ML20050F813
| ML20050F813 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/17/1982 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20050F756 | List: |
| References | |
| PROC-820317-01, NUDOCS 8204130383 | |
| Download: ML20050F813 (80) | |
Text
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i TABLE OF CONTENTS i
Revision Date l
1.0 CLASSIFICATION & ASSESSMENT 1.1 Initial Classification . . . . . . . . . . . 1 03-17-82 1.2 Plant Status ................ 0 03-31-81 1.3 Estimation of Source Term . . . . . . . . . . 0 03-31-81 1.4 Radiological Dose Evaluation . . . . . . . . 3 03-08-82 1.5 Protective Action Evaluation . . . . . . . . 2 02-26-82 1.6 Radioiodine Blocking & Thyroid Exposure Accounting ................ 1 02-26-82 2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Immediate Actions . . . . . . 0 03-31-81 2.2 Unusual Event - Plant and Company Personnel Notification ............... 1 07-01-81 2.3 Unusual Event - Off-Site Agency Notification 1 02-26-81 3.0 ALERT IMPLEMENTING PROCEDURES O 3.1 Alert - Immediate Actions . . 03-31-81
() 3.2 Alert - Plant & Company Personnel
. . . . . . . . 0 Notification ............... 1 07-01-81 3.3 Alert - Off-Site Agency Notification . . . . 0 03-31-81 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES 4.1 Site Emergency - Immediate Actions . . . . . 0 03-31-81
- 4.2 Site Emergency - Plant & Company Personnel Notification ............... 1 07-01-81 4.3 Site Emergency - Off-Site Agency Notification 0 03-31-81 5.0 GENERAL EMERGENCY - IMPLEMENTING.PROCE'DURES ' '
5.1 General Emergency - Immediate Actions . . . . 0 03-31-81 5.2 General Emergency - Plant & Company Personnel Notification . . . .. . . . . . 1 07-01-81 5.3 General Emergency - Off-Site Agency Notification ............... 0 03-31-81 6.0 EVACUATION 6.1 Limited Plant Evacuation . . . . . . . . . . 0 03-31-81 6.2 Plant Evacuation .............. 1 02-26-82 6.3 Exclusion Area Evacuation . . . . . . . . . . 0 03-31-81
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[b 6.4 Energy Information Center Evacuation . . . . 0 03-31-81 F20413032 820330 PDR ADOCK 05000266 F PDR
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e Page 2 I\ Revision Date 7.0 CHEMISTRY & HEALTH PHYSICS RESPONSE & PREPAREDNESS 7.1 Internal Chem & HP Group Personnel Notification /
Initial Response 7.1.1 Chem & HP Group Personnel Notification
& Initial Response when Chem & HP Personnel are On-Site . . . . . .. 1 03-17-82 7.1.2 Chem & HP Group Personnel Notification
& Initial Response when Chem & HP Personnel are Off-Site . . . . . . . 1 03-17-82 7.1.3 HP Protective Actions by Operations Personnel Prior to Arrival of Chem
& HP Group Personnel . . . . . . . . 1 05-15-81 7.2 Health Physics Facility Activation 7.2.1 Activation of HP Facilities at Site Boundary Control Center . . . . . 2 03-17-82 7.2.2 Activation of HP Facilities at Operations Support Center . . . . 1 03-17-82 7.2.3 DELETED
(s 7.2.4 Health Physics Communications Control & Use of Vehicles
. . . 1 03-17-82
( ) 7.2.5 . . . . . 1 03-17-82 7.3 Radiological Surveys 7.3.1 Airborne Sampling & Direct Dose Rate Survey Guidelines . . . . . . 3 03-17-82 7.3.2 Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant . . . . . . . . . . . . . 3 12-30-81 7.3.3 Post-Accident Sampling of Contain-ment Atmosphere . . . . . .. . . 3 12-30-81 7.3.4 Movement of Required Chemistry Equip- _ _ , _ ~
ment & Material to the Technical Support Center Counting Room &
Mini-Laboratory . . . . .. . . . 0 12-30-81 7.4 Emergency Equipment 7.4.1 Routine Check, Maintenance, Cali-bration & Inventory Schedule for Health Physics Emergency Plan Equipment . . .. . . . . . . . . 4 03-17-82 7.4.2 Emergency Plan Equipment Routine Check, Maintenance & Calibration
['/
\ 7.4.3 UseofBaldModeEb3bbingie' N_- Channel Iodine Spectrometer to Determine Airborne Iodine Activities . . . . . . . . . . . . 1 05-15-81
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. 7.4.3.1 Use of Canberra Model 3100 Series 30 Multichannel Analyzer to Determine Airborne Iodine Activities . . . . 0 02-26-82 7.4.4 AMS-2 Air Particulate, Iodine &
Noble Gas Sampler / Detector . . . . 0 03-31-81 8.1 Personnel Assembly & Accountability . . . . 1 03-17-82 9.1 Security . . ... . . . . . . . . . . . . . 0 03-31-8'1 10.0 Firefighting .. . . . . .. . . . . . . . . 0 03-31-81 ,
11.0 FIRST AID & MEDICAL CARE 11.1 On-Site First Aid Assistance . . . . . . . . 2 02-26-82 11.2 Injured Person's Immediate Care . . . . . . . 1 05-15-81 11.3 Hospital Assistance . . . . . . . . . . . . . 0 03-31-81 11.4 Personnel Decontamination . . . . . . . . . . 0 01-29-82 12.0 REENTRY & RECOVERY PLANNING 12.1 Reentry Procedures for Emergency Operations 1 03-17-82 3 12.2 Personnel Exposure & Search & Rescue Teams . . ... . . . . ... . . . . . . . 1 03-17-82 12.3 Recovery Planning . . . . . . . . . . . . . . 0 03-31-81 12.4 Personnel Monitoring Exposure Guidelines . . 0 01-29-82 13.0 PRESS 13.1 Crisis Communications . . . . . . . . . . . . 1 09-04-81 14.0 COMMUNICATIONS .
14.1 Testing of Communications Equipment . . . . . 0 03-31-81 15.0 TRAINING, DRILLS &. EXERCISES 15.1 Employee Training . . . . . . . . . . . . . . 1 09-04-81 15.2 Off-Site Personnel Training . . . . . . . . . 0 03-31-81 15.3 Drills & Exercises . . . . . . . . . . . . . 1 05-15-81 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Section Notification &
Response . .. . . . . . . . . . . . . . . 3 09-04-81
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. I 03-17-82
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i t i TABLE OF EPIP FORMS V
EPIP EPIP Form Title Procedure 01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (03-81) 7.3.1 02 Emergency Plan Survey Record Site Boundary Control Center (09-81) 7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 04 Status Report on Plant Systems & Controls for Affected Unit (03-81) 1.2 05 Worksheet for Status Report on Radiation Monitoring System for Unit (03-81) 1.2 06 Worksheet for Status Report on Radiation Monitoring System for Plant (03-81) 1.2 07 For X/Q Determination (09-81) 1.4 08 Estimated Whole Body & Thyroid Projected Doses (09-81) 1.4 09 Estimated Whole Body Dose Calculation Worksheet for Specific Noble Gas Releases (09-81) 1.4 10 Estimated Ground Deposition Calculation Worksheet for
,3 Particulate Radionuclide Releases (09-81) 1.4 Summary of Radiological Dose Evaluation Calculations (09-81)
(d)'
11 12 Unusual Event Incident Report Form (03-81) 1.4 2.1 13 Alert Incident Report Form (03-81) 3.3 14 Site Emrgency Incident Report Form (03-81) 4.3 15 General Emergency Incident Report Form (03-81) 5.3 16 Event Data Checklist (03-81) 5.3 17 List of Missing Personnel (03-81) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Drill / Exercise Scenario (03-81) 15.3 20 Drill / Observation Sheet (03-81) 15.3 21 Drill / Exercise Evaluation Report (03-81) 15.3 22 Plant & Company Emergency Call List (02-82) Call List Tab 23 Offsite Agency Emer@e~ncy Call List (02-82) Call List Tab 24a Site Boundary Control Center Emergency Plan Inventory Checklist (01-62) 7.4.1 24b TSC, ESC, South Gate & OSC Emergency Plan Inventory Checklist (03-82) 7.4.1 24c Emergency Plan Health Physics Supplies at Two Rivers Community Hospital Inventory Checklist (09-81) 7.4.1 -
24d Control Room Emergency Plan Equipment Inventory Checklist (09-81) 7.4.1 24e Emergency Vehicle Inventory Checklist (05-81) 7.4.1 24f Emergency Plan First Aid Kit Inventory Checklist (02-82) 7.4.1 24g Emergency Plan Burn Kit Inventory (02-82) 7.4.1 24h Emergency Plan First Aid Room Inventory (05-81) 7.4.1
(
24i Emergency Plan Stretcher Inventory (09-81) 7.4.1
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. EPIP EPIP Forms Title Procedure 25a Emergency Vehicle Checklist (10-81) 7.4.2 25b Monthly Health Physics Instrument & Air Sampler Functional Test Checklist (03-82) 7.4.2 25c Quarterly Emergency Plan Checklist (01-82) 7.4.2 25d Semi-Annual & Annual Eraergency Plan Checklist (03-82) 7.4.2 26 Quarterly Communications Test (03-81) 14.1 27 Monthly Communications Test (03-81) 14.1 28 Emergency Plan Instrument Calibration Schedule (05-81) 7.4.2 29 Emergency Plan Counting Equipment & Frisker Calibration l Schedole (07-81) 7.4.2 30 Reactor Coolant Post-Accident Sampling Analysis Report (09-81) 7.3.2 31 Containment Atmosphere Post-Accident Sampling Analysis Report (12-81) 7.3.3 32 Accounting Short Form (02-82) 8.1 s
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EPIP 1.1 MINOR Revision 1
.[m) 03-17-82 INITIAL CLASSIFICATION 1.0 GENERAL The purpose of this procedure is to provide a means of classifying an event or condition at the Point Beach Nuclear Plant into one of four emergency classifications as described in the Point Beach Nuclear Plant Emergency Plan. Each emergency classification requires emergency organization noti-fications, mobilizations, and actions to be performed in order to appropriately react to the situation and providt for the health and safety of plant and public personnel. They are listed in order of increasing severity.
1.1 Unusual Event An unusual plant condition which either has occurred or might occur.
This condition could possibly lead to a degradation in overall
, safety. This condition does not represent a significant radio-activity release, involves no offsite response,' and may require no
((m') augmentation of plant personnel. In spite of the above, prompt notification of the counties and state is required.
1.2 Alert Plant conditions in which events are in progress or have occurred which involve an actual or potential degradation of plant safety.
Radiation releases are not likely to cause an offsite hazard. Prompt offsite notification is necessary and the plant organization may have
. to be augmented.
- 1. 3 . Site Emergency Plant conditions in which events are in progress or have occurred which involve actual or probable major failures of plant functions.
Potential radioactive releases may have an impact on offsite people.
Prompt notification of offsite agencies is required. The plant organization must be augmented and the technical support center, onsite operations support center, and emergency support center will be operational. An evacuation may be necessary.
1.4 General Emergency Plant conditions in which events are in progress or have occurred which involve actual or imminent substantial core degradation and a f'- potential for loss of containment integrity. Potential radioactive h releases may have an impact on offsite people. Prompt notification 4
P EPIP 1.1 Page 2 N
of offsite agencies is required. The plant organization must be augmented and the technical support center, onsite operations support center, and emergency support center will be operational. An evacu-ation may be necessary. The emergency news center will be opened.
The Shift Supervisor has the responsibility and authority to take bmnediate action to mitigate the consequences of the emergency. He will consult with the Duty & Call Superintendent and assign the appropriate emergency classi-fication and initiate the necessary Emergency Plan implementing procedures.
2.0 REFERENCES
2.1 Nuclear Regulatory Commission NUREG-0654, Revision 1, published November, 1980.
2.2 Point Beach Nuclear Plant Emergency Plan Sections 4.1 and 5.1.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged.
3.2 Emergency Plan implementing procedures are not to be used to respond
' /~') to security threats. One hour notification of the NRC is required
$s_,/ using the red phone for security threats.
3.3 Certain events require notification to the NRC within one hour. These items are included on Table 1-1. Those items which are noted as "NRC Only" means that there is no classification for the events and no notification other than the NRC is required. These notifications are not considered as starting the Emergency Plan.
3.4 The " Indications Used" in Table 1-1 are those which one may expect if that level of emergency occurs very quickly. For more slowly developing situations, other indications may be judged appropriate.
For example, a primary system leak rate of 40 gpm is an Unucual Event. Subsequently, charging may be lost and, in addition, the leak may worsen. One may not see charging flow 50 gpm greater than letdown flow when in fact an Alert should be declared.
4.0 INITIAL CONDITIONS -
None.
NOTE: APPENDIX 1 0F NUREG-0654 (PAGE 1-3) CONTAINS THIS SENTENCE: "THE TIME IS MEASURED FROM THE TIME AT WHICH OPERATORS RECOGNIZE (EMPHASIS ADDED) THAT EVENTS HAVE OCCURRED WHICH MAKE DECLARATION OF THE EMER-GENCY CLASS APPROPRIATE.
. ,m f,v) 9 l , .. . .. - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
o EPIP 1.1 Page 3 O 5.0 PROCEDURE 5.1 Call the Duty & Call Superintendent for consultation to establish the initial classification. If he is unavailable, the Shift Supervisor is responsible for classification.
5.2 Select affected categories related to plant events or conditions at this time. Check (J) all applicable categories.
Refer to Page ;
Category in Table 1-1
- 1. Safety System Functions 1
- 2. Abnormal Primary Leak Rate 1
- 3. Abnormal Coolant Temperature /
Pressure 2
- 4. Abnormal Primary / Secondary Leak 2
- 5. Core Fuel Damage 3 (s_, 6. Secondary Coolant Anomaly 4
- 7. Abnormal Effluent 5
- 8. Major Electrical Failures 5
- 9. Control Room Evacuation 6
- 10. Fire 6
- 11. Plant Shutdown Function 7
- 12. Abnormal Radiation Levels at Site Boundary 8
- 13. Fuel Handling Accident 8
- 14. Serious or Fatal Injury 9
- 15. Security Threat 9
- 16. Hazards to Plant Operations 9
- 17. Natural Events 10 Reactivity Transient 10
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EPIP 1.1 Page 4 C
Refer to Page Category in Table 1-1
- 19. Load Transient 11
- 20. Other 11 5.3 Beginning at the indicated page in Table 1-1 (attached), review initiating conditions for all categories checked above.
5.4 Record most severe emergency classification at this time.
5.5 Record date/ time of initial classification (subsequent columns for reclassification at a later date and time are provided if reclassifi-cation is required).
Initial Subsequent Subsequent i Date/ Time Date/ Time Date/ Time
\ NOTE: IF THE SHIFT SUPERVISOR CANNOT COMMUNICATE WITH A DUTY &
CALL SUPERINTENDENT, THE SHIFT SUPERVISOR MUST NOTIFY THE STATE AND TWO COUNTIES WITHIN 15 MINUTES OF THE DECLARATION OF ANY CLASS OF EMERGENCY.
5.6 If events or conditions are classified as an Unusual Event, perform EPIP 2.1, " Unusual Event - Immediate Actions."
5.7 If events or conditions are classified as an Alert, perform EPIP 3.1,
" Alert - Immediate Actions."
5.8 If events or conditions are classified as a Site-Emergency, perform EPIP 4.1, " Site Emergency - Immediate Actions."
5.9 If events or conditions are classified as a General Emergency, perform EPIP 5.1, " General Emergency - Immediate Actions."
NOTE:
"One hour" refers to the requirement to notify NRC within one hour (10 CFR 4
- I 50.72).
"One hour - Open line" refers to the requirement to notify NRC within one hour and maintain an open line for continuous communication (10 CFR 50.72).
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! Notes: DCS - Duty & Call Superintendent DSS - Duty Shift Supervisor TABLE l-1
'FFDSAR - Final Facility Description &
Safety Analysis Report MASP - Modified Amended PBNP Security Plan EMERGENCT CLASSIFICATION Emergency Category Initiating condition Indication Used Classification
- 1. Safety System Functions Unplanned initiation of emergency core cooling Any of the following first-out reactor trip Unusual Event with injection to the primary system panel annunciation with indicator confir-nation noted:
- 1. "Contair. ment press hi",
[PI-945, PI-947, PI-949 (2/3 >5 psig)]
- 2. " Steam line loop A lo-lo press"
[PI-468, PI-469, PI-482 (2/3 <530 psig)]
- 3. " Steam line loop B lo-lo press" .
(PI-478, PI-479, PI-483 (2/3 <S30 psig)]
- 4. " Pressurizer lo press SI"
[PI-429, PI-430, PI-431 (2/3 <1735 psig))
- 5. Wide range pressure <1500 psig Loss of containment integrity requiring When shutdown commences as determined by DSS Unusual Event ,
shutdown by Technical Specifications and DCS Loss of engineered safety feature requiring When shutdown commences as determined by DSS Unusual Event shutdown by Technical Specifications and DCS Loss of fire protection system function When shutdown commences as determined by DSS Unusual Event requiring shutdown by Technical Specifi- and DCS cations (i.e.. both fire pumps inoperable) s
- 2. Abnormal Primary Exceeding Technical Specification primary system When shutdown commences as determined by DSS Unusual Event Leak Rate leak rate (10 gpe) and DCS
% %) <
l EPIP 1.1 Table 1-1 1 Page 2 Emergency Category Initiating Condition Indication used Classification Leak rate >SO cpm All of the following: Alert
- 1. " Volume control tank level hi-lo"
[LI-141 and/or LI-112 <8%)
- 2. Decreasing pressurizer level
[LI-426,LI-427,LI-428]
- 3. " Charging pump speed hi"
- 4. Charging line flow (FI-128) >50 cpm more than letdown flow (F1-134)
Leak rate in excess of available pump All of the following: Site Emergency capacity including charging, high head SI
- and low head SI 1. " Volume control tank level hi-lo
- [LI-141 and/or LI-112 <8%]
- 2. No pressurizer level indicated l [LI-426, LI-427, LI-428]
- 3. All available pumps running as indicated by the red light at the switch
- 4. Increasing core exit T/C temp as indicated by F-250 and confirmed on local readout.
- 3. Abnormal Coolant Unexpected decrease in subcooling margin Both of the following: Unusual Event Temperature / Pressure
- 1. Alarm on P-250, if operable
- 2. Confirmation by manual calculation Pressure >2735 psig rressure >2735 psig on PR-420 and NRC only
" Code, safety or PORV not closed" l-hour open line (2)
DNBR <1.30
- 4. Abnormal Primary /' Exceeding Technical Specification primary-secondary When shutdown commences as determined by DSS Unusual Event Secondary Leak leak rate and DCS
N %) -
EPIP 1.1 Table 1-1 Page 3 l ,
Emergency
- l. Category Initiating Condition Indication Used Classification Gaoss failure of I SG tube (>400 gpm) & loss of All of the following first-out reactor panel Alert .
offsite power.(FFDSAR 14.2.4) annunciation with confirmation indication:
- 1. " Pressurizer to Press SI,"
[PI-429, PI-430, PI-431 (2/3 <!735 psig)] ,
- 2. a. " Steam generator A level hi"
[LI-461, LI-462, LI-463 (2/3 >70%)] or
- b. " Steam generator B level hi"
[LI-471, LI-472. LI-473 (2/3 >70%)]
- 3. a. "4.16 kv bus undervoltage"
& O volts on A03 & A04 voltmeters.
- b. XO4 to A03 ammeter on CO2 (0 amps)
' c. XO4 to A04 ammeter on CO2 (0 amps)
- 4. SI flow >400 gpa indicated by F1-924 &
FI-925 and pump discharge pressure corresponding to flow. '.
Rapid failure of >10 SG tubes (4000 gpm) with All of the'following first-out reactor panel Site Emergency or without offsite AC annunciation with confirming indication:
- 1. " Pressurizer lo press SI"
[PI-429, PI-430, PI-431 (2/3 <1735 psig)]
- 2. a. " Steam generator A level hi" lLI-461, LI-462, LI-463 (2/3 >70%)]
or
- b. ' Steam generator B level hi"
. [LI-471 LI-472, LI-473 (2/3 >70%)]
- 3. SI flow >4,000 gpm indicated by FI-626 &
FI-928.
- 5. Core Fuel Damage Gross fuel damage in core indicated Both of the following: Unusual Event
- 1. Letdown line radiation monitor (R9) 100 x alarm setpoint.
- 2. Sustained offscale & chemical analysis shows fission product concentration increase by 100X.
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EPIP 1.1 Table 1-1 Page 4 Emergency i Category Initiating Condition Indication Used Classification Nassive fuel damage 300 pCi/cc iodine-equivalen+. as determined by Alert by chemical analysis
- 1. dassive loss of fuel clad integrity Initiating Condition Nos. 1 & 2 exist and No. 3 General Emergency
- 2. With simultaneous loss of primary system integrity is possible:
- 3. With potential loss of containment integrity
. 1. 300 pCi/cc iodine-equivalent determined by chemical analysis
- 2. Primary system leak >1000 gun indicated by SI flow >1000 cpm (FI-924 & FI-925) and pump discharge pressure corresponding to flow
- 3. Ninimum containment pressure suppression equipment is not available (any of the
, following):
No fan coolers operating and <2 spray a.
Pumps.
- b. No spray pumps operating and <2 fan coolers s .
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- c. <2 fan coolers running with I spray ptyp
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(PI-9ES, PI-947, PI-949 (2/3 >5 psig)) '
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.,1 f f f , 5 "Centainment spray" with 2/3 + 2/3 >25 psig f ?] -
y (PI-945, PI-947, PI-949] '
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- 6. Secondary Caolant - Reduction in feedwater enthalpf incidtht , L a. Decreasing feedwtsterrteg ir*dicated by giusual, Event a
- ' *, f*
Ancealy ,
(FFDSAR 14.1'7).
-- . T0-4134 & TO-438A on P-2ff ag .'r ; f / .-',
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,b. Confire d by local temperature indika' tor j l ,d' a
e- 5.. r i 7~ > l ', ' 5
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-/ on outlet of No. 5 feedwater heater.
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- 2. Unexpecte'd increasing power on excore nuclear instrumentation
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, f. 3 '#-- . Steam lid break with primary-to-seconder 7 leak ' All of the following first-out reactor trip Alert .
- '. p- rate in excess of 10 cpm g.
panel e nunciation with confirmation ,
. 14 -
,'. (FFDSAR 14.2.5) ; . ,;; "4
! 'r "
1.' Either:
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- 4. "SteamlineloopAb)-Lopress" =>
2- p, y ,
y - [PI-468, Pfq409,'PI-481,,(2/3 <530 psig)] ,
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" Steam liue loop B Lo-Lo press" .-
(PI-478, PI-479, PI-483 (2/3 <530 psig)l e s/./.. ,
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EPIP 1.1 2
' ( , Table 1-1
~-' i T
i Page 5
< , 4
. Emergency
-'f
-Category >
Initiating Co_qdition "
Indicatiof_ Used Classification
- 2. Confirmed primary-to-secondary leak rate e of at least 10 gpe.
, 3. Either:
- a. "Stese line loop A isol channal alert" lFI-464, FI-465 (1/2 >3.9x10s Lb/hr)]
or~
- b. " Steam line loop B isol channel alert"
[FI-474, FI-475 (1/2 >3.9x10s Ib/hr)]
Secondary Coclant Transient initiated by loss of feedwater, followed All of the following: General Emergency Anomaly by loss of auxiliary feedwater for >l hour (FFDSAR 14.1.11) 1. Decreasing SG levels -
"A" SG {LI-461, LI-462, LI-463]
"B" SG lLI-471, LI-472, LI-473)
- 2. No auxiliary feedwater flow -
(FI-4002, FI-4007, FI-4014]
lFI-4036, FI-4037]
- 7. Abnormal Effluent Radiologicdl effluent Technical Specification limits Airborne effluents only Unusual Event exceeded but <10 times the limit (FFDSAR 14.2.3)
Radiological effluent Technical Specification limits Liquid effluents only Unusual Event exceeded (FFDSAR 14.2.2)
Radiological effluents >10 times Technical Airborne effluents only Alert i specification instantaneous limits. (An instan-taneous rate which, if continued for >2 hours, would
! result in a dose of about I mR at the site boundary under average meteorological conditions.)
i __
- 8. Major Electrical Sustained loss of offsite power >15 minutes All of the following: Unusual Event Failures (FFDSAR 14.1.2)
- 1. "4.16 kv bus undervoltage"
& 0 volts on A03 & A04 voltmeters.
- 2. XO4 to A03 ammeter on'CO2 (0 amps).
- 3. XO4 to A04 ammeter on CO2 (0 amps) l l
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EPIP 1.1 Table 1-1 Page 6 Emergency Category Initiating Condition Indication Used Classification Sustained loss of onsite AC power capability Both of the following: Unusual Event
(>15 minutes)
- 1. "4.16 kv bus undervoltage" &
0 volts on A05 and A06 voltmeters and
" Emergency Diesel Starting System Disabled" for both Diesels Loss of all vital onsite DC power >15 minutes Both of the following: Site Emergency
- 1. " Annunciator power failure" on 001, CO2, C03, and C04
. 2. <100 volts on the voltmeters for all batteries Loss of offsite power and loss of all onsite AC A J of the following: Site Emergency power for >15 minutes
- 1. "4.16 kv bus undervoltage" 0 volts on A03, A04, AOS, A06 & "Emerg Diesel starting system disabled" for both Diesels 2, XO4 to A03 ammeter on CO2 (0 amps)
- 3. X04 to A04 ammeter on CO2 (0 amps) i Loss of offsite and all onsite AC power with loss of All of the following: General Emergency all auxiliary feedwater for >2 hours
- 1. Unit aux W meter XO2 on CO2 (0 m )
- 2. Station aux W meter XO4 on CO2 (0 W )
- 3. XO4 to A03 ammeter on CO2 (0 amps)
- 4. XO4 to A04 aseter on CO2 (0 amps)
- 6. Xo2 to A01 ammeter on CO2 (0 amps)
- 7. a. No auxiliary feedwater flow
[FI-4036, FI-4037]
- b. Decreasing SG level -
"A" SG lLI-461, LI-462, LI-463]
"B" SG [LI-471, LI-472, LI-473]
- 9. Control Ro.;m Evacuation Evacuation of control room >15 minutes & As required by DSS Site Emergency no control at remote shutdown station LO. Fire Fire in vital area or on the controlled side of, plant As reported by Fire Brigade Chief Unusual Event ,
lasting >10 minutes after initial use of fire extinguishing equipment.
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EPIP 1.1 Table 1-1 Page 7 Energency Initiating Condition Indication Used Classification s category Fire affecting 1 train of safety systems. As reported by Fire Br,igade Chief Alert t
Fire affecting 2 trains of safety systems As reported by Fire Brigade Chief Site Emergency Nonfunctional indications or alarms it. the control Both of the following: Unusual Event
- 11. Plant Shutdown Function room on primary system parameters requiring plant
- 1. " Annunciator power failure" on C04.
- 2. Failed indication as determined by DSS.
Turbine mechanical failure with consequences 1. Annunciator " Turbine supervisory." Unusual Event
- 2. Indication on TR-6019 of bearing vibration
>7 mils.
- 3. Bearing vibration alarm on back of C03.
- 4. Visual confirmation of turbine housing penetration by a blade or disc.
Significant loss of effluent monitoring capability & 1. Loss of LW16 during a release Unusual Event meteorological instruments which impairs ability to or perform emergency assessment. Loss of effluent 2. Loss of R18 during a release monitoring may/may not require plant shutdown. or
- 3. a. Loss of wind speed indication or wind direction indication snd
- b. Loss of R14 Lnd RMS II Channel 1 or
- c. Loss of R15 and CR9 and RMS II channel 5 or
- d. Loss of R21 and RMS II Channel 2 or
- e. Loss of GWil2 and RMS II channel 6 Alert Failure of reactor protection system to All of the following:
complete a trip which brings reactor subcritical Unplanned first out annunciator on C04 with confirmation from associated indicator and intermediate range detector output not decaying end >l RCC KPI indicates fully withdrawn
d I
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\ J a EPIP 1.1 Table 1-1 Page 8 Emergency category Initiating condition Indication Used classification All alarms (annunciators) lost >l5 minutes while unit 1. " Annunciator power failure" on Col, CO2 & Alert is not in cold shutdown 1(2)C03, 1(2)C04 Loss of functions needed for cold shutdown for >4 Any of the following: Alert hours while at cold shutdown
- 1. Loss of service water Unit 1 = south & west header .
Unit 2 = north & west header-
- 2. Loss of both trains of RHR
- 3. Loss of component cooling
- 12. Abnormal Radiation a. Effluent monitors detect levels corresponding to Airborne effluents only Site Emergency Levels at Site any of the following:
(1) >50 mR/hr for \ hour (2) >250 mR/hr for hour for the thyroid (3) >500 mR/hr whole body for 2 minutes (4) >2500 mR/hr to the thyroid for 2 minutes at the site boundary for adverse meteorology
- c. Any of the dose rates projected, based on plant parameters
- a. Effluent monitors detect levels corresponding to Airborne effluents only General Emergency either:
(1) 1 R/hr whole body (2) S R/hr thyroid at the site boundary under actual meteorological
+
conditions
- c. Either of above dose rates projected based on other plant parameters
- 13. Fuel Handling Accident Major damage to irradiated fuel in containment Both of the following: Alert
- 1. As reported to DES by Core Loading Supvr.
- 2. Alarm on Victoreen on manipulator & alarm on R11
s C' '
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EPIP 1.1 Table 1-1 Page 10 Emergency Category Initiating Condition Indication Used Classification
- 17. Natural Events Any earthquake Activation of >2 accelerograohs Unusual Event Any tornado visible from site verification by operations Supervisor Unusual Event Low Lake Michigan water level with no CW pumps running, water level is 3.9' Unusual Event below O' on sorge chamber level & confirmed by measuring forebay level at 10.9' below pumphouse floor (7' level)
Earthquake greater than operating basis earthquake Earthquake with attendant structural damage of Alert containment or spent fuel pit Any tornado striking the facility Visual observation by operations Supervisor Alert Seiche near dasign level >6" of water in turbine hall Alert Winds in eccess of design levels Wind speed indicated as >100 mph Alert Wind with damage Structural damage to containment Site Emergency Failure of protection for vital equipment at low Any of the following: Site Emergency levels (i.e., caused by seiche > design levels)
- 1. >3' water in both EDG rooms.
- 2. >2' water in vital switchgear room.
- 3. >2' water in auxiliary feed pump room.
- 18. Reactivity Transient Uncontrolled rod withdrawal (FFDSAR 14.1.1 & 14.1.2) Unusual Event CVCS Malfunction (FFDSAR 14.1.5) Unusual Event Accidental Crit'cality NRC Only (3) 4
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EPIP 1.1 Table 1-1 Page 9 Emergency Indication Used Classification Category Initiating Condition Both of the following: Alert Fuel damage accident with release of radioactivity to auxiliary building (FFDSAR 14.2.1) 1. As reported to DSS by Supvr in charge of fuel handling & drusming area vent (R21)
- 2. Alarm on Victoreen on spent fuel pit bridge.
\
Reported as judged by DSS Unusual Event
- 14. Serious or Fatal Injury Transportation of seriously or fatally injured individual from site to hospital (expect hospitalization for at least (Reference EPIP 11.1) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)
Per MASP & Appendices Security threat or attempted sabotage Per NASP
- 15. Security Threat 1-Hour Red Phone Only
- or (open Line) (4)
Ongoing security compromise Visual observation of Operations Supervisor or Unusual Event
- 16. Hazards to Plant Unusual aircraft activity over facility security force operation As reported to DSS by plant personnel making Unusual Event Near or onsite explosion or flammable or toxic gas release visual observation Missile impacts from any source on facility visual observation by Operations Supervisor Alert Missile impact causing damage to two trains of Visual observation by Operations Supervisor Site Emergency safety systems A'ircraft crash'in protected area (within the fence) Visual observation by operations Supervisor Alert Known explosion damage to facility affecting plant Visual observation by operations Supervisor Alert
, operation. Toxic or flammable gases in facility environment excluding normal process gases Visual observation by Operations Supervisor Site Emergency Toxic or flammable gases entering into vital areas (control room, auxiliary building, etc.) excluding normal process gases
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\ L, O' EPIP 1.1 Table 1-1 Page 11 Emergency category Initiating condition Indication Used classification
- 19. Load Transient Loss of Electrical Load (FFDSAR 14.1.10) Unusual Event
- 20. Other Condition that warrants State and/or local official DCS & DSS concurrence Unusual Event awareness Condition that warrants establishment of technical DCS & DSS concurrence Alert support center & emergency support center condition that warrants use of monitoring teams DCS & DSS concurrence Alert Personnel contamination Health Physicist & DCS concurrence NRC-only 1-hour (10)
Any unplanned reactor trip DCS & DSS concurrence NRC-only 1-Hour (7)
Strike by employees or guard force DCS & DSS concurrence NRC-only 1-Hour (12)
Loss of red phone (ENS) DCS & DSS concurrence NRC-only 1-Hour (13)
Personnel or procedural error DCS & DSS concurrence NRC-only 1-Hour (6) 10 CFR 20.403 DCS & DSS concurrence NRC-only 1-Hour (!!)
4 0
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4 EPIP 7.1.1 MINOR Revision 1 03-17-82 CHEMISTRY & HEALTH PHYSICS GROUP PERSONNEL NOTIFICATION AND INITIAL RESPONSE WHEN CHEMISTRY & HEALTH PHYSICS PERSONNEL ARE ON SITE 1.0 PURPOSE The purpose of this procedure is to establish guidelines for the initial response of the Chemistry & Health Physics Group in support of a Site or General Emergency which may require evacuation of the main plant building while Chemistry & Health Physics personnel are on site. A rapid and organized response by the Chemistry & Health Physics Group is necessary to facilitate early assessment of site radiological conditions. The three major areas of concern are as follows:
- a. The area within the prote::ted area including the plant buildings.
- b. The area outside of the protected area but within the exclusion area (site boundary perimeter lines).
- c. Those areas off-site (beyond the exclusion area).
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Health Physics response team assignments (refer to EPIP 7.2.1) will be made by a Health Physics Supervisor after a preliminary assessment (EPIP 1.0) of plant / site radiological conditions.
2.2 Assigned personnel will wear the prescribed protective clothing, dosimetry devices, and other prescribed protective equipment when on their job assignments.
2.3 Whenever possible, standard health physics procedures are to be followed.
2.4 It is to be understood that these are implementation guidelines and that the existing plant and radiological conditions may necessitate changes to these guidelines and/or the sequence in which they are implemented.
3.0 CHEMISTRY & HEALTH PHYSICS GROUP INITIAL RESPONSE 3.1 Upon notification that an Alert, Site, or General Emergency is in effect, all Chemistry & Health Physics Group personnel on site not already assigned an emergency function will report to the health physics station.
a s 1
- l 2 1 i EPIP 7.1.1 l Page 2 O 3.2 Upon arrival at the health physics station, all Chemistry & Health Physics personnel shall remain alert for further instructions con-cerning the need for limited or plant evacuation (EPIP 6.0) or the need for search and rescue efforts (EPIP 12.0).
, 3.3 The acting Health Physics Supervisor will have a roll call taken to ensure that all Chemistry & Health Physics Group personnel on duty ,
are present. Personnel not accounted for will be paged. The Health Physics Supervisor will notify the Security staff of missing per-sonnel.
3.4 The Chemistry / Health Physics Supervisor (Superintendent - Chemistry &
Health Physics) or his designated alternate will report to the tech-nical support center and be prepared to implement EPIP 7.2.2,
" Activation of Health Physics Facilities at the Operations Support
. Center," as required.
4.0 CHEMISTRY & HEALTH PHYSICS GROUP RESPONSE IN THE EVENT OF A PLANT EVACUATION OR NEED FOR PROTECTED AREA OR OFF-SITE SURVEYS 4.1 In the event of a plant evacuation, the Health Physics Director
, (Health Physicist) or his designated alternate will report to the site boundary control center and begin implementation of EPIP 7.2.1,
" Site Boundary Control Center Activation' Plan," as appropriate. In (v) addition, the emergency vehicle will be utilized for transportation to the site boundary control center. If plant evacuation has not been declared, but protected area /off-site surveys are required, the Health Physics Director (Health Physicist) will report to the health physics station and make assignments as necessary.
4.2 The acting Health Physics Supervisor assigned to the health physics station should utilize Appendix "A" to verify completion of the procedural steps to follow.
4.3 .Under the direction of a Health Physics Supervisor, Chemistry &
Health Physics personnel will collect and make ready for use the
~
. equipment listed below or their equivalents:
Dosimeters (0-500 mR) As available Dosimeters (0-5000 mR) 25 ea.
Dosimeter chargers 2 ea.
! Rad Owl One 1 ea. .
Mini-scaler and battery pack 1 ea.
HPI-1010 1 ea.
PIC-6A .
5 ea.
d 530 (Canberra Model 30)
Baird Mo'el 1 ea.
Self-contained breathing units 4 ea.
Other instruments and equipment as designated O
, ,y-, .- - - - - . _ - - ---- - - - -
. .- - - , , - - - - - , - . , , - .- - ~ , - - -
E EPIP 7.1.1 Page 3 4.4 In the event of a plant evacuation, the Health Physics Supervisor will:
4.4.1 Assign personnel as follows:
OSC/TSC SBCC HP Supervisors (2) Nuclear Plant Specialist-HP (2)
Nuclear Plant Specialist- Rad Control Operators (4)
Chemistry (2) Rad / Chem Technicians (2)
Rad Control Operators (4) A0T assigned to HP (All)
Rad / Chem Technicians (4) 4.4.2 Assign one site boundary control center individual to get e carryall vehicle (other than the assigned site emergency vehicle) and wait with the vehicle at the west entrance door near Ready Stores. This vehicle will be used to transport equipment to the site boundary control center.
4.4.3 Assign two technical support center / operations support center individuals to move the Baird Model 530 SCA or the Canberra Model 30 MCA and detector to the technical support
,p center / operations support center or to an alternate area
't j determined by the Chemistry / Health Physics Supervisor. Upon b completion of this assignment, they are to proceed to the site boundary control center.
4.5 In the event of either a plant evacuation or need for off-site sur-veys, the acting Health Physics Supervisor will verify that all required equipment indicated in Section 4.3 has been obtained.
4.6 On completion of the above procedural guidelines, the acting Health Physics Supervisor will direct Chemistry & Health Physics Group personnel assigned to the site boundary control center to report utilizing private vehicles and/or health physics assigned Company vehicles (maximum of two).
4.7 Upon arrival at the site boundary control center, personnel are to proceed in accordance with EPIP 7.2.1, " Activation of Health Physics Facilities at the Site Boundary Control Center."
APPENDIX "A"
~~ EPIP 7.1.1 CHECKLIST CHEMISTRY & HEALTH PHYSICS GROUP PERSONNEL NOTIFICATION AND INITIAL RESPONSE WHEN CHEMISTRY & HEALTH PHYSICS PERSONNEL ARE ON SITE i Date INITIALS TIME
- 1. Chemistry & Health Physics Group personnel report to the health physics station. (section 5.1 and 5.2)
- 2. All Chemistry & Health Physics Group personnel on duty present and/or accounted for. (Section 5.3)
- 3. Chemistry / Health Physics Supervisor (Superintendent -
Chemistry & Health Physics) has been notified of accountability.
- 4. If plant evacuation has been declared, proceed with EPIP 7.1.1. If plant evacuation has not been declared but protected area /off-site surveys are t[ \ required, proceed as directed by the Health
's '
Physics Director (Health Physicist).
- 5. Health Physics Director (Health Physicist) has obtained the emergency vehicle and reported to the site boundary control center or to the health physics station. (Section 6.1)
- 6. The acting Health Physics Supervisor at the health physics station will direct chemistry &
Health Physics personnel to collect and make ready for use the following equipment or their , _ " '
equivalents. (Section 4.3)
- a. Dosimeters (0-500 mR) As available
- b. Dosimeters (0-5000 mR) 25 ea.
- c. Dosimeter chargers 2 ea.
- d. Rad Owl One 1 ea.
- e. Mini-scaler and battery pack 1 ea.
- f. HPI-1010 1 ea.
- g. PIC-6A 5 ea.
- h. Baird Model 530 or Canberra Model 30 1 ea.
- i. Self-contained breathing units 4 ea.
- j. Other instruments and equipment as designated by Chemistry & Health Physics supervision O
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ks _s INITIALS TIME
- 7. For a plant evacuation, acting Health Physics Supervisor will: (Section 4.4)
- a. Assign personnel to the TSC/OSC to initiate EPIP 7.2.2, " Activation of Health Physics Facilities at the TSC/OSC." (Section 4.4.1)
- b. Assign one individual to get a carryall vehicle and wait at the west entrance door by Ready Stores. (Section 4.4.2) ,
- c. Assign two individuals to move the Baird Model' 530 or Canberra Model 30 to the technical support center or an alternate area determined by the Chemistry / Health Physics Supervisor.
(Section 4.4.3)
- 8. Monitor loading of equipment (Section 4.3) into l carryall and direct driver to proceed to the site boundary control center. (Section 4.5) l
- 9. Direct Chemistry & Health Physics personnel to l
\ proceed to the site boundary control center or TSC/OSC as assigned. (Section 4.6)
- 10. Upon arrival at site boundary control center.
Proceed in accordance with EPIP 7.2.1, " Activation of Health Physics Facilities at the Site Boundary Control Center."
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EPIP 7.1.2 MINOR Revision 1 hv 03-17-82 CHEMISTRY & HEALTH PHYSICS GROUP PERSONNEL NOTIFICATION AND INITIAL RESPONSE WHEN CHEMISTRY & HEALTH PHYSICS PERSONNEL ARE OFF SITE 1.0 PURPOSE
- The purpose of this procedure is to establish guidelines for the initial response of the Chemistry & Health Physics Group in support of an Alert (as required), Site or General Emergency during other than normal duty hours when Chemistry & Health Physics personnel are not on site. A rapid and organized response by the Chemistry & Health Physics Group is necessary to assist in early assessment of plant and site radiological conditions. The three major areas of concern are as follows:
- a. The areas located within the protected area including inside of plant buildings.
- b. The areas located outside of the protected area but within the ex-clusion area (site boundary perimeter lines).
(
x-- c. Those areas off-site located outside of the exclusion area.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Health physics response team assignments (refer to EPIP 7.2.1) will be made by a Health Physics Supervisor after a preliminary assessment (Section 1.0) of site radiological conditions.
2.2 Assigned personnel will wear the prescribed protective clothing, dosimetry devices, and other prescribed protective equipment when -
conducting their job assignments.
2.3 Whenever possible, standard health physics procedures are to be followed at all times.
3.0 CHEMISTRY & HEALTH PHYSICS GROUP RESPONSE 3.1 All Chemistry & Health Physics Group personnel will report to the site boundary control center or stand by at their place of residence as directed by the notification telephone call.
3.2 The Chemistry / Health Physics Supervisor (Superintendent - Chemistry &
Health Physics), Health Physics Director (Health Physicist), and the i Chemistry & Health Physics Duty & Call Supervisor or their designated fv l
I
EPIP 7.1.2 Page 2 alternate will, upon arrival at the site boundary control center, inquire as to the status of the plant radiological assessment (EPIP 1.0).
3.3 Dependent upon the existing plant radiological conditions, the Chemistry / Health Physics Supervisor, Health Physics Director, 4
Chemistry & HeaJth Physics Duty & Call Supervisor, or their desig-nated alternates, will at this time, determine the necessity for activating the health physics facilities of the site boundary control center and the operations support center as follows.
3.3.1 No Plant Evacuation
- a. Chemistry & Health Physics personnel will proceed to the health physics station and establish controls for entry into the auxiliary building and begin implementation of EPIP 7.1.1, " Chemistry & Health Physics Group Personnel Notification & Initial Response when Chemistry & Health Physics Personnel are On Site," as directed by the
, Health Physics Director.
i 3.3.2 Plant Evacuation If plant evacuation is declared, proceed as follows in b Section 4.0.
4.0 PLANT EVACUATION DECLARED 4.1 Chemistry & Health Physics Group personnel, upon arrival at the site boundary control center, will be directed to begin implementation of EPIP 7.2.1, " Activation of Health Physics Facilities at Site Boundary Control Center."
4.2 Dependent upon habitability, the Chemistry / Health Physics Supervisor j or his' designated alternate will proceed to.the technical support center whenever a.second Chemistry & Health Physics Supervisor is available at the site boundary control center.
4.3 As Chemistry & Health Physics personnel become available, the Health Physics Director will assigh them as fallows:
OSC/TSC SBCC Health Physics Supervisors (all) Nuclear Plant Specialists-HP (all) l Nuclear Plant Specialist-Chem (all) Rad / Con Operators (4)
Radiochemist A0T's Assigned to HP (all)
Rad / Chem Techs (all)
Rad / Con Operators (4) nm 9
%w EPIP 7.2.1 MINOR Revision 2 93-17-82 ACTIVATION OF HEALTH PHYSICS FACILITIES AT SITE BOUNDARY CONTROL CENTER 4
1.0 PURPOSE The primary purpose of this procedure is to provide guidelines for acti-vating the site boundary control center during a Site or General Emergency requiring plant evacuation or in the event that surveys outside the pro-tected area are required. Modifications to these guidelines may be implemented by the Health Physics Director (Health Physicist) to meet the existing plant and site radiological conditions so as to ensure the con-tinued safety of plant personnel and the general public.
2.0 ACTIVATION OF HEALTH PHYSICS FACILITIES AT SITE BOUNDARY CONTROL CENTER 2.1 Health Physics Director The Health Physics Director or his designated alternate is respon-f-~s sible for directing health physics activities at the site boundary
) control center and for providing radiation protection assistance as requested by the Chemistry / Health Physics Supervisor. When the Radcon/ Waste Manager is available, the Health Physics Director should report to him. Appendix "A", Health Physics Director Duties, provides the specific guidelines for accomplishment of these duties.
2.2 Assistant to the Health Physics Director When manpower allows, the Health Physics Director will assign a chemistry & Health Physics Supervisor to perform the duties of Assis-tant :to the Health Physics Director. The Assistant Health Physics
. Director-is responsDale for directing Chemistry & Health Physics i personnel: from the site boundary control center and for the coordi-nation of all health physics related activities with the Health Physics Director. Appendix "B" provides the guidelines for accom-plishment of these duties.
2.3 The following teams will be manned by personnel as assigned by the Health Physics Director or the Assistant to the Health Physics i Director. Team duties are outlined in the respective appendix. 1 I
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(. r. ._._._.._...___-__.____..
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i EPIP 7.2.1 '
i Page 2 O Team Appendix Site Boundary Control Center / Radiation Control Team B l
Counting Team C l Survey Teams C ,
l' Kewaunee Shuttle Team C i
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6 l EPIP 7.2.1 Page 3 APPENDIX "A" -
SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS DIRECTOR RESPONSIBILITIES AND DUTIES
. 1. Obtain environmental-data (wind speed, direction and stability class) l from the Chemistry / Health Physics Supervisor in the technical support center.
! 2. Use results from EPIP 1.4, " Radiological Dose Evaluation," and EPIP 1.5, l " Protective Action Evaluation," procedures and determine the extent
- and location for the initial and followup environmental surveys as
- required.
- 3. .When manpower allows, designate a chemistry & Health Physics Super-visor to perform the duties of Assistant to the Health Physics Di rector at the site boundary control center (EPIP 7.2.1, Appendix "B").
If manpower is not sufficient, perform the duties listed in Appendix "B".
- 4. Coordinate with the RadCon/ Waste. Manager, when available, control and
( j exposure documentation within the exclusion area and off-site.
- 5. Coordinate with the RadCon/ Waste Manager when available on the evalu-ation of environmental radiological survey results, project dose l consequences, and make recommendations consistent with the Emergency Plan with respect to the general population (EPIP 1~.4 and EPIP 1.5).
- 6. Coordinate off-site surveys with Radiation Control / Waste Manager when available.
- 7. Assist in evaluating medical emergencies and coordinate use of the
- site emergency vehicle with the Chemistry /. Health Physics Supervisor.
. 8. Establish access controls to coordinate access to the operations 1
support center and the protected area. Ensure that all personnel entering or exiting the site are properly accounted for and are
! equipped with the necessary' dose evaluation devices, i
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EPIP 7.2.1 Page 4 l
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APPENDIX "B" SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES ASSISTANT TO THE HEALTH PHYSICS DIRECTOR 1
Direct the available Chemistry & Health Physics Group personnel in
~
1.
setting up and making available for use all site boundary control center health physics equipment. Verify the availability and opera-tional status of equipment after it is checked out.
- 2. Designate Chemistry & Health Physics personnel to man the following radiation control teams as personnel become available for duty.
- a. Counting team (one Nuclear Plant Specialist-HP, one Radiation Control Operator).
- b. Survey teams; two, two-man teams. One survey team should be i given primary responsibility for plume and whole body gamma
', measurements at locations to be specified.
- c. Site boundary control center / radiation support team (remaining I '_\
\ ! Radiation Control Operators and Auxiliary Operator Trainees).
- d. Kewaunee shuttle team (if required).
- 3. Initiate health physics radio communications network (KRQ-717) radio check. Ask control room personnel to ask Appleton to minimize radio traffic.
- 4. Receive environmental radiological survey instructions from the Health Physics Director and direct survey team leader to conduct the surveys.
~
- 5. Coordinate all environmental radiological surveys. Ensure that all surveys are properly logged and identified. ,
- 6. Coordinate counting of air samples and smear surveys with the counting team leader. Receive and review the completed sample results from the sample team leader.
- 7. Report all environmental radiological surveys in their completed form to the Health Physics Director for evaluation.
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EPIP 7.2.1 Page 5 d
- 8. Coordinate with the Health Physics Director on samples requiring multi-channel analyzer counting. Direct the site boundary control center / radiation support team leader to transport samples to the operations support center or as otherwise directed for MCA counting.
Receive and report the completed analysis to the Health Physics Director.
SITE BOUNDP.RY CONTRCL CENTER HEALTH PHYSICS RESPONSIBILITIES SITE BOUNDARY CONTROL CENTER / RADIATION CONTROL TEAM
- 1. Set up and verify operational status of personnel friskers.
- 2. Monitor personnel and equipment for contamination and perform decon-tamination as necessary.
- 3. Implement control and documentation of personnel entering or ~ exiting the exclusion area.
- 4. Implement controls for dosimetry issue, use, and documentation of r-'S personnel exposure and control of exposure data.
(V- 5. Coordinate all health physics activites with the Assistant to the Health Physics Director.
- 6. Perform other duties as directed.
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cEPIP 7.2.1 Page 6 1 l
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APPENDIX "C" SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES COUNTING TEAM
- 1. Set up and verify the operational status of all site boundary control center counting equipment.
- 2. Log all environmental radiological samples and sc. ear' surveys. Count all samples and smear surveys. Calculate activities and document results. Report all analysis results to the Assistant to the Health Physics Director.
- 3. Perform other duties as directed.
SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES SURVEY TEAM
- 1. Set up and verify the operational status of the site boundary control
{(^N) center air sampling and radiological survey equipment.
- 2. Conduct all radiological surveys and air sampling. Record all air sample data and radiological survey results.
- 3. Ensure that all air samples and radiological surveys are properly logged and identified prior to turn in to the Assistant to the Health Physics Director.
- 4. Perform other duties as directed.
SITE BOUNDARY CONTROL CENTER HEALTH PHYSICS RESPONSIBILITIES KEWAUNEE SHUTTLE TEAM
- 1. Transport samples to Kewaunee Nuclear Plant for analysis as directed .
by the Assistant to 'the Health Physics Director.
- 2. Document results of analysis and report results to the Health Physics ,
Director by radio (KRQ-717) or telephone.
- 3. Perform other duties as directed.
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1 e l EPIP 7.2.2 MINOR Revision 1
, ( 03-17-82 1
i ACTIVATION OF CHEMISTRY & HEALTH PHYSICS AT '
TECHNICAL SUPPORT CENTER /0PERATIONS SUPPORT CENTER l
1.0 PURPOSE 1.1 The purpose of this procedure is to establish guidelines for acti-
! vating the Chemistry & Health Physics facilities at the technical support center / operations support center (TSC/OSC) in support of an emergency. situation which may require evacuation of the main plant buildings.
1.2 The Chemistry / Health Physics Supervisor and certain designated mem-
] bers of the Chemistry & Health Physics Group are responsible for activating the health physics equipment at the TSC/OSC The extent i and sequence of implementation of these guidelines will be outlined in EPIP 7.1.1.
i 2.0 ACTIVATION OF HEALTH PHYSICS FACILITIES AT TSC/OSC 2.1 For emergency conditions during which a plant evacuation is not required, the Chemistry / Health Physics Supervisor and Health Physics Director will determine to what extent, if any, health physics cover-age will be provided at the TSC/OSC.
2.2 For emergency conditions which require plant evacuation, Appendix "A" guidelines of EPIP 7.1.1 should be followed. The sequence for imple-
! mentation of Appendix "A" guidelines depends upon whether Chemistry &
t Health Physics Group personnel are on or off-site when notification is received (EPIP 7.1.1 and EPIP 7.1.2). -
- 3.0 HEALTH PHYSICS RESPONSIBILITIES FOR TSC/OSC/ RAD SUPPORT TEAM -
3.1 When Chemistry & Health Physics Personnel'are On-Site (EPIP 7.1.1) j 3.1.1 Obtain five (5) PIC-6A survey instruments.
3.1.2 Proceed to the TSC/OSC and: ,
.a. Hove the AMS-2 continuous air sampler (cart-mounted)
. into the TSC/OSC hallway and set up for operation.
v
- 4 5
EPIP 7.2.2 Page 2 Oa
- b. Place the Vamp area monito; .a south gate in oper-ation.
- c. Set up and place into operation the south gate low l volume air sampler.
I 1
- d. Collect two portable radios (KRQ 717) and:
- 1. Return one (1) radio (KRQ 717) to the TSC.
- 2. The second radio (KRQ 717) should be taken to the OSC counting room.
- e. Proceed to the TSC/OSC and begin preparation to provide health piirsics support as described under OSC/HP equip-ment activation, Section 3.3 of this procedure.
3.2 Notification When Chemistry & Health Physics Personnel are Off-Site (EPIP 7.1.2) 3.2.1 Upon receipt of instruction to activate the TSC/OSC, one member of the OSC/ rad support team will proceed to the ESC
!Q located in the basement of the Energy Information Center
) and:
- a. Set up and place into operation the low volume air sampler and Vamp area monitor.
- b. Perform a communications check of the portable radio (KRQ 717) located in the Duty Technical Advisor's sleeping quarters.
- c. Proceed to the TSC/OSC.
3.2.2 The remainder of the OSC/ rad support-team will proceed to the south gate and:
- a. Set up and place into operation the Vamp area monitor and the low volume air sampler at the south gate.
- b. Pick up two (2) portable radios (KRQ 717) and distribute as in Step 3.1.2(d) above.
3.2.3 Proceed to the TSC/OSC and move the AMS-2 continuous air sampler (cart-mounted) into the TSC/OSC hallway; set up and place the AMS-2 into operation.
3 . 2 .,4 Begin preparation to provide health physics coverage as t/
s) described under OSC/HP equipment activation, Section 3.3 of this procedure.
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p EPIP 7.2.2 Page 3 3.3 0SC/HP Equipment Activation 3.3.1 Prepare the health physics equipment from the emergency locker for use.
3.3.2 Prepare KRQ 717 radio for communications check.
3.3.3 Provide health physics support as required at the TSC/OSC and in-plant support as requested by the Chemistry / Health Physics Supervisor.
3.3.4 Assist in response to medical emergencies within the pro-tected area (EPIP 11.0). '
3.3.5 Coordinate with the Chemistry / Health Physics Supervisor at '
the TSC/OSC on in plant personnel exposure and documenta-tion.
3.3.6 Verify that all personnel who are departing from the OSC are certain as to details of their approved assignments and are complying with all health physics requirements. Whenever practicable, entries into high radiation or airborne areas
(~ will be made under the radiation work permit system.
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W EPIP 7.2.4 MINOR Revision 1 03-17-82 i
HEALTH PHYSICS COMMUNICATIONS 1.0 PURPOSE The purpose of this procedure is'to provide communications guidelin'es for the Chtniistry & Health Physics group to assist in the perfonnance of their duties during an Emergency Plan situation requiring plant evacuation and/or in the event that surveys outside of the protected area are required.
2.0 COMMtINICATIONS, GENERAL i 2.1 Radiological response activity communications between the health physics response teams (EPIP 7.2.1) will normally be accomplished utilizing the KRQ 717 radio network. Telephone communications should be held to a minimum.
2.2 The following locations of KRQ 717 radios will be maintained during a Site or General Emergency:
k .
y Location Tm 2.2.1 Control Room Base station 2.2.2 Technical Support Center Portable
- 2.2.3 Operations Support Center Portable
- l 2.2.4 Site Boundary Control Center Portable 2.2.5 Emergency Vehicle Mobile 2.2.6 Other Plant Vehicles (2 each) Mobile 2.2.7 Emergency Support Center Portable **
- 0btained from south gate guardhouse
, **0ne available from Duty Technical Advisor rest station 2.3 KRQ 717 radio communications network functional check:
2.3.1 Upon arrival at their assigned locations, health physics personnel shall place the radios (KRQ 717) in an operating mode and stand by for a radio check. The site boundary control center is responsible for' initiating the radio J
check. The results of the communications check should be recorded in the site boundary control center logbook.
2.3.2 Mobile or portable radio units should also be given a func-tional check prior to departing from the site boundary I
control center for the performance of assigned duties.
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EPIP 7.2.4 Page 2
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2.3.3 Communications between portable or mobile radio units is limited by the distance or terrain between them. In some i cases, communications to another portable or mobile unit will have to be relayed through the control room base station.
2.3.4 Radio antennas must not be in contact with metal structures when being used to transmit.
3.0 RADIO PROTOCOL 3.1 To eliminate confusing radio transmissions and to expedite communi-cations, the following should be adhered to:
t 3.1.1 Identify the radio call-sign and your unit or location at the start of each transmission.
EXAMPLE: THIS IS KRQ 717, SURVEY TEAM #1 3.1.2 Identify unit or location being called.
EXAMPLE: THIS IS KRQ 717, SITE BOUNDARY CONTROL CENTER
(} CALLING THE TECHNICAL SUPPORT CENTER.
(U 3.1.3 Use of radios are for business purposes only.
3.1.4 Limit the time of all transmissions.
3.1.3 FCC regulations prohibit the use of vulgar or profane language.
3.1.6 Upon completion of the conversation, sign off as follows:
EXAMPLE: KRQ 717, SURVEY TEAM #1, CLEAR & STANDING BY.
4.0 USE OF TELEPHONES 4.1 The use of the telephone communications network by health physics personnel during an Emergency Plan situation will be limited to the following:
4.1.1 NRC Health Physics Dedicated Line These lines are located in the Chemistry & Health Physics group office and at the site boundary control center. They provide a means of direct communications with the NRC health physics offices during an emergency. The use of these lines
. will be only as directed by the Chemistry / Health Physics i Supervisor, the Health Physics Director or other ranking s plant supervisors.
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cy EPIP 7.2.4 Page 3 4.1.2 Plant PBX Telephone System
! This system provides direct dialing between plant locations
! within the on-site and protected areas. The use of these lines is to be limited to business-related calls.
4.1.3 Off-Site Telephone Lines.
These lines provide for direct dialing to off-site loca-tions. The use of these lines is to be limited to '
business-related calls. Use should be minimized to the extent practicable.
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EPIP 7.2.5 MINOR
, N Revision 1 I
03-17-82 CONTROL & USE OF VEHICLES 1.0 PURPOSE The purpose of this procedure is to provide Chemistry & Health Physics group personnel with guidelines for controlling the use of personal and Company vehicles during a Site or General Emergency on a plant evacuation or in the event that surveys outside of the protected area are required.
2.0 COMPANY VEHICLE USE 2.1 Site Emergency Vehicle 2.1.1 During a plant evacuation the emergency vehicle is under the direct control of the Health Physics Director at the site boundary control center. This vehicle is equipped with a mobile radio (KRQ 717) and is designated for emergency medical transportation (EFIP 11.1).
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2.1.3 At any time the emergency vehicle is in use, the operator will ensure that the radio (KRQ 717) is in the operating mode. The emergency vehicle's ignition switch must be on, and the engine running before a radio transmission can be made. -
2.2 Other Company Vehicles -
2.2.1 Mobile radios (KRQ 717) are installed in three (3) Company carryall-type vehicles, including the emergency vehicle.
Two of these vehicles, including the emergency vehicle, are assigned to health physics during an emergency situation.
The third vehicle will be utilized by the security guard force.
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2.2.2 TherearetenCompanyvehiclesthatarenoteduippedwith mobile radios. They are as follows: , s x w ~
Stakebed truck 1 each N' '
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Security truck 1 each ' '-
Sedan 4WD 6 each '
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3.0 PERSONAL VEHICLE USE IN SUPPORT OF A SITE OR GENERAL EMER_GENC'Y .-
3.1 Due to the varying requirements for transportation which might be s experienced during an emergency condition, it may become'necessary ,
for personnel to utilize their personal vehicles in'a,ccomplishment of their assigned duties. The following guidelince-shall be followed:
l 3.1.1 The Chemistry / Health Physics Supervisor-or tl's Health' Physics Director may authorize the use of personal-vehicIps in the accomplishment of assigned duties. ,
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3.1.2 Personnel utlizing their personal vehicles shall maintain a record of mileage driven and furnish such record to a,Che.m-l istry & Health Physics Supervisor for verification of-Q'Q reimbursement claims.
s 4.0 EMERGENCY DELIVERY OF TLD'S '
i Should it be necessary, a Company vehicle will be utilized to'.trassport' TLD's to the vendor for emergency processing. w
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D' c- EPIP 7.3.1 MINOR O Revision 3 03-17-82 AIRBORNE SAMPLING & DIRECT DOSE RATE SURVEY GUIDELINES 1.0 PURPOSE N The purpose of this procedure is to establish guidelines for (1) the collection of various air samples, and (2) the performance of direct plume and ground deposition surveys for use in verifying the initial dose rate estimates obtained in EPIP 1.4, "Radiclogical Dose Evaluation."
s 2.0 PRECAUTIONS AND LIMITATIONS 2.1 Personnel assigned to survey teams shall wear the prescribed pro-tective clothing, dosimetry devices, and other protective equipment as required when conducting surveys.
i 2.2 Survey teams shall be aware of the exposure authorized for a specific job assignment and shall not exceed the maximum authorized exposure.
"N 2.3 Survey teams shall carry survey instruments and continuously monitor
(' the areas they are entering.
' " 2.4 Standard Health Physics procedures are to be followed if and when radioactive contaminated material is being handled.
3.0 GENERAL INFORMATION 13.1 To accomplish the objectives of this procedure, with a minimum of delay, survey teams will be designated by the Health Physics Director and/or Assistant Health Physics Director (EPIP 7.2.1). These survey teams will obtain airborne (particulate, iodine, noble gas) and direct plume and ground: deposition beta-gamma and beta dose rate surveys as directed from specific locations within the exclusion zone-and, if deemed necessary, from specified off-site locations.
3.2 To facilitate identification of sample locations, the area sur-rounding the plant has been identified by quadrants radiating outward at 22.5 degree angles. Each quadrant has been identified by a letter
~
_ of the alphabet starting with the letter "A" and radiating clockwise from due north. To avoid confusion, the letters "I" and "0" are not used. ,The Health Physics Director or Assistant Health Physics Director will indicate the designated survey locations to the survey team leader on appropriate survey maps (EPIP-01 and EPIP-02).
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.' EPIP 7.3.1 Page 2 3.3 The attached partial listing of Maximum Permissible Concentrations (MPC) in air of selected isotopes will aid in determining exposure limits to airborne materials. For isotopes not listed, refer to Table 1, Column 1, of 10 CFR 20.
l 4.0 AIR SAMPLING INSTRUCTIONS 4.1 Standard health physics air sampling procedures will normally be utilized whenever possible. The following samples will be collected at each location unless otherwise directed. Record all airborne sample data on EPIP-01.
Type Sample Sample Volume Air particulate 1 E 6 cc (1)
Iodine 1 E 6 cc (1)(3)
Noble gas 1,075 cc (2)
Note 1: Air sampler flow rates vary depending upon the type of sampler used. The battery-powered air samplers normally provide the lowest flow rates (4 cfm). To obtain the suggested minimum sample volume a sample time of 10 minutes (p
h should be used. For sample flow rates less than 4 cfm the total sample time should be extended.
Note 2: One liter (1,075 cc) polybottles will be used to collect noble gas samples.
1 Note 3: If significant noble gas is suspected, silver zeolite filter cartridges will be used for iodine collection.
4.2 When collecting air samples, the following precautions should be observed.
4.2.1 The air sampler should be placed approximately four to five feet above the ground so as to sample the breathing zone. DO NOT place the air sampler on the ground.
! 4.2.2 During inclement weather it is necessary to shield the
- filters from rain or snow. This may be accomplished by operating the sampler inside of an open vehicle or by pro-viding other methods of shielding.
5.0 DIRECT RADIATION PLUME SURVEYS 5.1 Direct radiation surveys within the plume area provide a means of determining whole body gamma dose rates and for estimating beta dose g rates to the skin. Since most beta gamma survey instruments are i sensitive to the higher beta energies only, it is necessary that a
- V thin window detector be used for plume beta dose rate e'stimations. To obtain estimated beta dose rates using the Eberline Rad Owl instru-ments, proceed as follows. -
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EPIP 7.3.1
< Page 3
- 5.1.1 Hold the instrument (Rad Owl One or Two) approximately four to five feet above the ground with the detector facing .
j upwards in the suspected direction of the plume and obtain a
- gamma dose rate (beta shield covering the detector window). .
j In the event that dose rates from the plume are low, use the j integrating mode on the Eberline Rad Owl One and obtain a i timed integrated dose rate. This should be accomplished for i both the beta-gamma and gamma dose rate. (The HP-1010 survey instrument may also be used to obtain a gamma inte-i grated dose ra.te.) Record results on form EPIP-02. Then, I holding the instrument at approximately the same position,
! remove the beta shield and obtain a beta-gamma dose rate.
. Record results.
2 j 5.1.2 Estimate beta dose rate as follows. Subtract the gamma dose
- rate from the beta-gamma dose rate. Multiply the result by I l 1.5, an empirically determined correction factor suitable t j for Xe-133 betas, to determine an estimate of the beta dose :
rate. Record results.
i NOTE: RADIO THE RESULTS OF THESE DIRECT EXPOSURE MEASURE-MENTS TO THE SITE BOUNDARY CONTROL CENTER AS SOON AS THEY ARE AVAILABLE.
f 5.2 Isotopic Determination of Beta-Gamma Skin Dose Rates from Noble Gases
- 5.2.1 Upon completion of multi-channel analysis of the noble gas
] samples collected in Section 4.1 above, the true beta-gamma l skin dose rate may be calculated using form EPIP-03, or l determined by use of Table 2 (attached).
i 5.3 Thyroid Exposure Calculations l The dose to the thyroid.from airborne concentrations of radioiodine can be estimated using plume gamma whole body dose; rates-and Section 5.3 of EPIP 1.4. It is emphasized that thyroid dose rates derived in this manner greatly overestimate actual conditions. They should l 4 only be used until measurements of airborne iodine concentrations can ;
. be obtained by multi-channel analysis of plume iodine samples. i i
6.0 GROUND DEPOSITION SURVEYS AND CALCULATION !
3 6.1 Ground contamination by radioactive material from the plume may be j determined by direct radiation dose rate surveys as follows.
l 6.1.1 An Eberline Rad Owl type instrument should be used for l
obtaining ground deposition dose rates.
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Page 4 l O 6.1.2 With the beta shield in place and the detector facing the ground (held in a vertical position), obtain the beta-gamma dose rates at positions of one foot and three feet above the surface of the ground. Record results on form EPIP-02.
NOTE: THE FOLLOWING CALCULATIONS OF ESTIMATED GROUND DEPOSITION TAKE INTO CONSIDERATION THAT THE DETECTOR IS AFFECTED BY RADIOACTIVE MATERIAL EVENLY DEPOSITED OVER THE ENTIRE AREA WITHIN ABOUT 10 FEET OR SO OF THE DETECTOR. INSURE THAT THE DETECTOR IS NOT SHIELDED BY BUILDINGS, VEHICLES, ETC., WHEN OBTAINING THE SURVEY READINGS.
6.1.3 Calculate the estimated ground deposition at three feet as follows:
Ground Deposition = Gamma Dose Rate at X 2.6E2 pCi - hr.
in pCi/m 2 3 ft. in mR/hr. m z - mR 6.1.4 Calculate estimated ground deposition at one foot as follows:
(
Ground Deposition _ Gamma Dose Rate at X 1.5E2 Y
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in pCi/m 2 1 ft. in mR/hr. m 3 -
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6.1.5 Record results in Column "G" of EPIP-02 on " Ground Survey Results."
NOTE: CALCULATIONS ARE BASED ON AN AVERAGE OF 0.7 HEV AND PROVIDE A REASONABLE ESTIMATE OF GROUND DEPOSITION OF MIXED FISSION PRODUCTS.
6.2 It should be noted that smear surveys for determining ground contami-nation must be taken with care. The. surface being smeared should be
- l. relatively smooth (vehicle's, metal, mail' boxes, etc.) with a hard
. surface.
6.2.1 In the event smear surveys are not feasible, vegetation type samples may be obtained. For this type of sample, carefully collect the vegetation (grass, leaves, etc.) from an area of.
approximately 100 cm2 . Package in plastic bags and record' the necessary sample data.
6.2.2 Ground scrapings may also be used to determine ground con-tamination. When obtaining this type of sample, care should
,s be used to collect.only the surface material from an area of l approximately 100 cm2 . Package in plastic bags and record l l's>} the necessary sample data.
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EPIP 7.3.1 Page 5 m
U 7.0 ROUTING OF AIR SAMPLES AND SURVEYS FOR COUNTING AND EVALUATION 7.1 Complete documentation of all airborne and direct dose rate surveys is very important. Insure that sample locations are properly identi-fled and that all required information is entered on the air sample (EPIP-01) or survey (EPIP-02) forms. Return all surveys to the Health Physics Director or Assistant Health Physics Director.
7.2 The Assistant Health Physics Director will assign survey numbers and record the following information in the SBCC health physics activi-ties log:
Survey Number Survey Location Type of Survey Time Received at the SBCC Samples will then be directed to the SBCC/ counting team for gross counting and to the operations support center (OSC) or the Kewaunee Nuclear Plant for multi-channel analyzer (MCA) counting as required.
Direct radiation dose rate surveys will be reported to the Health Physics Director for further evaluation.
4 7.3 The SBCC/ counting team will do a gross count all air particulate samples prior to their being sent, if necessary, for multi-channel analyzer counting. They will also purge all silver zeolite and/or charcoal filter cartridges of noble gases in accordance with Attach-ment 7.3.1-1, " Atmospheric Radioactive Iodine Sample Collection and Counting," prior to samples being sent for multi-channel analyzer analysis.
7.4 The SBCC/ radiation support team members will~ normally be utilized for transportation of samples between the SBCC and the OSC.
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- i EPIP 7.3.1 Page 6 TABLE 1 MAXIMUM PERMISSIBLE CONCENTRATIONS - AIR
~
i The following table is a partial listing of isotopes from Table 1, Column 1, of 10 CFR 20. Where different values are listed for both soluable and insoluable j forms, only the most restrictive concentration is listed.
Noble Gases MPC pCi/cc Other Isotopes MPC pCi/cc Ar-41 2 X 10 6 Sb-124 2 X 10 8 Kr-85m 6 X 10 6 Sb-125 3 X 10 8 Kr-85 1 X 10 5 Ba-140 4 X 10 8 ,
Kr-87 1 X 10 6 Bi-212 1 X 10 7 Kr-88 1 X 10 6 Cd-109 5 X 10 8 Xe-131m 2 X 10 5 Ce-141 2 X 10 7 Xe-133 1 X 10 s Ce-144 6 X l'0 9 Xe-133m 1 X 10 s Cs-134 1 X 10 8 j Xe-135 4 X 10 6 Cs-136 2 X 10 7 Cs-137 1 X 10 8 Iodines MPC pCi/cc Cs-138 1 X 10 6 Cr-51 2 X 10 6 I-131 9 X 10 9 Co-57 2 X 10 7 I-132 2 X 10 7 Co-58 5 X 10 8 I-133 3 X 10 8 Co-60 9 X 10 9 I-134 5 X 10 7 F-18 3 X 10 6 I-135 1 X 10 7 H-3 5 X 10 6 Fe-59 5 X 10 8-Alpha Emitters La-140 1 X 10 7 Pb-212 2 X 10 8 Isotope MPC pCi/cc Mn-54 4 X 10 8 Mo-99 2 X 10 7 Unknown 6 X 10 13 Ni-59 --. 5 X 10 7 -
7 Nb-95 1 X 10 6
Rb-88 1 X 10 Ru-103 8 X 10 8 Ru-106 6 X 10 9 Na-22 9 X 10 9 Na-24 1 X 10 7 Te-132 1 X 10 7
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.,.EPIP 7.3.1 Page 7 TABLE 2 i DOSE FACTORS FOR NOBLE GASES (Rem / Hour per pCi/cc)
Isotope S-Skin T-Skin I} Total Skin (3) T-Whole Body (4)
Kr-83m Negligible 2.45 2.45 .00863 Kr-85m 167. 156. 323. 134.
Kr-85 153. 2.18 155. 1.84 Kr-87 1110. 782.
- 1892. 676.
Kr-88 271. 1926. 2197. 1678.
Kr-89 1153. 2192. 3345. 1895.
Kr-90 832. 2065. 2897. 1781.
Xe-131m 54.3 19.8 74.1 10.4 Xe-133m 114. 41.4 155.4 28.7 Xe-133 34.9 44.7 79.6 33.6 Xe-135m 81.2 '
426. 507. 356.
Xe-135 212. 243. 455. 207.
Xe-137 1393. 191. 1584. 162.
Xe-138 471. 1167. 1638. 1008.
( Ar-41 307. 1178. 1485. 1009.
\g (1) Beta dose to skin takes credit for absorption in outer dead layer of skin, 7 mg/cm.
(2) Gamma dose to skin is calculated from gamma dose to air by multiplying by 1.11, the average tissue / air energy absorption coefficient.
(3) Total skin dose is the sum of (1) and (2).
(4) Gamma dose to the whole body takes credit for absorption in the first-5 cm of tissue.
c) Sample Calculation' Assume an air sample analysis indicates a total noble gas activity of 4.6E-04 pCi/cc composed of 95% Xe-133 and 5% Kr-85:
(1) Skin Dose Calculation .
Xe-133 0.95 (4.5E-04) = 4.37E-04 pCi/cc Beta: 4.37E-04 (34.9) = 1.53E-02 Rem / hour (a)
Gamma: 4.37E-04 (44.7) = 1.95E-02 Rem / hour (b) e
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i Table 2 continued ... I i
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! 0.05 (4.6E-04) = 2.3E-05 pCi/cc i L
! Beta: 2.3E-05 (153) = 3.52E-02 Rem / hour (c)
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i Gamma: 2.3E-05 (2.18) = 5.01E-05 Rem / hour (d) }
Total Skin Dose = (a) + (b) + (c) + (d) = 7.01E-02 Rem / hour
= 70.1 mrem / hour I l
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ATTACHMENT 7.3.1-1 ATMOSPHERIC RADIOACTIVE IODINE SAMPLE COLLECTION AND COUNTING 1.0 GENERAL In the event of a plant emergency requiring initiation of the Point Beach Nuclear Plant Emergency Plan, air sampling is necessary to determine the habitability of the operations support center (OSC), the technical support center (TSC), the site boundary control center (SBCC) and manned areas inside of the plant. In addition, it is necessary to determine airborne radioactivity concentrations at designated points around the plant site, as determined by the Health Physics Director, to facilitate entry into the plant and to determine the risk involved from the standpoint of health and safety of the public and/or plant personnel. This procedure does not cover the mechanics of air sampling, but is specifically directed towards the processing of radiciodine filter cartridges once the sample has been collected.
This procedure recognizes that masking of radiciodine peaks may occur during multichannel analysis (MCA) if the radioiodine charcoal filter is
( contaminated by radioactive air particulates, external contamination and/or radioactive noble gases. The purpose of this procedure is to outline specific steps to be taken to prevent charcoal filter contamination and thereby reduce this masking.effect.
2.0 PROCEDURE 2.1 When sampling for radiciodine, an air particulate filter will be placed in front of the charcoal filter to collect particulate matter and prevent charcoal filter contamination. The air particulate filter will be processed for MCA counting and any radioiodine collected will be added to the total concentration of iodine on the charcoal filter.
2.2 Prior to MCA analysis of the charcoal filter for radiciodine, the filter must be purged with nonradioactively contaminated air to displace the radioactive noble gases that may have accumulated in the filter. This purge may be accomplished through the use of plant service air (verify that service air is not contaminated) if access to'the plant is possible. It may be accomplished by placing the filter in another air sampler and operating it in an area outside of the known radioactive airborne area. If an air sampler is used for purging, a clean particulate filter will be used to prevent charcoal filter particulate contamination.
NOTE: (1) THIS SHOULD BE ACCOMPLISHED INSIDE A CHEM LAB HOOD OR
[\ IN AN OPEN AREA AWAY FROM PERSONNEL TO PREVENT UNNECESSARY EXPOSURE TO THE POTENTIAL NOBLE GASES.
(2) PURGE UNTIL CONTACT READING ON FILTER IS <5 mR/ HOUR.
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2.3 All handling and transfer of the various filter media should be done so as not to externally contaminate it. Samples should be handled l with clean gloves and individually placed in plastic bags to prevent any cross contamination.
2.4 The charcoal air particulate filter and sample forms will be set up for delivery to the OSC for multichannel analysis is to be performed.
NOTE: ROUTINE PROCEDURES FOR HANDLING RADI0ACTIV'E CONTAMINATED MATERIAL WILL BE FOLLOWED AT ALL TIMES.
2.5 Upon completion of counting, the Health Physics Director or his designated alternate will be notified of the results of all air sample analyses. He will be responsible for determining the habit-ability of the area sampled and respiratory equipment requirements.
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4 4 EPIP 7.4.1 MINOR g' N Revision 4
() 03-17-82 ROUTINE CHECK, MAINTENANCE, CALIBRATION & INVENTORY SCHEDULE FOR HEALTH PHYSICS EMERGENCY PLAN EQUIPMENT 1.0 PURPOSE The purpose of this procedure is to establish the routine checks, mainte-nance, calibration and inventory schedules for health physics related j material and equipment applicable to the Emergency Plan.
{
2.0 EMERGENCY PLAN EQUIPMENT STORAGE LOCATIONS 2.1 Emergency Plan equipment is normally maintained in a state of opera-tional readiness at the following locations.
2.1.1 Health physics station 2.1.2 Emergency support center (ESC) 2.1.3 Operations support center (OSC) 2.1.4 Site boundary control center (SBCC) 2.1.5 Control room 2.1.6 Two Rivers Community Hospital (NFAR and triage area) 2.1.7 Point Beach Nuclear Plant first aid room (see EPIP 11.0) l 2.1.8 South gatehouse.
2.1.9 other items of Emergency Plan equipment such as first aid '
kits, burn kits, stretchers, and the emergency vehicle are maintained at specified locations throughout the plant.
3.0 ROUTINE CHECK, HAINTENANCE AND CALIBRATION SCHEDULES Routine checks, maintenance and calibration of Emergency Plan equipment will be consistent with the schedule outlined in Attachment "A" and the instructions contained in EPIP 7.4.2, " Emergency Plan Equipment Routine Check, Maintenance & Calibration Instructions."
4.0 INVENTORY SCHEDULE gy 4.1 Inventory of health physics related Emergency Plan equipment will be consistent with the schedules provided in Attachment "A".
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EPIP 7.4.1 Page 2 4.2 Inventory of Emergency Plan equipment will be accomplished utilizing the inventory checklists listed below and attached to this procedure.
Missing or deficient items noted by the inventory will be promptly replaced by personnel assigned to accomplish the inventory. The results of all inventories will be reviewed by the Health Physics Supervisor who will ensure that all discrepancies are corrected. The ccmpleted inventory forms will then be forwarded to the Superin-tendent - Technical Services and the Health Physicist.
4.2.1 Inventory Checklists
- a. Site boundary control center (form EPIP-24a)*
- c. Two Rivers Community Hospital (form EPIP-24c)*
- d. Control room (form EPIP-24d)*
- e. Emergency vehicle (form EPIP-24e)
- f. First aid kits (form EPIP-24f)
( ) g. Burn kits (form EPIP-24g)
- h. PBNP first aid room (form EPIP-24h)*
- i. Stretchers (form EPIP-24i)
- The form needs to be filled out with an item by item count on an annual basis. Quarterly checks can be accomplished by verification of administrative controls such as seals.
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ATTACHMENT "A" EMERGENCY PLAN EQUIPMENT ROUTINE CHECK, MAINTENANCE, CALIBRATION AND INVENTORY SCHEDULE a
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?? $ b Y n x a u A a o c n E c No. Item Cross Ref. $ k CW $ k
- 1. Emergency Vehicle
- a. Radio operational test X
- b. Vehicle visual inspection and X engine start
- c. Emergency equipment inventory X
- d. Vehicle test drive XI X2
- 1. November through March
,~ 2. April through October
- 2. First Aid Burn Kits and Stretchers
- a. Inventory X3
- 3. January, April, July, September
- 3. Vamp Portable Area Monitors
- a. Functional check X
- b. Calibration X
- a. Functional test .X
- b. Preventive maintenance X (where applicable)
- c. Flow rate calibration X
- 5. SBCC Air Sampler (Battery 12 V DC) I
- a. Functional test X
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- b. Flow rate calibration X
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- 6. SBCC Air Sampler (Gasoline Powered)
- a. Functional test X
- b. Flow rate calibration X
- c. Spare gasoline changed X
- 7. Batteries - Replacement
- a. Traffic warning lights v X
- b. Survey / counting instruments 3 X
- c. Flashlights o X
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- d. Portable radios (KRQ 717) X
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/ e. Dosimeter chargers 0 x v
- 4. Alkaline type batteries to be used where possible and to be replaced yearly. Standard carbon cells, if used, to be replaced quarterly.
- 8. Potable Water (Stored) r
- a. Water changed X
- 9. Counting Instruments
, a. Functional test X
- b. Calibration x
- c. Counting efficiency determination x
- 10. Frisker Type Instruments .
- a. Functional test X
- b. Calibration X
- c. Efficiency determination X
- 11. Portable Survey Instruments l t
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- a. Functional test X (V]; b. Calibration X l
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- 12. Pocket Dosimeters and TLD's
- a. Dosimeter drift / response check X
- b. TLD's changed X
- 13. Respirators
- a. Inspection X
,. a. Inspection X T'N b. Functional test X
- 15. Bio-Paks (Oxygen Rebreathers)
- a. Inspection X
- b. Functional test X
- c. Periodic maintenance X
- 16. Inventory of Emergency Plan 5 Equipment - Complete X
- 5. This inventory includes all equipment listed for each center on forms EPIP-24a, b, c, d and h.
- 17. Portable Radio (KRQ 717)
Functional Check X 18.
Traffic Warning Light Functional Check X
- 19. Technical Support Center AMS-2/RM-14 Air Monitoring System
- a. Calibration X
( 20. Silver Zeolite (AqZ) Moisture Indicator Check. .
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EP1P 8.1 MINOR Revision 1
('~h 03-17-82
\v l PERSONNEL ASSEMBLY AND ACCOUNTABILITY 1.0 GENERAL The purpose of this procedure is to detail a method for (1) the assembly of personnel on the plant site in the event of an emergency situation and (2) the subsequent accounting of personnel.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Personnel accountability roster sheets (forms EPIP-17 and EPIP-18, attached) must be completed quickly and accurately and forwarded to the appropriate supervisor as soon as possible.
3.0 INITIAL CONDITIONS 3.1 An emergency has been declared as a result of plant conditions.
- y 3.2 A limited plant, plant, or an exclusion area evacuation has been
) ordered requiring the accountability of all personnel on the plant
(
x- / site.
3.3 The Shift Supervisor has determined that personnel assembly and accountability is necessary.
4.0 PROCEDURE 4.1 Shift Supervisor 4.1.1 Determine and communicate as required any special instruc-tions necessary for safe evacuation of personnel in the plant (for example, verbally communicate the assembly areas, designate any assembly area not to be used, designate certain areas of the plant to be avoided, etc.).
Assembly Areas ,
For Evacuation:
- 1. Control Room *
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EPIP 8.1 Page 2 O 3, Site Boundary Control Center *
- 4. Emergency Support Center *
- 5. Security Building (Extension Building)* and Gatehouse For Limited Plant Evacuation:
- 6. Health Physics Station
- 7. Cafeteria I
For Plant Evacuation:
- 6. Onsite Operations Support Center
- For Exclusion Area Evacuation:
- 6. Two Creeks Town Hall
- Center for emergency operation.
4.2 Security Shift Lieutenant 4.2.1 Designate an individual to perform Section 4.4 of this procedure for security posts.
4.2.2 Obtain a list of all personnel currently on the plant site from the appropriate security systems (badge checks, computer printouts, etc.)
4.2.3 As attendance is reported from the assembly areas (see Section 4.1.1), indicate on the list obtained in Step 4.2.2 that the individual has been accounted for.
- 4. 2.4' After the assembly areas and security personnel have sub-mitted their' rosters, compile a' list-of missing personnel using form EPIP-17.
4.2.5 Attempt to contact missing personnel using the Gai-tronics system.
4.2.6 If unable to contact the missing personnel, obtain from the missing person's supervisor the last known or probable location and/or job assignment. Enter this data on form EPIP-17.
4.2.7 Transmit copies of form EPIP-17 to the Maintenance Super-visor. l 4.2.8 Update forn ZPIP-17 as changes to rosters arrive and as mis' sing personnel are located.
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EPIP 8.1 Page 3 4.2.9 Transmit any changes in form EPIP-17 to the Maintenance Supervisor immediately.
4.3 Designated Supervisor at the Assembly Area (Including Centers for Emergency Operations) 4.3.1 Upon arrival at the assembly area, one supervisor should compile a roster of all personnel in his group who are present and accounted for using form EPIP-18 (attached). At-each in-plant center, there should be a roster of persons who are to report to that center. Each person present should be checked off.
4.3.2 When it is felt that the roster is completed as well as possible, notify the Security Shift Lieutenant at the central alarm station (CAS) or at the site boundary control center of any missing people by badge number.
4.3.3 Update the respective group roster as personnel arrive at or depart from the assembly area.
4.3.4 Report changes of the roster to the Security Shift Lieute-I nant periodically or as determined necessary by the Security b Shift Lieutenant.
4.4 Security Officer / Designee 4.4.1 Compile a roster of all security personnel using form EPIP-18.
4.4.2 Upon completion of the roster, notify the Security shift Lieutenant. Alert him to any missing personnel.
4.4.3 Maintain the roster current as personnel arrive at or depart from the security building or sacurity posts.
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.1 EPIP 12.1 MINOR g-'s Revision 1
( 03-17-82 Nm REENTRY PROCEDURES FOR EMERGENCY OPERATIONS I
1.0 GENERAL The purpose of this procedure is to detail the method for monitoring per-sonnel daring emergency repair / operation or search and rescue operations and provide instructions for reentering areas that have become radio-actively contaminated and/or have high or uncertain radiation levels.
Monitoring of personnel for purposes other than the reentry for emergency repair / operation or search and rescue operations will be in accordance with the normal health physics procedures or as delineated in the Point Beach Nuclear Plant Emergency Plan.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Personnel engaged in either emergency repair / operation or search and rescue operations should keep in mind the concept of time-distance-
,_ shielding to minimize radiation exposure as much as possible.
's 2.2 The " buddy system" is in effect and an individual will not be allowed to travel through potentially high radiation areas alone unless he is within sight of a buddy.
2.3 For purposes of emergency repair / operation, personnel will not receive a dose exceeding 25 Rem to the whole body.
2.4 For purposes of search and rescue operations, personnel should not receive a dose exceeding 100 Rem to the whole body.
2.5 All personnel who may receive radiation doses greater than 25 Rem will participate on a voluntary basis only.
2.6 Any exposure to radiation in excess of 10 CFR 20 limits should be authorized by the Health Physicist or Superintendent - Chemistry &
Health Physics and have the concurrence of a Duty & Call Superin-tendent or Site Manager. In an emergency, the Shift Supervisor should try to notify these persons for extended exposure authori-zation in excess of 10 CFR 20 limits, but has the authority to take immediate actions as required.
3.0 INITIAL CONDITIONS .
3.1 As a result of previous training all participating personnel will be aware of the possible hazards associated with radiation doses greater
( ) than 25 Rem to the whole body.
- [
EPIP 12.1 Page 2 O 3.2 Any completed radiation surveys of areas to be entered by emergency repair / operations or search and rescue personnel will be made available to the teams.
4.0 PROCEDURE 4.1 Team Leader 4.1.1 Determine with the Shift Supervisor and Chemistry /HP Super-visor which route to take to the location of interest.
Review any surveys of areas to be travelled or occupied by the team.
4.1.2 With the Chemistry /HP Supervisor, determine each team I member's allowable dose and calculate the stay time for each member.
4.1.3 Arrange, in advance, for any anticipated necessary reliefs
. for the team members.
I I
NOTE: STEPS 4.1.4 THROUGH 4.1.6 ARE DEPENDENT UPON THE RADIOLOGICAL CONDITIONS BOTH EXISTING AND POTENTIAL. IF, FOR EXAMPLE,
( THE EMERGENCY IS CONFINED TO THE AUXILIARY BUILDING, THE TEAM MAY REQUIRE LITTLE DOSIMETRY TO SEARCH THE TURBINE HALL.
4.1.4 Determine with the Chemistry /HP Supervisor the protective clothing and respiratory equipment necessary.
} 4.1.5 Equip team members with the following personnel dosimetry:
) a. Low range self-reading dosimeter (0-200 mR).
- b. Medium range self-reading dosimeter (0-5R)
- c. High range self reading dosimeter-(0-200R)^
- e. Extremity monitoring dosimeter (s) as prescribed by the Chemistry / Health Physics Supervisor.
4.1.6 Equip at least one team member with a high range beta-gamma detector, such as Teletector.
4.1.7 Each team will have a portable radio for communications capability with the control room and Health Physics super-vision.
4.1.8 Ensure the team has proper keys.
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i EPIP 12.1 Page 3 O
O 4.2 Repair / Operation Team 4.2.1 Determine with the Shift Supervisor exactly what work is to be performed, how many people will be required, and what tools and spare parts are needed.
4.2.2 Equip each team member with protective clothing, respiratory protection equipment and personnel monitoring devices. All clothing openings are to be taped.
4.3 Chemistry /HP Supervisor or Designee 4.3.1 Determine if potassium iodide administration is necessary and administer it to the search and rescue, repair / operation team members if needed. See EPIP 1.6, "Radioiodine Blocking and Thyroid Exposure Accounting," for guidance.
4.3,2 Brief all repair / operation and search anci rescue members of the hazards of radiation doses in excess of 25 Rem to the whole body.
4.3.3 Ensure that the teams have met all the necessary require-ments prior to entering a contaminated or radiation area.
4.3.4 During the team effort monitor the radio and log radiation levels as reported by the team and compare the readings to those expected. Keep track of the team's time and estimate the dose they are receiving as appropriate. Note also Bio-Pak depletion time.
4.3.5 10 CFR 20 limits exposure to the whole body, extremities, skin, and internals. The exposure records of any team member who exceeds 10CFR 20 limits should be forwarded to the Company Medical Director.
4.3.6 If the whole body dose of a team member exceeds 25 rem or his dose is uncertain or suspected of exceeding 25 rem or his internal dose is estimated to be greater than or equal to 10,000 MPC hours, he should be referred to a physician for appropriate medical care.
4.4 Maintenance Supervisor 4.4.1 The Maintenance Supervisor is responsible for accountability and search and rescue. He will work with the Chemistry / Health Physics Supervisor in the selection of the team.
4.4.2 As soon as one team is sent out, a second team should be set up and dressed.
V 4.4.3 The Maintenance Supervisor should work with the Plant Oper-ations Manager and Chemistry / Health Physics Supervisor.
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EPIP 12.2 MINOR w Revision 1 03-17-82 PERSONNEL EXPOSURE & SEARCH AND RESCUE TEAMS 1.0 GENERAL The purpose of this procedure is to provide the guidance and requirements necessary to conduct efficient search and rescue operations.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Proper radiological controls are to be maintained during search and rescue operations. Proper health physics practices must be adhered to in accordance with EPIP 12.1, " Reentry Procedures for Emergency Operations."
3.0 INITIAL CONDITIONS 3.1 EPIP 8.1, " Personnel Assembly and Accountability," is completed or persons are known to be missing or in need of help.
3.2 Review EPIP 12.1, " Reentry Procedures for Emergency Operations."
4.0 PROCEDURE 4.1 Maintenance Supervisor 4.1.1 Assemble a search and rescue team or teams, each team con-sisting of at least two persons. Of the two personnel, at least one will be trained in first aid. At least one will be qualified in health physics and both will be familiar with the plant.
NOTE: FOR THE PURPOSES OF THIS PROCEDURE, THE HEALTH PHYSICS QUALIFIED PERSON WILL BE CALLED THE HEALTH PHYSICS REPRESENTATIVE.
4.1.2 Appoint the most qualified team member as the search and rescue team leader. The search and rescue team leader will be in charge of the team while conducting search and rescue operations.
4.1.3 Coordinate all search and rescue teams so that duplication of effort and unnecessary radiation exposure does not occur.
4.1.4 Work with the Plant Operations Manager and Chemistry / Health bsj Physics Supervisor.
V 1
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.e EPIP 12.2 Page 2 b
v 4.1.4 Use a map of the plant to mark off areas which have been searched.
4.1.5 Recall the search and rescue team (s) when search and rescue operations are no longer necessary or when all missing
. persons are accounted for.
4.2 Health Physics Representative 4.2.1 Ensure that all team members meet the personnel dosimetry, protective clothing and respiratory requirements of EPIP 12.1, " Reentry Procedures for Emergency Operations."
4.2.2 Ensure that no team member receives a whole body dose greater than 100 Rem while conducting search and rescue operations.
4.2.3 The Health Physics representative will have the authority to secure search and rescue operations of the team and to order the team out of contaminated or radiation areas.
4.3 Search and Rescue Team Leader
\M) 4.3.1 Obtain the following information prior to performing search
\s_ / and rescue operations:
- a. Identification of each missing individual.
- b. Last known location of each individual.
- c. The job each individual was working on.
- d. Any significant plant status known that may affect the search.
- e. Allowable radiation exposure l'imits for each team member.
4.3.2 Ensure that the team is equipped with a first aid kit and knows the locations of stretchers.
4.3.3 Proceed to the last known location of the missing individual i and if necessary expand the search to adjacent areas.
4.3.4 Maintain close communications with the Chemistry /HP Supervisor on all team actions including notification when any personnel are located.
p) t" NOTE: TEAM MEMBERS SHOULD NOT SEPARATE WITHOUT THE DIRECT PERMISSION OF THE CHEMISTRY /HP SUPERVISOR AND TEAM LEADER.
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' Page 3 i e 4.3.5 Provide first aid and medical care as necessary and transport i
j or escort the located individual (s) to a safe location as !
soon as possible. t t
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i 1 POINT BEACH NUCLEAR PLANT l TSC, ESC, SOUTH GATE & OSC
\ EMERGENCY PLAN INVENTORY CHECKLIST d
Date Suggested Inv.
4 Inventory Check Air Samplinc Equipment 4
- 1. Low volume air sampler 1
- 2. High volume air sampler
- 2
- 3. AMS-2 cart mounted air sampler 1
- 4. Particulate filters, low volume, box 1 2
- 5. Charcoal filters, low volume, box 1
- 6. Particulate filters, b'gh volume, box 1
- 7. Charcoal filters, high volume, box 1
- 8. Silver zeolite filters 15
- 9. Plastic bottles, 1 liter 12
- 10. 50' extension cord 2 1 Dosimetry Equipment
- 11. Dosimeters (0-5,000 mR) 40
- 12. Dosimeters (0-200 R) 6 Dosimeter charger 2
- 14. Batteries, Size AA, pkg.
O13.
g 1 Survey & Monitoring Equipment
- 15. Victoreen Vanp 1
- 16. Rad Owl II 1
- 17. Thyac III - side window probe 1
- 18. Batteries, Size D 24
- 19. Batteries, Size 9 volt 6
- 20. Smear filters, box 20
- 21. Smear envelopes, box 2 21a. \" lead detector shield (teletector) 1 Signs ,
- 22. Three pocket placards 24
- 23. " Radiation Area" inserts 24
- 24. "High Radiation Area" inserts 24
- 25. "RWP Required" inserts 24
'26. " Airborne Area" inserts 24
- 27. " Contaminated Area" inserts 24
- 28. " Radioactive Materials" insert,s 24 EPIP-24b
-(03-82) .
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4 Item Suggested Inv.
No. Item Inventory Check C-) Respiratory Protection Equipment
- 29. Clear-Vue respirator 6
- 30. Ultra-Vae respirator 6
- 31. Filter cartridges, box 1
- 32. Smoke test kit 1
- 33. Bio-Pak 60 7 CHP Forms
- 34. CHP-02, Io' dine Airborne Survey, pad 1
- 35. CHP-21, Miscellaneous Surveys, pad 1
, 36. CHP-31, Radiation Work Permit, pad 1
- 37. CHP-34, Dosimeter Rezero, pad 1
- 38. CHP-37, Irregular or Offscale Dosimeter Report, pad 1
- 39. CHP-22, Air Particulate Sample, pad 1 EPIP Forms
- 40. EPIP-01, Emergency Plan Airborne Radiation Survey 10
- 41. EPIP-02, Emergency Plan Survey Record 10
- 42. EPIP-03, Dose Factor Calculation Sheet 10 l
0s 43. EPIP-04, Status Report on Plant Systems &
Controls 5
- 44. EPIP-05, Work Sheet for Status Report on RMS for Unit 5
- 45. EPIP-06, Work Sheet for Status Report on RMS for Plant 5
- 46. EPIP-07, X/Q Determination 5
- 47. EPIP-08, Estimated Whole Body & Thyroid Projected 5
- 48. EPIP-09, Estimated Whole Body Calculation Work Sheet 5 i 49. EPIP-10, Estimated Ground Deposition Calculation 5 EPIP-17, List of Missing Personnel
, 50. 5
- 51. EPIP-18, Assembly Area Roster 5
- 52. Xe-133 Equivalent Release Rate, Worksheet No. 1 5 i l
EPIP Procedures
- 53. EPIP 1.4, Radiological Dose Evaluation 5
- 54. EPIP 1.5, Protective Action Evaluation 5
- 55. EPIP 7.1.1, Chemistry & Health Physics Personnel Notification & Initial Response When Chemistry & Health Physics Personnel O are On-Site 5 N. /
EPIP-24b (03-82)
Item Suggested Inv.
No. Item Inventory Check
,O
'- EPIP Procedures, continued ...
- 56. EPIP 7.2.1, Activation of Health Physics Facilities at Site Boundary Control Center 5
- 57. EPIP 7.2.2, Activation of Health Physics Facilities at Technical Support Center /
Operations Support Center 5 Miscellaneous
- 58. Barricade tape, yellow / magenta, rolls 5
- 59. Tuck tape, rolls 2
- 60. Hot spot tags 50
- 61. Radiation material hazard tags 50
- 62. Radioactive material contamination tags 50
- 63. Yellow / magenta tape, rolls 6
- 64. Yellow / black warning tape, roll 5
- 65. Plastic bags, 3 x 5 50
- 66. Plastic bags, 5 x 7 50
- 68. Coveralls, cotton 12 pr
- 69. Gloves, cotton 12 pr
- 70. Hoods, cloth 12
- 71. Low volume air sampler 1
- 72. Filters, charcoal 6
- 73. Filters, air particulate 1 box
- 74. Rad Owl II survey instrument 1
- 75. Cs-137 check source 1
- 76. Dosimeters, high range (0-5,000 mR) 12
- 77. Dosimeter rezero unit 1
- 78. Shoecovers, white plastic 50 pr
- 79. Victoreen Vamp 1
- 80. Respirators, clear-vue 6
, 81. Respirators, ultra-vue 6
- 82. Filters, respirator particulate 1 box
- 83. PBNP Emergency Plan 1
- 84. Emergency Plan Implementing Procedures 1 SOUTH GATE Air Sampling
- 85. Low volume air sampler 1
- 86. . Particulate filters, box 1
- 87. Charcoal filters, box 1 Extension cord, 50'
( ) 88.
1 EPIP-24b .
(03-82).
4 Item Suggested Inv.
No. Item Inventory Check s
Radiation Survey & Monitoring Instruments
- 89. Vamp area monitor 1 Protective Clothing s
i 1 l
- 89. Coveralls 20 pr _.
- 90. Cotton gloves 20 pr s
- 91. Rubber gloves 20 pr - t s
- 92. Pallbearer gloves 20 prs
- 93. Cloth hoods 20 N f'
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- 94. Canvas booties 20 pr *
- 95. Plastic suits 20 sets
- 96. Shoecovers, white plastic l c's
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97.
PBNP Emergency Plan 1 \\ 1, j
98.
Emergency Plan Implementing Procedures ,.,1 -i~ , N,
- 99. PBNP HP Administrative Policies & Procedures s ,
Manual ,1
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100. Air sample number assignment list l' .
101. Bio-Pak 60 manual 1 102. Log book '
1* s 103. Cs-137 Check Source s 1 _
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Item Suggested Inv. i No. Item Inventory Check Radiation Survey & Monitoring Instruments
- 89. Vamp area monitor 1 Protective Clothing -
- 90. Coveralls 20 pr
- 91. Cotton gloves 20 pr
- 92. Rubber gloves 20 pr
- 93. Pallbearer gloves 20 pr
- 94. Cloth hoods 20
- 95. ' Canvas booties 20 pr
- 96. Plastic suits 20 sets
- 97. Shoecovers, white plastic 1 cs
- 98. PBNP Emergency Plan 1
- 99. Emergency Plan Implementing Procedures 1 100. PBNP HP Administrative Policies & Procedures Manual 1 101. Air sample number assignment list 1 102. Bio-Pak 60 manual 1 103. Log book 1 104. Cs-137 Check Source 1 By. Date Reviewed By -
Date (Health Physics Supervisor)
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-EPIP-24b (03-82) ,
y POINT BEACH NUCLEAR PLANT MONTHLY HEALTH PHYSICS INSTRUMENT AND AIR SAMPLER FUNCTIONAL TEST CHECKLIST DATE
Reference:
EPIP 7.4.1 - Routine Check, Maintenance, Calibration and Inventory Schedule of Health Physics Emergency Plan Equipment EPIP 7.4.2 - Emergency Plan Equipment Routine Checks, Maintenance and Calibration Instructions SITE BOUNDARY CONTROL CENTER INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Thyac III Installed cpm cpm
- 2. GSM-5 S-23 cpm cpm
- 3. RM-3C S-23 cpm cpm
- 4. PIC-6A Cs-ll mR/hr mR/hr
- 5. PIC-6A Cs-ll mR/hr mR/hr
- 6. PIC-6A Cs-ll mR/hr mR/hr
- 7. PIC-6A Cs-ll mR/hr mR/hr
- 8. Radector III Cs-11 mR/hr mR/hr
- 9. HPI-1010 Cs-ll mR/hr mR/hr
- 10. Nuclear Chicago S-23 cpm cpm AIR SAMPLERS Item Satisfactory No. Tm Functional Test NOTE: SOURCE CHECK CRITERIA
- 1. High Volume TO BE ENTERED FROM CURRENT CALIBRATION STICKER ON EACH
- 2. Gasoline Powered UNIT. RESULTS MUST BE WITHIN 120% OF THIS VALUE.
- 3. Battery (12 V DC)
EPIP-25b Page 1 of 4 (03-82) .
OPERATIONS SUPPORT CENTER INSTRUMENTATION Source Item Type of Serial Check Check No. Equipment Number Source Criteria Results
- 1. Rad Owl II Cs-6 mR/hr mR/hr 2., Thyac III Int. cpm cpm
- 3. Thyac III Int. cpm cpm
- 4. Vamp Area Monitor Cs-6 mR/hr mR/hr AIR SAMPLERS Item Satisfactory No. Description Functional Test
. 4. AMS-2 (cart-mounted)
Check Source Check Source Criteria Criteria
! a. AMS-2 cpm cpm
- b. RM-14 cpm cpm Use check source CS-6.
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(03-82) l
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EMERGENCY INSTRUMENTATION Item No;_
Type of Equipment Serial 1 Number Check Rad Owl II Source 2.
Vamp Area Cs-5 Monitor i
Cs-5 AIR SAMPLERS It g ~em-Description ,
INSTRUMENTATION SOUTM GATE Item No;_ Type .of Equipment Serial Check Source Sc
- 1. Number b VAMP Monitor Used Q Cri d AIR SAMPLERS ~ Cs-6 Item Type of No._ Equipment 1
Satisfactory low Volume Functional Test INSTRUMENTATION CONTROL ROOM i
N IM Type of
\
A Equipment Serial check 1 Number Source Source Radector III M h Check Cr_iteria Cs-3 E
EPIP-25b (03-82) l
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- FIRST AID ROOM I \
INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
~
- 1. Thyac III Internal cpm cpm EMERGENCY VEHICLE INSTRUMENTATION Item No. Equipment Number Used Criteria Results
- 1. Thyac III Internal cpm cpm
- 2. Thyac III Internal cpm cpm
- 3. Mini-Rad Cs-3 mR/hr mR/hr
- 4. Mini-Rad Cs-3 mR/hr mR/hr Checked By Date
-Reviewed By Date Health Physics Supervisor 4
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Page 4 of 4 l (03-82) -
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SEMI-ANNUAL AND ANNUAL EMERGENCY PLAN CHECKLIST DATE
Reference:
EPIP 7.4.1 - Routine check, Maintenance, Calibration and Inventory of Schedule of Health Physics Emergency Plan Equipment EPIP 7.4.2 - Emergency Plan Equipment Routine Checks, Maintenance and Calibration Instructions SITE BOUNDARY CONTROL CENTER AIR SAMPLERS Item Preventive Flow Rate No. T E Maintenance Calibration
- 2. Gasoline Powered
- 3. Powered DOSIMETERS Pocket Desimeters Drift / Response Checked '
Date Last Completed Date Due TLD's TLD's Changed
- Date Changed Date Due
- Includes TLD's from emergency vehicle.
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EPIP-25d Page 1 of 5 ,
l (03-82) l l
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6 e ANNUAL BATTERY REPLACEMENT NOTE: If regular carbon batteries have been used, they should be replaced quarterly.
Item Battery No. Type of Equipment m T Quantity Changed Date Due
- 1. Traffic Warning Light
- 2. Survey /Frisker Instruments
- 3. Flashlights
- 4. Portable Radio
- 5. Dosimeter Charger MISCELLANEOUS Item No.
- 1. Potable Water (20 gal.) a. Date Changed
- b. Date Due J 2. Gasoline / Oil (Air Sampler) a. Date Changed
- b. Date Due
- 3. Fire Extinguisher Serial Number Date Last Inspected
- 4. AgZ Filters Moisture Indicator Checked l TECHNICAL SUPPORT CENTER AIR SAMPLERS Item Preventive Flow Rate 2 No. Maintenance Calibration
- 3. AMS-2 Cart Mounted
( -
EPIP-25d Page 2 of 5 .
(03-82)
9 DOSIMETERS Pocket Dosimeters Drift / Response Checked Date Last Completed Date Due MISCELLANEOUS
- 1. AgZ Filters Moisture Indicator Checked RESPIRATORY EQUIPMENT Item Serial Periodic No. Number Functional Test Maintenance
- 1. Bio-Pak OPERATIONS SUPPORT CENTER AIR SAMPLERS Item Preventive Flow Rate No. m T Maintenance Calibration
DOSIMETERS Pocket Dosimeters Drift / Response Checked
- . -Date Last Completed Date Due RESPIRATORY EQUIPMENT Item Type of Periodic No. Equipment Functional Test Maintenance
- 1. Bio-Pak 4
EPIP-25d '
Page 3 of 5 (03-82)
- MISCELLANEOUS
- l. AgZ Filters Moisture Indicator Checked SOUTH GATE AIR SAMPLERS Item Preventive Flow Rate No. Equipment Maintenance Calibration
- 1. Low Volume ,
CONTROL ROOM 4
DOSIMETERS Pocket Dosimeters Drift / Response Checked Date Last Completed Date Due RESPIRATORY EQUIPMENT Item Type of Serial Periodic
( No. Equipment Number Inspection Functional Test Maintenance
- 1. Bio-Pak
- 2. Bio-Pak
- 5. Supplied Air / N/A
, (Comp. Unit) / N/A
- 6. Supplied Air / N/A (Comp. Unit) / N/A
- 7. Supplied Air / N/A -
(Comp. Unit) / N/A
- 8. Supplied Air / N/A (Comp. Unit) / N/A o
EPIP-25d Page 4 of 5 (03-82) .
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. 9. Supplied Air / N/A (Comp. Unit) / N/A i
l 10. . Supplied Air / N/A (Comp. Unit) / N/A i
i REMARKS:
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Checked BY Date Reviewed By Date Health Physics Supervisor i
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EPIP-25d Page 5 of 5 (03-82) ,
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