair) 20 Hoods: Cotton -
20 Full Face Respirators with GRM-I Canister (or equivalent) 6 Eberline E-520 w/HP-270 Probe 1 Eberline PIC-6A 3 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 .
Radeco H809V Air Sample 1 Dosimeter (0-100R), (0-5R) 6 each Dose. Cards 25 Silver Zeolite Filter Cartridges 30 Particulate Filters 30 Filter Cartridge Labels 25 Dosimeter Charger 1 m ,j - Potassium Iodide Tablets (bottle) 25
- k. l Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 3 Rad Tape 2 Smears (box) 1 Poly, Bass ,
6 Masking Tape (Roll) 1 Pen 2 Legal Pad .. 1 Grease Pencil (and refills) -, 1 Flashlights 8 Batteries (Size D) 30 Batteries (9V) 12 Small Sample Bottles or Medication Envelopes 10 i
, Rain Suits 6 Decon Kit 1 i 1) Red Con
- 2) Rad Wash
( 3) Paper Towels
- 4) Scrub Brush
- 5) Cotton Swabs
- 6) Fingernail Clippers
- 7) Phischex (125 al)
- 8) Personnel Decontesination Forms
! Instrument /Saear Survey (pad) 1 Request for Exposure Extension Forms 15 i ' ,'j Plant Drawinas 1 2_. MP/0/B/1009/16 1 HP/0/3/1CCI./Ca 1
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CATAWBA NUCLEAR STATION
/ ' TECHNICAL SUPPORT CENTER KIT LIST OF CONITNIS .
HP/0/B/1000/06 -
ENCLOSURE 5.12 , .
- Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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/. ..' CATAWBA NUCLEAR.. STATION FUEL TRANSFER KIT LIST OF CONTENTS .
HP/0/B/1000/06 ,
' ENCLOSURE 5.13 l
MINIMUM ITEM AMOUhT Liat of Contents 1 Shoe Covers:. Disposable (pair) . 20 Rubber (pair) 6 Gloves: Cotton (pair) 20 Surgeons (box) 1 Rubber (pair) 6 Coveralls: Disposable 4 Cotton 6 Hoods 4
Vet Suit 2 -
Hard Hat 3 Full Face Respirators with GMR-I Canister (or equivalent) 2 Radeco Hgo9V Air Sampler 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Eberifme PIC-6A 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source
., .,[ 1 (O; Silver Isolite Cartridges and Particulate Filters 10 Labels for Filters and Cartridges 10 Potassiba Iodide Tablets (Bottle) 30' TLD Badge i
5 Low /High Range Dosimeter (0-500 mR), (0-5R) 5 each i
Dose Card 25 Dosimeter Charger '
1 Veather-Proof Caution Signs with Inserts 4 Radioactive Waste Signs (4" x 6") 12 Caution: Radiation / Radioactive Material Tags 12 50 yd. Roll of Barricade Tape (Magenta & Yellow) 4 Step off Pads 3 Poly Bass 12 Hand Gardening Spade 1 Vide Mouth Sample Bottles 4 Plastic Sample Bottles or Medication Envelopes 12
- K1 swipes (box) 2 Nucon Saears 100 I Copy of NAC-1 Drawings (Prints) 1 Copy of Loading and Unloading Instructions 1 Duct Tape (Roll) 2 Masking Tape (1" and 2" Rolls) I each Contact Pyrometer with Probe 2
- Safety Glasses 5 Binoculars 1 Tool Kit 1
./ ' Batteries (9 Volt) 4 V Tlashlights 2
'.:;aiu '3 se T) id Steno Pad with 2 Mechanical Lead Pencils 1
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- Page 2 of 2 -
- CATAWBA NUCLEAR. STATION FUEL TRANSFER KIT LIST OF CONTENTS .
HP/0/B/1000/06 _
' ENCLOSURE 5.13
~
. MINIMUM
.. ITEM AMOU'fr Grease Pencils 2 All Purpose Marker 2 Scotch Tape Roll and Dispenser 1 Roll of Dimes 1 Gasoline Generator (Gasoline Stored in Safety Cabinet) -
1 Instrument /Seear Survey (pad) 1 HP/0/B/1009/16 1
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_ , s CATAWBANUCLF4;jATIOlt NF/2/B/1000/06 ENERCENCY EQUIPNENT DEVIATION AUTHORIZATION SNEET .
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a' ACTION'TAKEN TO ImVIATIO!! DESCRIPTION KIT
- RENEDY DEVIATION ACTION JUSTIFICATION SIGNATURE DATE
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,HP/0/B/1003/06 .
ENCLOSURE 5.15 CATAWBA NUCLEAR STATION .
RECOMMENDED SHELF-LIFE FOR PROTECTIVE CIDIHING .
. Cotton Goods: 4 years Tyvek Goods: ,
4 years *
. Duraguard Goods: 4 years Rubber overshoes 4 years Vinyl Gloves: 6 months Lates Gloves: 6 months -
PVC goods: 1 year NOIE: If the data marked on the protective clathing exceeds the allavable shelf-life, remove the protective clothing from the emergency kit.
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CATAWBA NUCLEAR STATION .
PROTECTED AREA SURVEY KIT LIST OF CON'IT.NTS
,..s HP/0/B/1000f06 ENCIASURE 5.16 ITEM MINIMUM AM.OUNT r
List of Contents 1 Eberline R0-2A (or equivalent) 2 Map of Protected Area 2 Emergency Radio Transmitter / Receiver 2 High Range Dosimeters (0-5 R) 2 i .
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