ML20069J485
| ML20069J485 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/28/1983 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20069J477 | List: |
| References | |
| PROC-830128-01, NUDOCS 8304220621 | |
| Download: ML20069J485 (105) | |
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January 28, 1983 .
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Q' POINT BEACH NUCLEAR PLANT l EMERGENCY PLAN IMPLEMENTING PROCEDURES The following new and revised procedures are attached and should be inserted into your manual. Please destroy all revisions removed from your manual.
- 1. EPIP 1.1, " Initial Classification," Revision 4, dated 01-28-83.
- 2. EPIP 1.3, " Estimation of Source Term," Revision 4, dated 01-28-83.
- 3. EPIP 6.1, " Limited Plant Evacuation," Revision 2, dated 01-28-83.
- 4. EPIP 6.2, " Plant Evacuation," Revision 2, dated 01-28-83.
- 5. EPIP 6.3, " Exclusion Area Evacuation," Revision 1,. dated 01-28-83.
- 6. EPIP 7.3.2, " Post-Accident Sampling and Analysis of Potent,ially High Level Reactor Coolant," Revision 5, dated 01-28-83.
- 7. EPIP 8.1, " Personnel Assembly & Accountability,"' Revision 3, dated 01-28-83.
- 8. EPIP 11.3, " Hospital Assistance," Revision 3, dated 01-28-83.
The following new and revised forms are attached for insertion into your manual. Please. attach the form to the indicated procedure and destroy all revisions removed from your manual,
- 1. EPIP-01 (01-83) , " Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center," (attach to EPIP 7.3.1).
- 2. EPIP-02 (01-83), " Emergency Plan Survey Record Site Boundary Control Center," (attach to EPIP 7.3.1) .
- 3. EPIP-04 (01-83), " Status Report on Plant Systems & Controls for Affected Unit," (attach to EPIP 1.2) .
- 4. EPIP-22 (01-83) , " Plant & Company Emergency Call List," (place after a the, call list tab).
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- 5. EPIP-23 (01-83), "Offsite Agency Emergency Call List," (place afte'r the call list tab).
- 6. EPIP-24a (01-83), " Site Boundary Control Center Emergency Plan Inventory Checklist," (attach to EPIP 7.4.1) .
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- 7. EPIP-25b (01-83), " Monthly Health Physics' Instrument & Air Sampler Functional Test Checklist," (attach to EPIP 7.4.2) .
O 8304220621 830420 PDR ADOCK 05000266 k F PDR
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Emergency Plan Implementing Procedures - 2
- 8. EPIP-25c (01-83), " Quarterly Emergency Plan Checklist," (attach to EPIP 7.4.2) . j
- 9. EPIP-27 (01-83) , " Monthly Communications Test," (attach to EPIP 14.1) .
- 10. EPIP-34 (01-83), " Calculation of Xe-133 Equivalent Release Rates,"
(attach to EPIP 1.8).
Also attached is a revised listing of the ' Table of Centents to be inserted into your manual. Please destroy the old revision.
- Also attached is a revised Table of EPIP Forms. Please insert this table into your manual. Please destroy the old revision.
Please fill out the attached receipt form and re urn it to Ms. F. A. Flentje at the Point' Beach Nuclear Plant.
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J. E. Knorr
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u.wxc M .(a d ) POINT BEACH NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 01-28-83 I hereby acknowledge , receipt of EPIP 1.1, EPIP 1.3, EPIP 6.1, EPIP '6. ,
2, EPIP 6.3, EPIP 7.3.2, EPIP 8.1.and EPIP 11.3 and have inserted them,into my manual.
G Date
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01-28-83 v
TABLE OF CONTENTS Revision Date_ # 7 " ,
1.0 CLASSIFICATION & ASSESSMENT 1.1 Initial Classification ... . ....... 4 01-28-83 i 1.2 Plant Status . . . . . . . . . . . . . . . . 0 03-31-81 1.3 Estimation of Source Term . . . ....... 4 01-28-83 1.4 Radiological Dose Evaluation . .......
6 09-10-82 1.5 Protective Action Evaluation . ....... 4 09-10-82 1.6 Radiciodine Blocking & Thyroid Exposure Accounting . . . . ... ... ...... 1 02-26-82 1.7 Evaluation of Core Damage . . . ....... 1 09-10-82 1.8 Emergency Off-Site Dose Estimations . . . . . 2 09-10-82 2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES
, 2.1 Unusual Event - Imediate Actions . . . . .. 1 09-10-82 2.2 Unusual Event - Plant and Company Personnel Notification . . . ..... ....... 1 07-01-81 2.3 Unusual Event - Off-Site Agency Notification 2 09-10-82
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/ 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Imediate Actions . . . . . . . . .
.. 2 09-10-82 3.2 Alert - Plant & Company Personnel Notification . . . ..... ....... 1 07-01-81 3.3 Alert - Off-Site Agency. Notification ' . . . . 1 09-10-82 4.0_ SITE EMERGENCY - IMPLEMENTING PROCEDURES ,
4.1 Site Emergency - Imediate Actions ..... 2 09-10-82 4.2 . Site Emergency - Plant & Company Personnel Notification . . . .... . ....... 1 07-01-81 4.3 Site Emergency - Off-Site Agency Notification 1 09-10-82 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Imediate Actions . . . . 2 09-10-82 5.2 General. Emergency - Plant & Company ..
Personnel Notification .. . .. ..... 1 07-01-81 5.3 General Emergency - Off-Site Agency l l Notification . . . . ... . . ...... 1 09-10-82 6.0 EVACUATION
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% .6.1 Limited Plant Evacuation .. . d. . . .. . . 2 01-28-83
! 6.2 Plant Evacuation . . . . .. . ....... 2 01-28-83
~/ 6.3 Exclusion Area Evacuation . . . . . . . . . . 1 01-28-83 6.4 Energy Information Center Evacuation .... 0 03-31-81 6.5 .TSC & OSC Activation . .. . . . ...... 0 09-10-82 4 -
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.,n 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 ....... 2 04-3D-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 i Boundary Control Center ..... 2 03-17-82 7.2.2 Activation of HP Facilities at Operations Support Tenter .. .. 1 03-17-82 7.2.3 DELETED
/] 7 . 2.'4 Health Physics Communications ... 1 03-17-82 (j 7.2.5 Control & Use of Vehicles ..... 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 . . . . .,. ... . . . . . 5 01-28.-83 -'
7.3.3 , Post-Accident Sampling'of Contain-ment Atmosphere ......... 4 09-10-82 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 ............ 6 09-10-82 7.4.2 Emergency Plan Equipment Routine l
Check, Maintenance & Calibration
[M 7.4.3 Us 1d odei53bbingie' t ' ?j Channel Iodine Spectrometer to !
Determine Airborne Iodine i Activities . . . . . . . . . . . . 1 s 05-15-81 l
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Revision m /x Date 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 . ...
3 01-28-83.
9.1
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Security ................. 0 03-31-81 10.0 Firefighting ................ 0 03-31-81 11.0 FIRST AID & MEDICAL CARE , j 11.1 On-Site First Aid Assistance ........ 3 09-10-82 11.2 Injured Person's Immediate Care . ...... 1 05-15-81 11.3 Hospital Assistance . . . . . . . . . . ... 3 01-28-83 11.4 Personnel Decontamination . . . . . . . ... 0 01-29-82 12.0 REENTRY & RECOVERY PLANNING __ .
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12.1 Reentry Procedures for Emergency Operations 1 03-17-82
- 12.2 Personnel Exposure & Search & Rescue
'y Teams . . . ................ 2 04-30-82 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 . . . . . . . . . . . . '2 09-10-82 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 ............. 2 04-30-82 i
15.4 Emergency Pr,eparedness Review . ....... 0 09-10-82 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Section Notification &
Response ................. 3 09-04-81~ --
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.,/ TABLE OF EPIP FORMS l i
Form Title Procedure i
l 01 Emergency Plan Airborne Radiation Survey Record Site
] Boundary Control Center (01-83) 7.3.1 j 02 Emergency Plan Survey Record Site Boundary Control Center-i (01-83) 7.3.1
} 03 Dose Factcr Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 04 Status Report on Plant Systems & Controls for Affected Unit (01-83) 1.2
{ 05 Worksheet.for Status Report on Radiation Monitoring System i
for Unit (03-81) 1.2 06 Worksheet for Status Report on Radiation Monitoring System for Plant (03-81) 1.2 l 07 For X/Q Determination (09-82) 1.4 -
, 08 Estimated Whole Body & Thyroid Projected Doses (09-82) 1.4 i 09 Estimated Whole Body Dose Calculation Worksheet for 1
Specific Noble Gas Releases (09-82) 1.4 j 10 Estimated Ground Deposition Calculation Worksheet for
+ , ,) Particulate Radionuclide Releases (09-82) 1.4 j / 10a Estimated Population Dose (09-82) .
1.8 4 11 Summary of Radiological Dose Evaluation Calculations (09-82). 1.4 12 Incident Report Form (09-82) 2.3, 3.3,
'4.3, 5.3 i 13 Status Update Form (09-82) 2.3, 3.3 i 4.3, 5.3 14 Unused -
15 Unused
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, 16 Event' Data Checklist' (03-81) -
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17 Accounting Short Form (04-82) 8.1
! 18 Assembly Area Roster (03-81) 8.1
] 19 Drill / Exercise Scenario (03-81) 15.3 l 20 Drill / Observation Sheet (03-81) 15.3
! 21 Drill / Exercise Evaluation Report (03-81) 15.3
. 22 Plant & Company Emergency Call List (01-83) Call List Tab i 23 Offsite Agency Emergency Call List (01-83) Call List Tab j 24a. Site Boundary Control Center Emergency Plan Inventory
} Checklist (01-83) 7.4 1 24b TSC, ESC,' South Gate & OSC Emergency Plan Inventory
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Checklist (09-82) 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 i
(06-82) 7.4.1
} m 24e Emergency Vehicle Inventory Checklist (04-82) 7.4g ,
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- p1 24f Emergency Plan First Aid Kit Inventory Checklist (09-82) 7.43- '
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) EPIP EPIP
_, / Forms Title Procedure ,
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24g Emergency Plan Burn Kit Inventory (09-82) 7.4.1 24h Emergency Plan First Aid Room Inventory (09-82) 7.4.1 i 241 Emergency Plan Stretcher Inventory (09-82) 7.4.1 l 24j Emergency Trauma Kit Inventory Checklist (09-82) 7.4.1 25a Emergency vehicle checklist (06-82) 7.4.2 25b Monthly Health Physics Instrument & Air Sampler Functional Test Checklist (01-83) 7.4.2
! 25c Quarterly Emergency Plan Checklist (01-83) 7.4.2 25d Semi-Annual & Annual Emergency Plan Checklist (09-82) 7.4.2 26 Quarterly Communications Test (03-81) 14.1 I
27 Monthly Communications Test (01-83} 14.1 28 Emergency Plan Instrument Calibration Schedule (06-82) 7.4.2 -
i 29 Emergency Plan Counting Equipment & Frisker Calibration Schedule (06-82) 7.4.2 30 Reactor Coolant Post-Accident Sampling Analysis Report
.' (09-81) '7..3 2 i 31 Containment Atmosphere Post-Accident Sampling Analysir l Report (12-81) 7.3.3 4 32 Search & Rescue and Emergency Operations Checklist (04-82) 12.2 l 33 Estimation of Core Damage (09-82)_ _ 1.7
, 34 Calculation of Xe-133 Equivalent Release Rates (01-83) 1.8 i ., 35 Dose Calculations (09-82) 1.8
- . + 36 Unused
, 37 Medical Assistance Call List (09-82) 11.1 1
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j t EPIP 1.1 l
MINOR ,
Revision 4 01-28-83 j w IllITIAL CLASSIFICATION i
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] 1.0 GENERAL -
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.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 j Plan. Each emergency classification requires emergency organization noti-
{ fications, mobilizations, and actions to be performed in order to appro-j priately react to the situation and provide for the health and saf6ty of plant.and public personnel. They are listed in order of increasing severity.
l 1.1 Unusual Event ,
1 l An unusual plant condition which either has occurred or might occur.
j This condition could possibly lead to a degradation in overall safety.
- This condition does not re; resent a significant radioactivity release, j involves no offsite responte, and may require no au pentation of
) 7 plant personnel. In spite of the above, prompt notification of the J
,) 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 l offsite notification is necessary and the plant organization may have .
l to be.aupented. , ,
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] 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.
l Potential radioactive releases may hive an impact on offsite people-Prompt notification of offsite agencies is required. The plant organization must be aupented and the technical support center, onsite operations support center, and emergency support center wi,ll
, 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 potential for loss of containment integrity. Potential radioactive h,
a releases may have an impact on offsite people. Prompt notification
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. EPIP 1.1 Page 2 l %
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t ..- x of offsite agencies is required. The plant organization must be l augmented and the technical support center, onsite operctions support l 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 immediate 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.
l 3.0 PRECAUTIONS _AND LIMITATIONS ,
3.1 All actions and notifications should be appropriately logged.
3.2 Emergency P,lan implementing procedures are not to be used to respond to security threats. One hour notification of the NRC is required using the red phone for security threat!s.
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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 ther~e is no classification for the events
- and no notification other than the NRC is required. These notifi-cations 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 Unusual 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.
3.5 For classification purposes where radiological dose is the primary parameter leading to a classification, use EPIP 1.8, " Emergency ~
. Off-Site Dose Estimation" for determination of dose.
4.0 INITIAL CONDITIONS None.
NOTE: APPENDIX 1 0F NUREG-0654 (PAGE 1-3) CONTAINS THIS SENTENCE: "THE f]
Dy 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.
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- 4 EPIP 1.1 Page 3 ,
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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 conditiong at this time. Check (J) all applicable categories.
l Refer to Face l
Categorv .in Table 1-1 i
- 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
) 6. Secondary Coolant Anomaly 4
- 7. Abnormal Effluent 5
- 8. __
Major Electrical Failures 5
- 9. . Control Room Evacuation' 6
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. 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 15 18. Reactivity Transient -
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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 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 oi conditions are classified as an. Unusual Event, perform- -
EPIP 2.1, " Unusual Event - Immediate Actions." ,
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5.7 If events or cond'itions are classified as an Al~ert, perfoba EPIP. 3.1', c
" 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 Eme,rgency - Immediate Actions."
NOTE: ..
"One hour" refers to the requirement to notify NRC within one hour (10 CFR '
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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_ . . _ . . . _ _ _ _ _ _ . . . . _ _ _ _ _ _ _ . - _ _ _ _ _ . . . _ ___ _ _ _ _ _ _ m__ .--m__._._._..__m _ _ , ... ._ __. . _ . . _ _ . . . _ . . _ _ . _ . . _ _
%Y j _Y' Notes: DCS - Duty & Call Superintendent -
DSS - Duty shift Supervisor . TA812 1-1
, FS&R - Final Safety Analysis Report ,
M&SF - Modified Amended FSMF Security Plan ,
, 53ERGENCY CIASSIFICATIcet Emergency Category Initiatine Condition Indication used Classification
- 1. Safety System Functiong unplanned initiation of emergency core cooling Any of the fellowing first-out reactor trip unusual Event
- with injection to the primary system panel annunciation with indicator confir- 1-Hour (7) mation noted ,' .
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- 1. " Containment press h!", /
[F1-945, FI-947, FI-949 (2/3 >5 pelg)]
- 2. " Steam Ilhe loop & lo-lo press" lFI-464, FI-469, FI-482 (2/3 (530 psig)l
- 3. " Steam line loop a lo-lo press"
[FI-478, FI-479, FI-483 (2/3 (530 pelg)]
~ 4. "Fressuriser lo press SI" .
[FI-429, FI-430, F1-431 (2/3 (1735 peig)]
- 5. Wide range pressure <1500 psig Loss of containment integrity requiring WlnenshutdowncommencesasdeterminedbyDSS Unusual Event .
shutdown by Technical Specifications and DCS 1-Hour (5)
Loss of engineered safety feature ~ requiring / When shutdown commences as determined by DSS Unusual Event shutdown by Technical Specifications and GCS 1-Hour (5)
't Loss of fire protection system function When shutdown commences as determined by DSS thnasual Event g requiring shutdown by Technical Specif1- and DCS 1-Hour (5) cations (i.e., both fire pumps inoperable) and no backg fire suppression. system , .
- 2. Abnormal Primary Escoeding Technical Specification primary system when shutdown commences as determined by DSS Unusual Event Leak Rate leak rate (10 gus) .
and DCS 1-Hour (5)
(5) (7) See DCS 1.12.1 lor 10 CFR 50.72 Notifications.
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Tableg l-1 Page 2
. Emergency Category Initiating Condition Indication Used Classification Leak rate >50 gin . All of the following: Alert *
- 1. " Volume control tank level hi-lo"
[LI-141 and/or LI-ll2 (8%] ,
- 2. Decreasing pressuriser level
. [LI-426,L1-427,LI-428]
, 3. " Charging pump speed ht" ,
- 4. Charging line flo*w (FI-128) >50 gin more than letdown flow (FI-134) l l
Leak rate in escess of available pump All of the following: Site Emergency capacity lacluding charging, high head SI and low head sI 1. " Volume control tank level hi-lo i
[LI-141 and/or LI-ll2 (8%) k i
- 2. tio pressurizer level indicated
[LI-426, LI-427, LI-428] '
l3. All avrilable 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 soth of the following: Unusual Event Temperature / Pressure
- 1. Alarm on P-250, if operable
- 2. Confirmation by manual calculation 1 moth of the following:
Pressure >2735 peig 1. Pressure >2735 psig on PR-420, and IIRC unly ,
1-hour open lire (2)
Delet <1.30 2. Code safety, er Poav not closed indication
- 4. Abnormal Primary / Esceeding Technical Specificatiodi primary-secondefy ifhen shutdown commences os determined by DSS Unusual Event secondary Leak t leak rate ,
and DCS 1-Hour (5)
(2) (5) See DCS 1.12.1 for 10 CFR 50.72 Isotification.
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Table 1-1 -
Page 3 Emergency category Taitiatina condition radication used clasalfication -
Grose failure of I so tihe (><M gn) a loss of alt of the following first-out reactor panel hiert offsite power (Fs&A 14.2.4) ear.unciation with confirmation indication: .
- 1. arressuriser to prese 31,=
(FI-429, FI-430, PI-411 (2/3 (1735 peig)]
- 2. a.
- steam generator a level ht" (LI-461, LI-462, LI-463 (2/3 >70%)] g
- b. " Steam generator B level ht" (LI-471, LI-472, LI-473 (2/3 >70%)]
- 3. a. "4.16 kv bus undervoltage"
& 0 volts on 403 & A04 voltmeters.
- b. 304 to A03 ammeter en m2 (0 aspe)
- c. 304 to 404 asumeter en (22 (e empo)
- 4. SI flow >400 g e indicated by FI-924 &
FI-925 and pimp disci *erge pressere -
corresponding to flow.
mapid failure of >10 se tubee (4000 go) with 111 of the following first-out reactor panel site Emergency or without offelte AC lanmunciation with confiralag indicaties: -
- 1. "Pressuriser le press s!" *
(FR-429, PI-430, PI-431 (2/3 <1735 pelg)] ,
, 2. a. " steam generator A level hi*
(LI-461, LI-462, LI-463 (2/3 >?0%)]
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- b. = steam gener ter a level ht=
(LI-471, LI-472. LI-4)3 (2/3 >70%)]
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- 3. si flow >4.00s em indicated by F1-626, '
FI-924, FI-924 & FI-925
- 5. core Fuel Damage Gross fuel damage la core indicated Soth of the followings unusual svent
- 1. Letdown line radiatica monitor (k9)
(semple line 3109) 100 m alarm setpolat.
, s 2'. sustained offseale & chemical saalysis shows ,
fiselon product concentratico lacrease by 100E.
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Table 1-1 Page 4 Emergency category Initiatine condition Indication used classification Naselve fuel damage
- 300 pci/cc lodine-egalvalent as determined by Alert by chemical analysis
- 1. Naasive loss of fuel clad integrity Initiating conditions Nos. 1, 2, 4 & 5 General Emergency *
- 2. With sleultaneous loss of primary system integrity exist and No. 3 is possible 1-Nour open line (3)
- 3. With potential loss of contalement integrity .
1.'300 pcl/cc Jodine.e p ivalent determiewd by chemical analysis -
- 2. Primary systaa leak >1000 g o indicated by si flow >1000 ga (FI-924 & F1-920) and pump
- discharge pressura corresponding to flow
' - . 3. Minimum containment pressure sg preselen egalpment is not availabin (any of the +
j follouing): ,
- s. No fan cooler operating and <2 apray pumps.
- b. No spray pump operating and <4 fan coolers j
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- c. <2 fan coolers running with I spray pump
- 4. " containment press ht" '
[rt-945, FI-947,71-949 (2/3 >$ psig)] f
- 5. " containment sprey" with 2/3 + 2/3 >25 psig /
lrI-945,PI-947,FI-949)
. trI-946,PI-948,rI-9501
, 6. secondary coolant Be& action in feeesater'enthalpy incident , 1. a . Decreasing feeh eter temp indicated by unusual Event Anomaly (FSAR 14.1.7) 70-418& & 70-4344 cm F-250 g ,
- b. confirmed by local tasperature indicator on outlet of No. 5 feeeester heater.
- 2. uneapected increasing pouer on encore nuclear - '
instrumentation Steam line break with primary to secondary leak A J of the follouing first-out reactor trip Alert / .
rate in escess of 10 go (FSAR 14.2.5) panel annunciation with confi mation: 1-Nour open line (3)
. 1. Either: '
j t a. " Steam line loop A Lo-Lo press"
, [PI-468, FI-469, FI-es2 (2/3 (530 peig)] .,
1 or
, b. " steam lin. E p a to-to pres."
i j
[F1-478, FI-479, 71-4a3 (2/3 <530 psig)] g i
(3) See DCS 1.12.1 for le CFR 60.72 Notification. . - \l
l , . c ~
[ ! ,
l 4 j ij l
)
i
(/ .
Table 1-1 Fage 5 cateery Initiating condition Emergency Indication used classification
- 2. Confirmed pr'imary-to-secondary leak rate of at least 10 go.
- 3. Eithaan
- a. " Steam line loop & isol channel alert" (FI-464. F1-465 (1/2 >3.9s10e Ib/br))
or
~
- b. "staan line loop a jsol channel alert"
[F1-474, F1-475 (8/2 >3.9s108 lb/br)]
3 Secoadary coolant Transient initiated by loss of fee &ater, folloued 1 Anomaly 3 of the follouthg General Emergency by loss of ausiliary fee &ater for >I hour ,
(FSAR 14.1.11)
- 1-Hour open line (3) 8
- 1. Decreasing SG 1evels -
"A" SG (LI-461,LI-462,LI-443]
"B" SG lLI-471,LI-472,LI-473) .
- 2. 38o ausiliary fee &ater flow - .
(FI-4002,F1-4007,F1-4014)
(FI-4036,F1-4037]
- 7. Abnormal Effluent Radiological effluent Technical specification limits Akrborneeffluentsonly unusual Event escoeded but <10 times the limit,(FSaa 14.2.3) 1-Hour (8) .
Radiological effluent Technical Specification limits Liquid effluents only escoeded (FSAR 14.2.2) unusual Event 1-Hour (8) .
Radiological effluents >10 times Technical Airborne effluents only SpecifAcation instantoneous lialta. (An insten- alert taneous rate which, if continued for >2 hours, would 1-Hour (8) result in a dose of about I mR at the site boundary under everage, meteorological conditions.) .
- a. saajor Electrical Sustained loss of offsite pouer >l5 minutes Failures 43 of the follouing: Unusual Event (FSAR 14.1.2) \
- 1. "4.16 kw bus undervoltage"
& 0 valts on 403 & A04 voltmeters.
- 2. 204 Lo 403 ammeter on 002 (0 amps). .
t
- 3. 304 to 404 aemeter on C02 (0 ag s) 1 (3) (8) See DCS 1.12.1 for 10 CFR 50.72 adotification.
- I
- _ _ . . . . - . .. . - _ . ~ . _ - _ _ . - -- _ - ---- _ ._. .__- - - __--_. _-~
'r
. A ;\ -
s, Table 1-1 Page 6 .
Category Emergency- '
Initiatina Condition Indication used , Classification svetained loss of onsite AC power capability noth of the following:
l
(>15 minutes) Unusual Event
, 1-Nour (5)
- 1. "4.16 kw bus tendervoltage" &
O volts on A05 and A06 voltaeters
- 2. "Beergency Diesel starting system .
Disabled" for both Diesels *
. ~ t .
Loss of all vital onsite DC power >15 minutes moth of the following:
Site Emergency y 1. " Annunciator power failure" on '
C01, Cot, C03, and C04 ,
f .
/
-1
- 2. <100, volts on the voltmeters for all batteries Loss of offsite power and loss of all onsite AC y of the following:
A power for >15 minutes Site smargency - '
r f '. .
- 1. "4.16 kw bus undervoltage" 0 volts on 403, A04, A05, 406 & "Emerg Diesel starting systes disabled" for both Diesels t
)' /
/ 2.l304toA03ammeteron002(0 amps)
- 3. 304 to A04 ammeter on CO2 (0 amps)
Loss of offsite and all onsite AC power with lors of AJ of the followings all aulliary fee &ater for >2 hours General Emergency *
- 1. Unit aus W meter 302 on C02 (O lat)
- 2. Station muu sai meter 304 on CO2 (0 faf)
$ 3. 304 to A03 ammeter on CO2 (9 amps) 1 4. 304 to A04 ammeter on CO2 (0 amps)
- 6. 302 to 401 ammeter on CO2 (0 amps)
, 7. a. No auulliary feedwater flou
[F1-4036,F1-4037]
- t. . Secreasing SG 1evel - *
"A" SG lLI-461, LI-462, L1-463]
- B" SG {LI-471, LI-472, LI-473)
- 9. Control poem Evacuation Evacuation of control room >15 minutes &
As re< paired by Dss site Baergency no control at remote shutdown station
^
l-Nour open line (3) t .
- 10. Fire Fire in vital area or on the controlled side of plant As reported by Fire Brigade Chief ,
2 lasting >10 minutes after initial use of fire unusual Event eatinguishing esysipment. g I
, '(3) (5) See DCS 1.12.1 for 10.CFR 50.72 Notifica%:n- '
='
- p
. - - 4
_- . . . _ . _ . _ . _ _ . _ . _ _ . _ - _ _ _ -. . _ _.. - ._. __ ._ . - _ _ .m_ - . .- ._ __ - ___ ..
.,' '..., %.) ._
~
, Table 1-1
- F*98 7 .
Emergency ,
Category Initiating Condition Indication used Classification Fire affecting 1 train of safety systems. As reported by Fire Brigade Chief Alert Fire affecting 2 trains of safety systems As reported by Fire Brigade Chief Site Emergency
!!. Plant Shutdown Function Nonfunctional indications or alarms in the control Roth of Llw following , Unusual Event room on primary system parameters requiring plant 1-Nour (5)
- 1. " Annunciator power failure" on C04.
- 2. Failed indication as determined by RSS.
Turbine mechanical failure with consequences All of the following:
- 1. Annunciator " Turbine supervisory." Unusual Event
- 2. Indication on TR.-6019 of bearing vibration
')7 mils.
- 3. Bearing vibration alara on back of C03.
43 Visual confirmation of turbine housing 8 penetration by a blade or disc.
Slysificant loss of effluent monitoring capability & 1. Loss of LWl6 (RE223) during a release unusual Event meteorological lastruments which~ impairs ability to or perform emergency assessmeet. Loss of effluent 2. Loss of R18 (8E218) during a release monitoring may/may not require plant shutdown.
~ '
or .
- 3. a. less of wind speed indication or wind
- direction indication and
- b. Loss of 814 (RE214) and RMS II channel 1 (kE315,RE317,RE319)
, or
- c. Loss of RIS (RE215) and CR9 and BMs II channel 5 (RE225, RE226) or
- d. Loss of R21 (RE221) and RMS II amnel 2 (BE325,RE327)
- or
- e. Loss of GWil2 (RE224) and Rus II Channel 6 Fhiluns of reactor protection system to 4 3 of the following: Alert complete a trip which brings reactor subcritical 1-Hour open line (3) -
- 1. Unplanned first out annunciator en C04 i with confirmation from associated indicator /
- 2. Intermediate range detector output not decaying
- 3. >l BCC RPI indicates fully withdrawn (3) (5) See PC5 1.12.1 for 10 CFR 50.72 alotification
o -
e t
. i _. 4 .i (., t Vf x %> .
Table 1-1 -
Page &
Emergency /
Category Initiatise condition ,
Indication used classification All alarms (annianciatore) lost >15 miantes idtile amnit 1. " Annunciator power failure" on 001, 002 & Alert /
is not la cold shutdown 1(2)c03,1(2)(24 '
Loss of functions needed for cold sheatdous for >4 Ang of the following: Alert hours idtile at cold shutdeum
, 1. Less of service water. x Onit 1 = south a vest header unit 2 = north & tenet header
, . 2. Loos of both traine of aHR .
- 3. Imse of component cooling i
- 12. Abaormal Radiaties a. Eff!ssent monitorq detect levels corresponding to Airborne affluents on1r Site Raergency I.evels at site any of the following: . -
(1) >Se am/br for % hour (2) >254 mm/hr for % hour for the thyroid -
(3) >500 mm/br whole body for 2 mianstes (4) >2500 at/hr to the thyroid for 2 = h eae at the site boundary for. adrerse meteorelegy
- b. Any of the above deses seasured la the enrirene reported to dss by w s gerviser
- c. Any of the dose rates projected, based on plant parameters
- a. Efflueet monitors detect levels corre "N to Airborne efflinents caly Generet Emergency R/br whole body' (2) 5 t/hr thyroid at the site boundary imider actual meteorological conditisme -
- b. Either of the above doses measured la envirens As reported to DSS by Mr Swervisor
- c. sither of above dose rates projected based en etter plant parameters.
! l i
- 13. Fuel pendling Accident Major d,emogs to irradiated fuel in containment Both of the follouing: Alert
- 1. As reported to Dss by core 14ading Sgwr.
t 2. Alarm on Victorees on manipulator & alarm .
on R211 S
l
_ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ m _. _ _ ____ _ _
a
.- a
~
Table 1-1 -
Page 9 Emergency category Initiating condition Indication used classification Fuel damage accident with release of radioactivity Both of the following: Alert to aus111ery building (FSAR 14.2.1) I I. As reported to DSS by Supvr in charge of fuel handling & drumming area vent (R221)
- 2. Alarm on Victoreen on spent fuel pit bridge.
^
- 14. Serious or Fatal Injury Transportation of seriously or fatally injured Reported as judged by DSS Unusual Event individual from site to. hospital (espect hospitalisation for at least (Beforence EPIP 11.1) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)
- 15. Security Threat Security threat or attempted sabotage Per NASP' Per,MASP & Appendices or 1-Hour Red Phone Only Ongoing security compromise (open Line) (4)
- 16. Hazards *to Plant husual aircraft activity over facility Visual observation of Operations Sgervisor or Unusual Event operation security force Near or casite emplosion or flammable or tonic gas ! As reported to DSS by plant personnel making unusu'al Event release visual observation Missile impacts from any source on facility Visual observation by Operations Sqervisor Alert Missile impact causing damage to two trains of .
safety systems Visual observation by operations Supervisor Site Emergency Aircraft crash in protected area (within the t'ence) Visual observation by operations Supervisor Alert Enown emplosion damage to facility affecting plant Visual observation by operations Supervisor Alert operation. Tosic or flammable gaseg in facility .
environment escluding normal process gases .
Tonic or flammable gases ertering into vital areas Visual observation by operations Supervisor Site Emergency (control room, ausiliary buildi~g,n etc.).escluding normal process gases t
(4) See Dcs 1.12.1 for 10 CPR 50.72 Notification.
'i
.?
v s..
~
Table 1-1 -
Fage 10
~
Emergency category Initiating condition Indication Used Classification *
- 17. Natural Events Any earthquake activation of >2 accelerographs and verified by actual physical ground shaking or by con-tacting Dr. David Willis, University of Wisconsin, Milwaukee Seismic center at l-414/963-4602. Unusual Event any tornado visible from site Verification by Operations Supervisor - Unusual Event Low Lke Michigan water level With no CW pumps running, water level is 3.9' Unusual Event below 0' on surge chamber level & confirmed by -
measuring forebay level at 10.9' below pumphouse
, floor (7' level) ,
Earthquake greater than operating basis earth pake Earthquake with attendant structural damage of Alert containment or spent fuel pit .
Any tornado striking the facility Visual observation by Operations Supervisor Alert i
Seiche near desip level >6" of water in turbine hall &lert Winds in escess of design levels Wind speed indicated as >100 mph Alert Wind with damage . Structural damage to contalsment Site Emergency Failure of protectica for vital equipment at low And of the following: Site Emergency levels (i.e., caused by seiche > desi p levels)
- 1. >3' water in both EDG rooms.
- 2. >2' water in vital switchgear room.
- 3. >2' water in auxiliary feed pump room.
- 18. heactivity Transient Uncontrolled rod withdrawal (FS&R l'4.1.1 & 14.1.2) Unusual Event ICVCG Ralfunction (FSAR 14.1.5) Unusual Event Accidental criticality NRC Only (3)
(3) See DCS 1.12.1 for 10 CFR 50.72 Notification.
(M,
~
s, _- \ ,
~
Table 1-1 Page !! .
Emergency -
Category laitiatina Condition Indication used classificatian
\
Unusual Event awareness ;
condition that warrants establishment of technical DCS & Dh5 concurrence Alert as9 port center & emergency support center i
k Condition that warrants use of monitoring teams DCS & DSS concurrence Alert Personnel contamination Health Physicist & DCS concurrence NRC-only l-hour (10)
Any usplanned reactor trip DCS & DSS concurrence NRC-only /
1-Hour (7)
Strike by employees or guard force . Db & DSS concurrence NRC-only 1-Hour (12) loss of red phone (ENS) DCS & DSS concurrence x NRC-only 1-Hour (13)
Personnel or procedural error DCS & DSS concurrence NRC-on!'y 1-Hour (6) 10 CFR 20.403 DCS & DSS concurrence NRC-only -
l-Hour (11)
(1) (7) (10) (11) (12) (13) See DCS 1.12.1 for 10 CFR 50.72 Notification '
I .
o
EPIP 1.3
' MINOR Revision 4 s.-) , ,
01-28-83 l
l ESTIMATION OF SOURCE TERM 1.0 GENERAL The purpose of this procedure is to estimate the source term (stack release rate in Ci/second) using the low range operational stack monitors, the Eberline RMS II Radiation Monitoring Systems or direct contact radiation measurements on the plant effluent vents. The plant effluent vent stacks are:
1.1 Auxiliary Building Vent (ABVNT) 1.2 Drumming Area Vent (DAVNT) j 1.3 Gas Stripper Building Vent (GSBVNT) 1.4 CombinedAirEjectorDecayDuctfCAE)
} 1.5 Main Steam Safety Valves and Atmospheric Dump Valves 2.0 REFERENCE 2.1 EDS Report to' Wisconsin Electric Power Company concerning NUREG-0578, March 7, 1980.
- 3.0 PRECAUTIONS ~
3.1 If fuel damage or l'oss of react'or coolant system integFity has occurred, some or all of the following would be present:
3.1.1 The letdo n radiation monitor (R9) may be unusually high or offscale.
3.1.2 The containment radiation monitors (Rll and R12) may be ,
unusually high or offscale.
3.1.3 The containment area monitors (R2 and R7) may be unusually high or offscale.
3.1.4 The charging pump area monitor (R4) may be unusually high or offscale.
h.,
n
\
\
, , - . ~ m n
EPIP 1.3 Page 2
)
3 . '2 Health Physics procedures and requirements must be followed when applicable (i.e., entering a high radiation area).
3.3 Evaluation of the radiation monitoring syste::: readouts and radio-logical hazards must be completed prior to any attempt to enter the auxiliary building or facade to take a contact reading on any stack.
3.4 If' this procedure is being used for determination of emergency classi-fication, use EPIP 1.8 " Emergency Off-Site Dose Estimations" for determination of projected dose off-site. EPIP 1.8 is a shorter, however more conservative procedure for determination of projected dose.
4.0 INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, " Plant Status", is compl'eted.
5.0 PROCEDURE FOR Xe-133 EQUIVALENT RELEASE RATE ESTIMATE - WORKSHEET NO. 1 5.1 Chemistry / Health Physics Supervisor or Designated Alternate 5.1.1 Obtain EPIP-05 and EPIP-06 of EPIP 1.2, " Plant Status," for j the radiation monitoring systems.
i -
NOTE: IF EPIP-05 AND EPIP-06 IN EPIP 1.2, " PLANT STATUS," ARE NOT COMPLETED, OBTAIN THE METER READINGS FOR EACH PLANT EFFLUENT VENT STACK FROM THE REMOTE CONTROL ROOM READOUT AND RECORD THIS ON WORKSHEET.NO. 1 AND THEN PROCEED
- WITH' STEP 5.1.3.
NOTE: PLANT EFFLUENT VENT. STACK MONITOR READINGS ARE ALSO AVAILABLE FROM THE TECHNICAL SUPPORT CENTER DATA LOGGER. SEE ATTACHMENTS 1.3-1, 2 & 3.
5.1.2 Enter the meter readings.and flow rates in the appropriate columns on Worksheet No. 1 for the indicated vents. If the readings are offscale, not monitored, or the monitors are inoperable, enter the appropriate word "offscale," "not monitored," or " inoperable" in the meter reading column for the vent affected. .. .
5.1.3 Designate individuals in accordance with ALARA concepts to
_ obtain meter readings of the vents whose Eberline RMS II data is not available and the main steam header by per-forming Section 5.2 of this procedure if required.
'~
m NOTE: IF STEP'5.1.3 NEEDS TO BE COMPLETED BECAUSE EBERLINE
- RMS II DATA IS NOT AVAILABLE, OR IF A STEAM GENERATOR
._*E TUBE RUPTURE IS, BELIEVED TO HAVE OCCURRED WHICH PRODUCES THE POTENTIAL FOR RELEASES, OR RELEASES ARE IN PROGRESS FROM THE MAIN STEAM HEADER OR THE ATMOSPHERIC STEAM DUMP, THEN PERFORM SECTION 5.3 0F THIS PROCEDURE AFTER APPROPRIATE MEASUREMENTS HAVE s
BEEN TAKEN IN SECTION 5.2.
~
_ _ _ _.. l
~
EPIP 1.3 Page 3 N
- x ,
5.1.4 Perform Section 5.3 of this procedure to determine the gross Xe-133 equivalent release rate' estimate.
' ~
5.2 Di' rect Stack Survey Team Designees
- NOTE: THE FOLLOWING SECTION WILL NOT BE INITIATED UNTIL THE EVALUATION DISCUSSED IN PRECAUTION 3.3 HAS BEEN COMPLETED.AND THE SITE MANAGER (DUTY & CALL SUPERINTENDENT), THE DUTY &
CALL HEALTH PHYSICS SUPERVISOR, AND THE DUTY SHIFT SUPERVISOR /
HAVE APPROVED INITIATION. THIS SECTION WILL BE ACCOMPLISHED '
UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION.
5.2.1 Determine the most direct and desirable route to the plant effluent stack to be monitored.
5.2.2 Determine the Health Physics requirements to be met for the passage to the vent areas.
5.2.3 Determine the appropriate survey instrument to be used for the plant effluent vent to be monitored.
.. 5.2.4 Proceed by the route determined in St'ep 5.2.1 to the stack
') and record the survey instrument ' reading in contact with the
- stack in the columns provided on Worksheet No. 1,'Part C, Plant Effluent Vent Stack Contact Readings.
~
NOTE: IN THE' CASE OF THE MAIN STEAM SAFETY VALVES AND ATMOSPHERIC STEAM DUMP VALVES, THE READING WILL BE TAKEN IN CONTACT WITH THE CENTERLINE OF THE MAIN STEAM HEADER, THREE FEET FROM THE MAIN STEAM LINE.
SHIELD THE PROBE (WITH A MINIMUM OF. 25 INCHES OF "
LEAD) ON THE SIDE $ FACING THE MAIN STEAM LINE'AND' THE CONTAINMENT.
5.3 Chemistry / Health Physics Supervisor or Designated Alternate -
5.3.1 Choose the appropriate vent stack readouts in Part A, B,* or C of-Worksheet No. 1 to convert readings to a Xe-133 equiva-lent release rate. That is if the low range monitors go offscale, use the high range monitors. Conversely, i,f the normal monitors are onscale, use the normal monitors, oc.if .
' both normal and high range monitors are offscale or inoper-able, use the vent stack contact readings.
5.3.2 Use the appropriate attached conversion curves for each of the plant effluent vent to convert the chosen vent stack readout, (cpm or R/ hour) and flow rate, from St'ep'5.3.1 to
/ an Xe-133 equivalent release rate in Curies /second and '
[v0 record the value on Worksheet No. 1, Part F, Estimate of Gross Xe-133 Equivalent Release Rate. Enter the appropriate
=
,.m,- , 9-. -
y,., .--.,,c _
-y --- c _,.,,%-__,,.
EPIP 1.3 '
Page 4 I
l --
- ' word "offscale," "not monitored," or " inoperable" for the cases where the plant effluent vent was not monitored, offscale, or inoperable.
NOTE: THE FOLLOWING QUALIFYING NOTES MUST BE RECOGNIZED.
- 1. If the actual flow rate is different than the conversion curves flow rate, a ratio of:
Actual Flow Rate Assumed Flow Rate {'
should be applied to determine the release rate.
(Ratio) x Release Rate Value = Adjusted Xe-133 5 Release Rate
= Equiv. Release Rate
- 2. If the main steam header vent release rate needs to be determined, the following steps must be applied. _ _ .
- a. Obtain from the Shift Supervisor an estimated
- flow rate through the main steam hatder in
-, lbm/ hour of steam being dumped to the environ-ment and the specific volume (v) of the steam.
At 1000 psia, specific volume is 0.446 ft.3/lbm.
At 500 psia, specific' volume is 0.928 ft.3/lbm.
3 lbm/hrxvft x7.86jCt E.
~. b. Convert contact re'ading obtained at th'e' main steam header to pci/cc using the appropriate conversion factor (Worksheet No. 1 Sect. C)
, for the main steam header.
pCi/cc
- c. Multiply flow rate obtained in Step (a) by the concentration obtained in Step (b) to obtain the release rata (Xe-133 equivalent) from.the main steam header.
Flow Rate (cc/sec.)
- Concentration _ Main Steam Heade
~
(pCi/cc) Release Rate i 5.3.2 Sum the values (1) through (5) on Worksheet No.1, Part F,
~
or use grab sample results #7 on Worksheet No. 1, Par't F,
'; ~ c -
to determine the gross Xe-133 equivalent release rate.
%L:
X
c -
.~
- = . . .
~
EPIP 1.3
~ Page 5 i _ , ,
/
NOTE: IF GRAB SAMPLE RESULTS ARE AVAILABLE, THE RESULT OF SUCH SAMPLES SHOULD BE MORE ACCURATE THAN GROSS MONITOR READINGS AND HENCE SHOULD BE USED IN LIEU OF THE RELEASE RATES CALCULATED ABOVE OR IN ADDITION j TO THE ABOVE IF THE RELEASE IS FROM AN UNMONITORED RELEASE. PATH.
S.3.3 Report the calculated gross Xe-133 equivalent release rate 4
to the Shift Supervisor and the Technical Support Manager.
f s
E i .
1 e o e
G
- D e
W. ,
Y enes
{
. . w -
..g -
4
- EPIP 1.3 ~
Page 6 , .
- ,s l
4
- WORKSHEET NO. 1 l
}
j Xe-133 EQUIVALENT RELEASE RATE 7' '
A. LOW RANGE OPERATIONAL VENT STACK READOUTS Conversion Xe-133 Equiv.
l Meter Reading Flow Rate Factor Release Rate j Vent (cpm) (cfm) Ci/sec+ cpm Ci/sec f 9
! Auxiliary Building R14 61400 5.8 x 10 8
Drumming Area R21 43100 1.3 x 10
, 6 i Gas Stripper Building GW-112 13000 2.0 x 10 l Combined Air Ejector ,9 Decay CR-9 25 8.0 x 10 -
B. EBERLINE RMS - II VENT STACK READOUTS l s NOTE: THESE READINGS ARE ALSO AVAILABLE ON THE TECHNICAL SUPPORT CENTER DATA LOGGEl(. ATTACHMENTS 1.3-1, 2, 3.
x jl _ ,
Conversion Xe-133 Equiv.
j Meter Reading Flow Rate Factor Release Rate l Vent (R/ hour) (cfm) Ci/sec+R/hr Ci/sec 3
] Auxiliary Building Ch. #1 61400 3.0 x 10 j Drumming Area'Ch.' #2 43100 2.1 2
l Gas Stripper Building Ch.-#6 13000 6.2 x 10 i
! Combined Air Ejector j Decay Ch. #5 25 3.4 1
l C. PLANT EFFLUENT VENT STACK CONTACT READINGS Conversion . Xe-133 Equiv.
Meter Reading Flow Rate Factor Release Rate Vent R/hr) (cfm) Ci/sec R/hr Ci/sec 1
- Auxiliary Building 61400 30 2
Drumming Area 43100 2.3 x 10
^
- G 4
- / Gas Stripper Building 13000 8 x 10 2
Combined Air Ejector _ Decay 25 1.6 x 10 s
Main Steam Header (See 8 x 10 See Section E Sect. E)
s 9
~
)
D. ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO Actual Flow Rate x Release Rate Value Assumed Flow Rate
= Adjusted Releast Rate f' I
( )x = .
E. STEAM HEADER CONTACT READING CALCULATION
- 1. Ibm /hr x specific volume ft 3 /lbm x 7.86 cc hr/ft3 sec NOTE: At 1000 psia specific volume = .446 ft 33/lbm At 500 psia specific volume = .928 ft /lbm lbm/hr x ft 3/lbm x 7.86 cc hr/ft sec 3
=
cc/sec
- 2. Contact reading from Section C:
R/hr = pCi/cc
- 3. Steam header release rate:
Flow rate cc/sec x Concentration pCi/cc = Release Rate 6
cc/sec x x 10 Ci/cc =
Ci/sec (1) (2)
F. ESTIMATE OF GROSS Xe-133' EQUIVALENT RELEASE RATE *
%e-133 Equivalent Release Rate Vent '
(Curies /Sec.)
- 1. Auxiliary Building ,
- 2. Drumming Area
- 3. Gas Stripper Building
- 4. Combined Air Ejector Decay Duct --
- 5. Main Steam Header
- 6. Sum (Gross Xe-133 Equiv. Release Rate) l
- O_R
.h$ h 7. Grab Sample Results = Ci/sec.
\;z/ '
l
'\
Completed By Time \
Date
~
6 . . .
N
- ATTAC& W l.3-1
< i 3 -
w.
J DRUMMING AREA VENT STACK RMS-II CH #2 AND '
COMBINED AIR EJECTOR DISCHARGE RMS-II CH #5 VOLTAGE TO R/HR CCNVERSION TABLE RANGE 1 to 10' R/HR I ,
~
I Volts ' 47 nits R/hr O. .001
. 0.1 .001.35 l 0.2 .001.847 0.3 .002.511 l- 0.4 _ . . .003.414 0.5 .004.641
- 0.6 .006.309
- .__ - )
0.7 - .008.576 0.8 .011.659 0.9 .015.848 i 1. .021.544 1.1 .029.286 1.2 .039.810 1.3 .054.116 1.4 .073.564 1.5 .100
. 1.6 .135.935 1.7 .184.784
- 1. 8, .251.188 j 1.9 .341.454 j 2. .464.158 2.1
.630.957 2.2 .857.695 2.3 1.165.914 2.4 1.584.893
. 2.5 2.154.434 -
2.6 2.928.644 5
2.7 3.981.071 2.9 5.411.695 - -
2.9 7.356.422
~
- 3. 10.000 5
s u s.
?,
- y .
i ATTACHMENT 1.3-2 -
, ,~
- i a i
l 2 UNIT 1 RMS-II CH #3 & UNIT 2 RMS-II CH #4 j CONTAINMENT PURGE STACKS 3
.i j
VOLTAGE TO R/HR CONVERSION TABLES RANGE 10 ' TO 10' R/HR l
- Volts ' Units - R/HR
- j. O. O.1 O.1 .135 0.2 .184
- 0.3 .251 0.4 .341 4 0.5 .464 0.6 - - -
.630
) 0.7 .857s
-s 0.8 1.165 j ;. } 0.9 1,.584 2.154 l.
- 1.1 2.928 l.2 3.98L 1.3 5.411 1.4 7.356 1.5 10.'
1.6 13.593 1.7- . 18.478 1.8 25.118 1.9 34.145
' 2'. 46.415 2.1 63.095 2.2 85.769 2.3 116.591 2.4 158.489 .
2.5 215.443 2.6 292.864 2.7 398.107 2.8 541.169 2.9 735.642 i 3. 1000.
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, ATTACHMENT 1.3-3
., AUXILIARY BUILDING VENT STACK RMS-II CH #1 &
. ,, GAS STRIPPER BUILDING VENT STACK RMS-II CH #2 VOLTAGE TO R/HR CONVERSION TABLE RANGE 10-' TO 10'. R/HR i
Volts Units - R/HR
.J i 0. 0.01
- 0.1 .013 O.2 .018 j 0.3 .025 O.4 .034 l 05
. .046 1 0.6 .063
- ' 0.7 .085 O.8 .116
.; 0.9 .158
- 1. -
.215
- 1.1 .292 4
..- 1.2 .398 i . ! 1.3 .541-
.735
] l.4 i 1.5 1.
1.6 1.35 1.7 1.847 1.8 2.511 l.9 3.414 l 2. 4.641 2.1 6.309 8.576' 2.2
- 2.3 ~
11.659 j 2.4 15.848
- 2.5 21.544 ,
j 2.6 29.286
- 2.7 39.810
- 2.8 54.116
+
2.9 73.564
)
- 3. 100.
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EPIP 6.1 '
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l Revision 2 '
'54# _, 01-28-83 LIMITED PLANT EVACUATION 1.0 GENERAL '
This procedure describes the steps to be taken in the event of a limited i plant evacuation. This procedure will be used when conditions warrant small areas ~inside the protected area to be evacuated. Assembly areas are ;
l defined on a case-by-case basis. i
2.0 REFERENCES
! None
- 3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged.
3.2 Health Physics personnel may require evacuation of rooms, areas, or
) the affected portions thereof to prevent the unnecessary spread of
. contamination.
4.0 INITIAL CONDITIONS
.A limited plant evacuation will be. considered when 'any of the following conditions exist.
4.1 Unanticipated radiation level increase at any, area radiation monitor
'in excess of 100 mr/hr. . .
4.2 A ncn-scheduled containment evacuation alarm.
, 4.3 Unanticipated airborne activit'y at any area gas or particulate monitor which indicates activ.ity in excess of the maximum permissible concentrations specified in Appendix B Table I to 10 CFR Part 20.
4.4 Excessive radioactive surface contamination levels due to a major spill of radioactive materials. ..
4.5 other emergency conditions, such as fire, that may endanger human life or health as deemed necessary by the Duty Shift Supervisor or Health Physics Supervisor.
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5.0 PROCEDURE 5.1 Shift Supervisor / Designee 5.1.1 Identify the areas that have to be evacuated.
j 5.1.2 Choose the assembly area where personnel will be relocated.
i If possible use the following areas:
- a. Health physics station, if evacuation is from areas within the controlled. area l or
- b. Plant cafeteria, if evacuation is from areas outside the
, controlled area.
1 i 5.1.3 Fill in the underlined announcement blanks in Step 5.1.4 with the appropriate information determined in Steps 5.1.1
! and 5.1.2. -
i 5.1.4 Sound the plant evacuation alarm (and fire alarm if appro-f a priate) and announce over the PA system: (NOTE: AN ,
g ANNOUNCEMENT CANNOT BE MADE WHILE THE ALARM IS SOUNDING.)
" ATTENTION, ALL PERSONNEL: THERE ARE CONDITIONS AT THE PLANT -
THAT WARRANT A LIMITED PLANT EVACUATION IN THE AREA (S). ALL PERSONNEL IN THE AREA (S) 1 (Specify Area) '
EVACUATE IMMEDIATELY AND REPORT TO THE i AND AWAIT FURTHER. INSTRUCTIONS." .
(Specify Area) 5.1.5 Repeat the' alarm sounding and announcement two more times.
Repeat the alarm and announcement again after an interval of j two to five minutes.
j - 5.1.6 Notify the Duty & Call Superintendent and Health Physicist of the limited plant evacuation.
5.1.7 . Initiate EPIP 8.1, " Personnel Assembly and Accountability,"
if not already done.
5.1.8 Initiate EPIP 7.0, "CHP Radiological Response and Prepared-ness," as required.
5.1.9 Reevaluate the ability to re-enter evacuated area (s) and c attempt to isolate affected area (s) as required.
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~ ;J' 5.1.10 Consider the initiation of EPIP 6.2, " Plant Evacuation," if the hazard continues to increase in severity.
5.1.11 Work may resume in evacuated area (s) when it has been deter-mined by the Shift Supervisor and a Chemistry & Health Physics Supervisor that no significant radiation hazard or other hazard to personnel remain.
5.2 Health Physicist / Health Physics Supervisor 5.2.1 Determine the scope of the radiation and contamination problem by implementing radiation surveys of affected area (s).
5.2.2 Specifying appropriate protective devices, commence a decon-tamination operation and set up appropriate health physics postings of the affected area (s), if required.
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. s EPIP 6.2 MINOR m Revision 2 ~
) -
01-28-83 PLANT EVACUATION 1
k.
j 1.0 GENERAL This procedure describes the steps and instructions to be taken in the
] event of a plant evacuation. This procedure will be used when conditions 4
are such that the plant, including the protected area, must be evacuated.
! Assembly areas are defined in particular locations and are constant for all j plant evacuations.
2.0 REFERENCES
l None 3.0 PRECAUTIONS AND LIMITATIONS-3.1 All actions and notifications should be appropriately logged.
3.2 A plant evacuation will probably not be necessary for an Unusual
- s Event or Alert classification.
'1
'3.3 Unless otherwise" directed by supervision, personnel should exit the controlled area as they usually would after discarding protective 4
clothing and frisking themselves at " Checkpoint Charlie."
1 3.4 Unles's otherwise directed by the guard at the gatehouse, personnel s
, .' leaving the protected area should punch out at the gatehouse, leave 1
their ID badges at SAS and exit through the south door, bypassing all other monitoring devices'.
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] 4.0 INITIAL CONDITIONS -
4 A plant evacuation will be considered when any of the following conditions j exist. .
4.1 Radiation levels in general areas of the protected area are in excess of 100 mr/hr.
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4.2 Airborrie activity in general areas of the protected area are in l excess of maximum permissible concentration and exposures are ex--
pected to exceed 40 MPC hours.
4.3 Other emergency conditions where it is deemed necessary to evacuate nonessential personnel from the plant.
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EPIP 6.2 i
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5.0 PROCEDURE 5.1 shift Supervisor / Designee 5.1.1 Notify security personnel that a plant evacuation is imminent and instruct them to implement procedure PBSP 1.9,
" Emergency Evacuation Procedure."
5.1.2 Notify the Duty & Call Superintendent, Duty Technical Ad-visor, and the Superintendent --Chemistry & Health Physics or Health Physicist of the impending plant evacuation.
5.1.3 Alert the Energy Information Center of the impending plant evacuation, by calling Ext. 246. Request that visitors be evacuated from the center using EPIP 6.4, " Energy Infor-mation Center Evacuation."
5.1.4 Sound the plant evacuation alarm and fishermen's pier evacu-ation alarm and announce over-the P.A. System:
" ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL, THERE ARE
, CONDITIONS AT THE PLANT THAT WARRANT A PLANT EVACUATION.
l ALL PERSONNEL SHALL IMMEDIATELY ASSEMBLE IN THE FOLLOWING
.J AREAS:
PLANT PERSONNEL REPORT TO WITH ASSIGNED EMERGENCY EMERGENCY DUTIES LOCATIONS PLANT PERSONNEL REPORT TO NOT ASSIGNED EL. 18.5' 0F EMERGENCY DUTIES THE TECHNICAL SUPPORT CENTER BUILDING VISITORS AND REPORT TO CONTRACTORS . SITE BOUNDARY CONTROL CENTER AND AWAIT FURTHER INSTRUCTIONS."
5 .1. 5' Repeat the alarm sounding and announcement two more times.
5.1.6 Initiate EPIP 8.1, " Personnel Assembly & Accountability," if not already done.
5.1.7 . Initiate EPIP 7.0, "CHP Radiological Response and Prepared-
, ness," if not already done.
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5.1.8 Consider the initiation of EPIP 6.3, " Exclusion Area Evacu-ation," if the hazard continues to increase in severity or spreads to areas outside the protected area or-it is deemed l
necessary to evacuate personnel from established assembly areas at the plant.
F 5.1.9 Contact the Township of Two Creeks and request them to make the Two Creeks Town Hall available for an assembly area for plant personnel by calling 755-2049 or 755-4196.
NOTE: (Telephone numbers are applicable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.)
5.2 Visitors and Contractors These persons should keep their dosimeters and TLD's, exit at the gatehouse, and report to the site boundary control center. When exiting the gatehouse, the portal monitors should be bypassed and the south door should be used. At the site boundary control center, people should remain in their cars except the supervisors doing accountability checks. After aEcountability is done, the Health Physics Director will determine what personnel monitoring will be
, required. After the Health Physics Director is satisfied with con-l tamination levels, the dosimeters' and TLD's will be collected prior to release.
5.3 Personnel Not Assigned Emergency Duties These persons should keep their dosimeters and TLD's and report to the assembly area on the 18.5' level of the technical support center building.'
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I EPIP 6.3 MINOR l < ?s Revision 1
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/ 01-28-83 _~
1, EXCLUSION AREA EVACUATION f
i 1.0 GENERAL This procedure describe the steps and instructions to Ime taken if an exclusion area evacuation is anticipated. This procedure will be used when conditions are such that the plant and the area around it, i.e., energy information center, nature trail, switchyard, fishing pier and roadways to the exclusion gates, must be evacuated.
2.0 REFERENCES
1 None ,
3.0 PRECAUTIONS AND LIMITATIONS
- 3.1 All actions and notifications sho'uld be appropriately documented.
3.2 The security checkpoint, assembly area, personnel monitoring and
) decontamination station can be established at either the site
, boundary control center 'or the Two Creeks Town Hall. This will depend upon the magnitude of the release and meteorological conditions. The Health Physics Director will recommend to the Site Manager which facility is preferred.
h- 4.0 PREREQUISITE CONDITIONS.
4;l EPIP 6.2, " Plant Evacuat' ion," complete'd. .
4.2 Exclusion area evacuation will be considered when any of the
_. following conditions exist.
4.2.1 Radiation levels in general areas of the exclusion area are in excess of 10 mr/hr whole body dose rate. (See Section 1.0) 4.2.2 Airborne concentrations of radiciodine are greater than 5.3 x 10 7 pCi/cc averaged over any two hour period in general areas of the exclusion area.. (This would result in a two hour dose to the thyroid of 2 Rem assuming that the predomi- ;
nate isotope is I-131.) '
4.2.3 When emergency or support personnel radiation doses in assembly areas and/or emergency response facilities are approaching or exceeding the following radiation dose
+% limits:
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EPIP'.6.3
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- a. Whole body gamma: N s 1.5 Rem
- b. Thyroid: 5 Rem
- c. Beta skin dose: 3 Rem 4.2.4 As other emergency conditions may dictate.
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5.0 PROCEDURE 5.1 Designee 5.1.1 If not already done, contact the Township of Two Creeks and request them to make the Two Creeks Town Hall available for an assembly area for plant personnel by calling 755-2049 or 755-4196.
NOTE: (Telephone numbers are applicable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.)
5.1.2 Ensure that EPIP 6.2,-" Plant Evacuation," is completed.
5.1.3 Instruct the Chemistry / Health Physics Supervisor and the '
Health Physics Director to identify assembly areas or support centers that must be evacuated in accordance with the exposure criteria listed in Section 4.2 above.
5.1.4 Instruct the Health Physics Director to establish a personnel monitoring and decontamination station a,t the Two Creeks Town Hall or the site boundary control center.
5.1. 5 Instruct the Sh'ift. Security Lieutenant to establish a check
-point and assembly area at the Two Creeks Town Hall or site boundary control center.
5.1.6 For each assembly area or support center identified for need of evacuation in Step 5.1.3, . designate the alternate location to be used. If possible, use the alternate areas
- listed in the following table.
I
, Support Center or Assembly Alternate Location l
Area to be.' Evacuated ,
to be Used **
Technical Support Center Control Room Security Building Site Boundary Control Center (Extension Building) or Two Creeks Town Hall
. ,4, Onsite Operations Support Center Site Boundary Control Center j q{ (Staging Area) or Two Creeks Town Hall 1
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EPIP 6.3 ew Page 3 Emergency Support Center Two Creeks Town Hall Site Boundary Control Center Two Creeks Town Hall 5.1.7 Inform each assembly area and support center identified in
' Step 5.1.3 that personnel must be evacuated and communicate to them the following information.
- a. The alternate location to which personnel should report (Refer to step 5.1.6 of this procedure).
- b. Preferred route to folldv to the alternate assembly area.
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- c. Protective measures to be taken by personnel before they evacuate the area.
- d. After arriving at new assembly area, initiate personnel accountability procedures in accordance with EPIP 8.1,
" Personnel Assembl~y~and Accountability," and report results to the technical support' center or control room.
) 5.1.8 Continue to update all assembly areas and support cent'ers with respect to where personnel should report and insure that personnel are made aware of possible radiation hazards in areas requiring access and re-entry.
5.1.9 Re-evaluate the abilit to re-enter plant assembly areas or support centers and attempt to isolate affected areas as required.
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' EPIP 7.3.2 MINOR
] , Revision 5 l
01-28-83 l
POST-ACCIDENT SAMPLING AND ANALYSIS OF POTENTIALLY HIGH LEVEL REACTOR COOLANT
1.0 INTRODUCTION
1.1 This procedure outlines the steps necessary to collect, handle and
. analyze a high level reactor coolant sample which could result from gross fuel failure.
1.2 Eq0ioment List Set up the following in the primary sample hood prior to collecting your sample:
1.2.1 The equipment detailed in Figures 2A and 2B, with the exception of the sample bomb.
1.2.2 Two magnetic stirrers and two 50 ml poly beakers and a 50 ml beaker.
1.2.3 h pH/mv meter, pH probe and chloride /re'ference elec-trodes. .
1.2.4 A piston burette.
1.2.5 A lead brick wall of sufficient size to store residue from analysis. .
1.2.6 Chemical transfer pump.
1.2.7 Remote handling tools located in the cabinet below the hood.
- 1. 2.'8 Prepare a 1.0 liter sidearm flask with a correctly sized solid stopper and rubber septum over the sidearm.
1.2.9 Gas syringe ...
The following equipment is also necessary for this procedure and need to be made ready.
1.2.10 .The gas partitioner for H2 analysis.
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EPIP 7.3.2 j --s Page 2 s
! 1.2.11 The special cart used for transport of the sample bomb.
! N 1.2.12 Tools for connecting and disconnecting sample bomb; i.'e.,
11/16" open end wrench or equivalent.
1.2.13 Remote valve turning tool. This tool as well as those I mentioned in Step 1.2.12 are necessary for sampling and should be taken along and placed on the sample bomb transport cart.
The following reagents are also necessary and need to be prepared.
1.2.14 0.1N NaOH for boron. Obtain a supply from normal boron analysis,.
1.2.15 2.0M HNO3 for chloride analysis.
4 1.2.16 Manitol for boron analysis.
1.3 Preliminary Steps Initials I 1.3.1 StandardizethepHmebr. -
) 1.3.2 organize as much of the' equipment as possible behind lead brick walls in an arrangement that allows for unobstructed view of all operations with the aid of the convex mirror.
(See Figure 2.)
1.3.3 Put new rubber septum on gas bomb.
1.3.4 Condition.and check out chloride / reference electrodes.
1.3.5 Check out and prime the piston burette with fresh 0.1N NaOH solution.
1.3.6 Check out the operation and calibration of the chemical transfer pump by pumping chloride free deionized water through the i Pump.
2.0 PRELIMINARY EVALUATION
- NOTE: THIS EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT TO ENTER THE AUXILIARY BUILDING OR SAMPLE ROOM TO OBTAIN A REACTOR COOLANT SAMPLE UNDER EMERGENCY CONDITIONS.
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- 2.1 Possible Indication of Fuel Damage Initials Some or all of the following would be present if fuel damage had occurred:
2.1.1 The letdown radiation monitor (R9) would be unusually high or offscale.
2.1.2 The containment radiation monitors (R11 and R12)
/ would be unusually high or offscale.
2,1.3 The containment area monitors (R2 and R7) would be reading unusually high or offscale. .
2.1.4 The auxiliary building stack monitor (R14) would
, show a significant increase due to auxiliary' building airborne activity from the letdown and charging pump areas.
l 2.1.5 Evaluation of Sample Room Conditions
- a. The sample room area monitor (R6) and T charging pump area monitor (R4) would give .
) an indication of conditions in the auxiliary building and sample room.
- b. After evaluation of the radiation monitoring system readouts, Health Physics will determine what airborne and radiation surveys would be. .
appropriate before auxiliary building entry.
- c. ' verify the requirement.s for auxiliary building '
sample room entry, i.e., (1) RWP requirements, (2) clothing requirements, (3) respiratory requirements, and (4) dosimetry requirements including extremity dose. monitoring requirements, and (5) health physics coverage requirements , [
. including timekeeping.
2.2 Possible Loss of Component Cooling -
2.2.1. Verify that component cooling is still in service . l to the affected unit. Sample cannot be obtained without component cooling to sample room heat exchangers.
3.0 REACTOR COOLANT SAMPLING PROCEDURE NOTE: THIS PROCEDURE SHALL NOT BE INITIATED UNTIL THE EVALUATIONS DIS- .
'- D)_ CUSSED IN SECTION 2.0 HAVE BEEN COMPLETED AND REVIEWED BY DUTY &
CALL SUPERINTENDENT (COORDINATOR), DUTY HEALTH PHYSICS SUPERVISION AND THE DUTY SHIFT SUPERVISOR, AND THEIR APPROVAL HAS BEEN GRANTED.
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i 3.1 Collecting a Pressurized Sample (Refer to Figure 1) Initials
! NOTE: THE FOLLOWING STEPS ILL BE ACCOMPLISHED UNDER THE
] DIRECTION OF HEALTH PHYSICS SUPERVISION AND ONLY i 4 AFTER COMPLETING SECTION 1.0 0F THIS PROCEDURE.
3 .' l .1 ' The following steps (a through f) must be j accomplished before opening the incontainment j sample isolation valve 955 (Step 3.1.2) and the j hot leg sample isolation valve 966C (Step 3.1.3).
i a. Verify that'the demineralized water header
, pressure is approximately 100 to 120 psi.
! NOTE: THIS STEP MAY BE DELETED IF REACTOR j MAKEUP WATER IS USED FOR THE FLUSH.
- b. Proceed to the sample room and install the shielded sample bomb on the outside wall of
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the sample room using the fittings provided.
, CAUTION: BEFORE REMOVING THE SWAGE LOCK' CAPS l 3 TO INSTALL THE BOMB, OPEN VALVES
')'
939,'940 AND 941 TO RELIEVE SYSTEM
" PRESSURE. CLOSE, VALVES 939, 940 l ,
i AND 941. PLACE A WASTE BUCKET ~
2 DIRECTLY UNDER THE BOMB. USE A PAPER
. TOWEL SHIELD AND RUBBER GLOVES WHEN
! REMOVING CAPS. .
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) After installing'the bomb' verify that the i dimineralized water line is connected from "
I valve'945 t'o the demineralized wate'r
- manifold. Ope.n demineralized H 2O valves i
945, 947, and 948 and check for leaks on the bomb fittings. Shut valves 945,-
l 947, and 948.
j c. Enter.the sample room and close the following valves on the sample panel.
l 1. 961C - Normal hot leg sample bomb inlet. .
1
- 2. 964C - normal hot leg sample bomb outlet.
- 3. 965C - normal hot leg' sample bypass.
- 4. 968 - normal hot leg' return valve.
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- 5. 971 - normal hot leg sink sample valve.
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- d. Further verify that there is component cooling i flow to the sample room heat exchangers by viewing the local flow indicator (FI-603)
. on the sample panel.
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- e. Open the following valves on the sample panel.
I 1. 969A - sample system purge to volume control tank. ,
- 2. 956C - normal hot leg sample supply
- valve.
1 3. 990 - residual heat removal sample '
supply valve.
a l f. Open vsfve 938 (high level hot leg sample valve) located on the wall behind the sample '
j panel.
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- g. Leave the sample room.and open the following i valves on the sample room wall. -
- 1. 939 - sample bomb inlet. (Wide Open)
- 2. 940 - sampfe bomb bypass. (Wide Open)
- 3. 941 - sample bomb outlet. (Wide Open) -
. NOTE: FOR DRILLS AND. PRACTICE OPEN ,
VALVE 941 ONLY ONE-QUARTER TURN
, 'TO ELIMINATE Nc16. GAMMAS. , , ,
- 3.1.2 Open the incontainment hot leg sample isolation i
valve (valve 955) and the residual heat removal sample isolation valve (valve 959) by means of the switches located outside the No. I pipeway for Unit 1 or No. 4 pipevay for Unit 2.
CAUTION: IF THE AFFECTED UNIT IS ALREADY i ON RHR, LEAVE THE AREA IMMEDIATELY j AFTER OPENING VALVE 959 AS BACK- ..
i GROUND RADIATION LEVELS WILL RISE SHARPLY.
]
4 If the valve No. 955 will not open because of containment isolation, perform the following i steps (1 through 3).
- 1. Request that the Control Room reset the con-tainment isolation signal.
- 2. Turn the local control switch positions for valves 951, 953, and 955 to the "close a position.
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. Page 6
- 3. Turn the. local ~ control switch for valve 955 to the "open" position.
- ' NCIE: SECTION 3.1.2 HUST BE ACCOMPLISHED BEFORE SAFETY INJECTION RECIRCULATION HAS BEGUN.
3.1.3 Leave the area and request control room -
supervision to open the hot leg sample isolation valve (966C). .
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3.1.4 Verity sample flow by radiation level.
3.1.5 After a recirc time of'30 minutes, return to the sample station and using the remote valve operating tool, fully open valves 9B and 9A and
- 8A and 8B. ,
- a. Slowly and completely close valve 940. ,
- b. Leave the primary auxiliary building.
NOTE: THE VALVE OPERATING TOOL t'HOULD BE USED m TO OPERATE ALL VALVES EXCEPT 945, 946, I 947 AND 948 (FLUSH VALVES).
3.1.6 After 15 additional minutes, return to collect the sample. Clo'se valves 9B and 9A and then valves 88 and 8A using the remote valve operating tool. Make note of the sample collection time.
NOTE: DO NOT DISCONNECT THE SAMPLE BOMB UNTIL '
SAMPLE FLOW 'IS SECURED AND THE DI FLUSH' IS COMPLETE AS EVIDENCED BY REDUCTION IN RADIATION LEVELS.
3.1.7 Request control room supervision to immediately close the hot leg sample isolation valve 966C.
NOTE: IT IS VERY IMPORTANT THAT THE HOT LEG
- SAMPLE ISOLATION VALVE 966C IS CLOSED .
PRIOR TO STARTING THE DI FLUSH. WAIT FOR CONFIRMATION FROM THE CONTROL ROOM.
4.0 SAMPLE LINE FLUSHING l
l 4.1 Leave valve 959 open,' and fully open valves 940 and 941. 1 "N Open valves 945 and 946. Allow the lines to flush for at
-' least 15 minutes. Do not remain in the area of the sample station during this flush.
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EPIP 7.3.2 Page 7
.s 4.2 After about 15 minutes return and measure radiation levels. i If a chemistry & Health Physics Supervisor determines that ,
the levels are satisfactory, close whitey valve 946 and using the remote valve tool, close valve 939. Then open valve 947 and valve 948 and allow about a 15-minute DI flush. !
. 4.3 After about 15 minutes, close valves 940 and 941 with the !
remote valve tool and then close valves 945, 947, and 948.
Disconnect valve 945 from the demineralized water manifold and cap both ends. Disconnect the sample bomb from the ,
fittings using a paper towel to prevent spraying. Remove the shielded sample bomb from its support. Remove excess ,
liquid from the top and bottom bomb fittings with a ;
syringe and dispose behind lead shielding. Replace the '
Swagelok caps on the wall fittings and on the bomb. [
Transport the bomb, remote valve tool and wrenches to the chemistry lab on a cart.
NOTE: AFTER DRILLS AND PRACTICE RUNS, RETURN ALL I EQUIPMENT AND VALVE LINEUPS TO NORMAL AS FOLLOWS:
3 '
) CLOSE VALVES: -
- 1. 966C - Containment hot leg sample isolation valve 2.. 961C - Normal hot leg sample bomo inlet
- 3. '964C - Normal hot leg sample bomb outlet-
- 4. .965C - Normal hot leg sample bypasr' I
- 5. 971 -Normal hot leg sink sample valve
- 6. 938 - High level hot leg sample valve
- 7. 939 - High level sample bomb inlet
- 8. 940 - High level sample bomb bypass e op
- 9. 941 - High level sample bomb outlet
- 10. 945, 946, 947, 948 - Demineralized water flush valves NOTE: DISCONNECT VALVE 945 FROM THE DEMINERALIZED N WATER MANIFOLD. ADVISE CONTROL TO REDUCE
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l DEMINERALIZED WATER HEADER PRESSURE TO NORMAL.
\ OPEN VALVES:
\ 1. 956C - Normal hot leg sample supply valve
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EPIP 7.3.2 Page 8
- 2. 968 - Normal hot leg return valve
- 3. 959A - Sample system purge to volume control tank 5.0 SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASEOUS l AND LIQUID COMPONENT (Refer to Figures 2A and 2B) 5.1 Collecting the Gaseous Sample From the Pressurized Sample ,
1 5.1.1 Place the shielded sample bomb in the sample holder in the primary sample hood.
5.1;2 Connect the sample bomb to the shielded gas ,
collection bomb by means of the fittings provided. Place lead bricks in the area of this connection for shielding.
. 5 .' 1. 3 Connect the valve manifold to the opposite end of
, the sample bomb and verify that valve 11 on the manifold is open. --
m 5.1.4 Make sure that the vacuum line is attached to i the gas collection bomb at the valve 1 location. .
Open valves 1 and 2. Secure valve 3. Evacuate the gas bomb and connecting lines. With vacuum still on, secure valve 1. Secure vacuum.
5.1.5 Before proceeding, make sure no inleakage has occurred into the gas bomb by observing the vacuum gauge reading. Using the remote valve tool, fully open valves 9A and 9B. Open valve -
8A'one-quarter turn. Crack open' valve 8B and~
control degassing by throttling valve 88.
Allow the' system to degas for 5 minutes.
Check that valves 9A and 9B, 8A and 8B are fully open. Close valve 2.
NOTE: OBSERVE THE VACUUM GAUGE. THE VACUUM SHOULD DROP VERY SLOWLY. IF THE DROP IS TOO RAPID, CLOSE VALVE 8B SLIGHTLY.
DROP SHOULD BE 5-10" HG/ MIN. -
5.2 Enalysis of Caseous sample 5.2.1 Hydrogen Use a syringe to draw a 1 cc sample. Use the
'S injection port on the gas partitioner for
! this analysis.
1 I
EPIP 7.3,2 l
. Page 9 5.2.2 Radioactive Noble Gas Use a syringe to draw a 1/2 cc sample and inject this into the flask prepared in Section 1.2.8.*
Allow 30 minutes for thermal mixing. Draw a 1/2 cc sample of this dilution and proceed as normal. -
- Additional dilution should be performed if the contact reading is >l mr/ hour.
NOTE: SEE SECTIONS 7.0 AND 8.0.
5.3 - Collecting the Liquid Sample From the Pressurfzed Sample 5.3.1 Add one drop of 2 M nitric' acid (per 10 ml of sample) to the chloride beaker for pH adjustment. ,
NOTE: IT IS EXTREMELY IMPORTANT TO VERIFY THAT VALVE 2 HAS BEEN CLOSED BEFORE PROCEEDING.
5.3.2 Open valve 3 slowly. Allow the liquid sample to drain into the 50 ml beaker. Direct a slow stream of air through the vent line on valve 3 if necessary to recover the total liquid sample.
5.3.3 Close valves 8A and 8B, 9A and 98, and valve 3.
5.4 Analysis of Liquid Samples 5.4.1 Boron /pH Analysis ,
- a. Transfer a 5 ml sample using the chemical transfer pumo into a 50 ml poly beaker .
containing a stir bar.
NOTE: OBSERVE THE TRANSFER PUMP OPERATION.
WHEN SAMPLE BEGINS TO ENTER THE BEAKER, THE TRANSFER RATE IS 0.5 ML/SECOND OR 10 SEC = 5 ML.
. ~
- b. After transfer is complete, record the pH.
- c. Plug in the magnetic stirrer, add mannitol, and proceed with the boron analysis.
. NOTE: IF THE PRIMARY SYSTEM HAS BEiN BORATED, l ; 5 ML OR MORE OF TITRANT MAY BE NEEDED
, TO REACH AN ENDPOINT.
' l l
EPIP 7.3.2
. Page 10 .
'OTE: AFTER DRILLS AND PRACTICE RUNS, THE N
BORON TITRATOR MUST BE FLUSHED WITH DEIONIZED WATER AND PUT IN DRY LAY- .
UP. ALL ELECTRODES SHOULD BE PLACED #
IN LAYUP SO THEY ARE CONDITIONED FOR IMMEDIATE USE.
5.4.2 Chloride Analysis Transfer the remainder of the sample to the -
second poly beaker containing the chloride electrode. Start the stirring action and record the potential. Use'the calibration curve for the chloride electrode to determine chloride concentration.
NOTE: CHLORIDE SAMPLE MUST BE pH ADJUSTED.
SEE STEP 5.3.1.
NOTE: HIGH LEVELS OF RADIOACTIVE IODINE IN THE COOLANT WILL INTERFERE WITH THE CHLORIDE ANALYSIS. REFER TO THE ATTACHED IODINE /
CHLORIDE CORRECTION CURVE (ATTACHMENT
, ,7.3.2-1) TO MAKE THE PROPER ADJUSTMENT TO THE CHLORIDE ELECTRODE ANALYSIS.
5.4.3 Iodine Analysis and. Gamma Scan Using the spscially prepared 2 cc syringe, with-draw 0.3 cc of the sample from the poly beaker used for the chloride analysis and' inject this sample into a 1000 ml poly bottle containing.
demine'ralized water. Make additional dilutions in the same manner.* Count as normal.
- Additional dilution should be performed until the contact reading is <1 mr/ hour.
NOTE: SEE SECTIONS 7.0 AND 8.0.
5.5 Reporting of Results Cosplete and forward Reactor Coolant Post-Accident Sampling Analysis l Report (EPIP-30). )
l 6.0 SAMPLE RESIDUE l Place all sample residue in the specially prepared lead pig for disposal. z. -
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= .
EPIP 7.3.2
~~ -
Page 11 4
7.0 SAMPLES TAKEN TO KEWAUNEE NUCLEAR PLANT FOR COUNTING
Reference:
Post-accident counting agreement with Wisconsin Public Service, Kewaunee Nuclear Plant.
Kewaunee Nuclear Plant does not utilize the 5 cc glass vial and 1 cc test tube geometries. Therefore, " normal" samples will have to be diluted and placed in one liter poly bottles if they are sent to the Kewaunee Nuclear Plant for analysis.
8.0 . LABELING OF SAMPLES Label all chloride, noble gas, iodine and gamma scan samples with all pertinent information such as: sample number, name of sample, date and time of sampling, sample volume and dilution (s).
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- ziZ AT"'ACHMENT 7.3.2-1 1
CORRECTION FOR REACTOR COOLANT IODINE INTERFERENCE WITH CHLORIDE ELECTRODE RESPONSE
1.0 INTRODUCTION
Chloride as determined by the chloride specific ibn electrode is subject to interference caused by the presence of high levels of other halogens, specifically iodine. The following procedure outlines the method used to estimate the correction for this interference.
2.0 PROCEDURE 2.1 Measure the chloride concentration using the chloride specific ion electrode.
2.2 Perform the iodine analyses as outlined in Section 5.4.3 of this procedure.
2.3 Convert the iodine concentration to ppm using the following conversion factors.
S i
Isotope pCi/cc + ppm Conversion Factor I-130 2.54 X 10 s I-131 3.85 X 10~4 I-132 4.71 X 10~8 I-133 .4.23 X 105 I-134 1.78 X 10~8-I-135 1.38 X 10 s 2.4 Sum th'e concentration, in ppm, of each iodine isotope and use' the attached curve to determine the estimated chloride concentration correction factor.-
3.0 EXAMPLE Reactor Coolant Analysis -
Estimated Isotope Concentration (pci/ccl Conversion Factor Concentration (ppm)
I-131 2.56 X 103 pCi/cc X 3.85 X 104 9.86 X 10~1 I-133 1.45 X 102 pCi/cc X 4.23 X 105 6.13 X 103 I-135 5.65 X 103 pCi/cc X 1.38 X 105 7.80 X 102 ___
TOTAL 1.07 ppm _
Chloride concentration from correction curve (ppm) = 0.42 ppm
\
_j Subtract this value from the chloride concentration determined by the i chloride electrode.
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MINOR I .; . : -
Revision 3 01-28-83 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. The goal of this procedure is to account for all personnel within 30 minutes of the evacuation alarm.
2.0 PRECAUTIONS & 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 INITIALCbNDITIONS ___
-, 3.1 An emergency has been declared as a result of' plant conditions.
-)g 3.2 A limited plant, plant, or an exclusion area evacuation has been ordered requiring the accountability of all personnel in the area evacuated.
3.3 The Shift Supervisor has determined that personnel assembly and accountability is necessary. - ' ,
4.0 PROCEDUEE 4,1 Shift Supervisor
~
4.1 '.1 Determine and communicate as required any special instruc- __
i 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.). -
l Assembly Areas For Evacuation:
Control Room
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- l Emergency Support Center
- Security Building (Extension Building)* and Gatehouse For Limited Plant Evacuation: "
Health Physics Station Cafeteria For Plant Evacuation:
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l Operations Support' Center *, El. 8', TSC Building i Evacuation Assembly Area El. 18.5', TSC Building For Exclusion Area Evacuation:
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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.
Obtain a list of all personnel currently on~the plant. site 4.2.2 from'the appropriate security systems (badge ch'cks, e computer printouts, etc.)
I 4.2.3 As attendanc'e is report'd e from the assembly' areas (see Section 4.1.1), indicate on the list obtained in Step 4.2.2 that the individual has been acccunted 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. '-
i 2 4.2.6 If unable to contact the missing personnel, obtain from the missing person's supervisor the last known or probable i
location and/or job assignment. Enter this data on form
) , EPIP-17. ,
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- c.; 4.2.7 Transmit copies of form EPIP-17 to the Maintenance Super-i visor.
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l 4.2.8 Update form EPIP-17 as changes to resters arrive and as missing' personnel are located.
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EPIP 8.1
- - Page 3 4
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j 4.2.9 Transmit any changes in form EPIP-17 to the Maintenance
- Supervisor honediately.
4.3 Designated Superfisor at the Assembly Area (Includinq
{ Centers for Emergency Operations) 1 4.3.1 Upon arrival at the assembly area, one supervisor should
! compile a roster of all personnel in his group who are j present and accounted for using form EPIP-18,(attached) or -
i an area roster. 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 all personnel present and accounted for by name.
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 Lieutenant
] periodically or as determined necessary by the Security 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 security posts.
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EPIP 11.3 MINOR
] Rgvision 3
~t 01-28-83
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HOSPITAL ASSISTANCE l
l 1.0- INTRODUCTION As outlined in EPIP 11.1, this procedure specifies plans to be used in the event of serious personal injury or illness at Point Beach. Since the possibility exists that treatment of an injured person may be complicated by radioactive contamination, a fully equipped, isolated, and controlled access treatment room, the Nuclear First Aid Room (NFAR), has been provided at Two Rivers Community Hospital in Two Rivers, Wisconsin. This room is equipped with filtered ventilation, sink, decontamination supplies, protective clothing, signs, and other necessary equipment. The Health Physicist and the Company Medical Director are responsible for the training and retraining of hospital and plant personnel involved in offsite medical plans.
l 2.0 PROCEDURE FOR HANDLING SERIOUSLY INJURED PERSONS m, 2.1 General Description (Detailed instructions and responsibilities in
- subsequent subsections) 2.1.1 Injury or Sickness Resulting in Loss of Consciousness or Mobility in the Clean Area control room personnel and the Shift Supervisor will be
- notified of the apparent nature and extent of 'the irijury and
~
location of the injured person. If'an injury occurs in a
" clean area"; i..e., an area free of. contamination,' first ~'
aid should be admini'stered by trained plant personnel and the injured person should be transported for medical treat-ment as necessary.
2.1.2 Injury or Sickness Resulting in Loss of Consciousness or Mobility in the Controlled Area Although an injury in a contaminated area is not likely to ,
involve gross radioactive contamination, special procedures '
are to be used for handling an injured and pot,entially -
contaminated person. The Shift Supervisor is to direct first aid measures and have the injured person moved to the health physics station where, if call out time allows, health physics professionals will take charge. The s .
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l EPIP 11.3 Page 2 j
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circumstances of the injury and the condition of the injured influence action with respect to decontamination of the injured, removal of protective clothing, and transport to the hospital.
In any case where a victim sustains serious injury, medical
. aid takes precedence over decontamination procedures.
Subsequent Action 2.1.3 ,
NOTE: IF THE TSC IS ACTIVATED, THE MAINTENANCE SUPERVISOR SH0blD ASSUME "HE DUTY SHIFT SUPERVISOR RESPONSI-BILITIES FROM BELOW.
~
- a. The Duty Shift Supervisor is to assign an individual to drive the emergency vehicle to transfer the injured person to the hospital. He will inform the driver as to which entrance to use. If the victim is contaminated, the west ehtrance at tne NFAR will be used. Otherwise the regular emergency entrance will be used. An employee trained in first aid-should accompany the injured person in the emergency vehicle.
3 .
- b. The health physics professionals are to be notified and
}
proceed to the Two Rivers Community Hospital to assist in decontamination procedures as required. They should arrive before the victim, if possible, to facilitate organization of the NFAR.
NOTE: IF THERE IS MORE THAN ONE SERIOUS INJURY ,
COMPLICATED BY CONTAMINATION, THE FIRST VICTIM TO ARRIVE AT THE HOSPITAL SHOULD BE DIRECTED TO THE NFAR. SUBSEQUENT VICTIMS SHOULD BE DELIVERED TO THE NORMAL EMERGENC'l ROOM ENTRANCE.
- c. The Shift Supervisor is to notify the Tw'o Rivers Conununity Hospital (see Attachment 11.1-1 to EPIP 11.1) of the nature of the emergency, if contaminated or clean, and expected time of arrival at the hospital.
- d. The Shift Supervisor will notify the Site Manager of the
' injury. -
- e. The Site Manager or his designated alternate should notify theLinjured person's family.
- f. PBNP 3.5.2, " Injuries, Accident Reporting & Industrial l Safety" should be used for documentation and followup of
.] the injury.
EPIP 11.3 -
Page 3 ,
.j w 2.1.4 Responsibility of Hospital Personnel .
Upon being notified that a seriously injured, contaminated person is being transferred, hospitaLpers5'nnel in charge of ecergencies will assure that a physician and sufficient personnel are available, evacuate the NFAR of all persons and materials not deemed necessary and assist in moving the injured person upon arrival. Any person or item leaving the treatment room after the arrival of the contaminated victim will be monitored for radioactive contamination. All items leaving the treatment room will be contained in sealed plastic baijs if found to be contaminated.
2.1.5 Following Emergency Treatment After emergency treatment is completed, the patient will be ,
decontaminated with the assistance of Point Beach Health Physics personnel. The NFAR and all supplies and equipment involved will be thoroughly decontaminated by Point Beach personnel. In addition, surveys will be made in areas nearby to ensure that radioactive contamination has not occurred.
These areas should include the emergency vehicle, the hallway and the hospital entrance. All liquid and solid wastes
,) accumulated as a result of treatment and decontamination will be transferred to the Point Beach Nuclear Plant for disposal in the plant waste disposal facilities.
~ '
2.2 Person Discovering the Injured Person 2.2.1 Immediately notify the Duty Shift Supervisor of the injury and the' location of the patient.
2.2.2 If the patient is in a radiation field great'er than 25 !
Rem / hour, or if serious airborne contamination is present, move the patient to an area with lower radiation dose rates, if possible.
NOTE 1: IN ALL CASES ANY ACTIONS TAKEN SHOULD MINIMIZE.
THE POSSIBILITY OF FURTHER INJURY TO THE PATIENT. IF MOVING THE PATIENT WILL CAUSE EVEN MORE SERIOUS INJURY TO THE PATIENT, THE
. RADIATION EXPOSURE IS OF SECONDARY IMPORTANCE.
GET ADDITIONAL HELP BEFORE MOVING THE PATIENT.
NOTE 2: IF THE PATIENT IS IN AN EXTREMELY HIGH RADIATION FIELD (500 REM / HOUR OR GREATER)
MOVE THE PATIENT IMMEDIATELY, REGARDLESS OF 3
, HIS INJURIES.
2.2.3 ReainwitNthepatient. If first aid qualified, perform emergency first aid and assist in transferring him to the emergency vehicle as directed by the Duty Shift Supervisor.
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..) I1 2.3 Duty Shift Supervisor ' ,
2.3.1 If the injury occurs on day shift, notify the Point Beach Industrial Safety Coordina tor or a Chemistry & Health Physics supervisor of the injury a nd the patient's location.
I 2.3.2 Assign an emergency vehir.le driver from available Operations I personnel or from the Chemistry & Health Physics Group and l dispatch the driver and vehicle to a suitable exit.
NOTE: IF THE PLANT ENERGENC'l VEHICLE IS NOT AVAILABLE, CONTACT THE TWO RIVERS FIRE DEPARTMENT FOR ASSISTANCE. NOTIFY THE PLANT GUARD AND DIRECT THE TWO RIVERS VEHICLE TO THE APPROPRIATE BUILDING EXIT UPON ITS ARRIVAL. SEE ATTACHMENT 11.1-1 FOR TELEPHONE NUMBER. VERIFY APPROPRIATE USE OF PERSONNEL MONITORING DEVICES AS SET FORTH IN SECTION 4.2.
2.3.3 Assure that first aid coverage is provided and instruct the person administering first aid to accompany the patient to the hospital.
l 2.3.4 Notify the Two Rivers Community Hospital and inform them of:
- a. Nature of the injury or illness, if known.
- b. Condition of the patient.
, c. Whether.or no't patient is radioactively contaminated.
- d. ,Means of' transportation and expected time .of arrival..
REFER TO ATTACHMENT 11.1-1 FOR TELEPHONE NUMBER.
2.3.5 If patient 'is radioactively contaminated, notify Health Physics personnel.
2.3.6 Assure that radiation monitoring instruments are placed in the emergency vehicle if the patient is radioactively contami-nated.
NOTE: FIRST CHOICE INSTRUMENTS ARF THE E3ERLINE PIC-SA AND THE EBERLINE RM-14 WITH HP210 PANCAKE PROBE.
2.3.7. Notify the Duty & Call Superintendent.
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2.4 Emergency Vehicle Driver 2.4.1 Upon being assigned, obtain the necessary radiation moni-toring instruments from the Health Physics Station, if required.
2.4.2 Stand by with the vehicle at the designated building exit and assist persons in handling the patient.
2.4.3 After receiving the patient, proceed directly to the Two Rivers Community Hospital.
- a. Noncontaminated patients will be taken to the emergency 1
ambulance entrance, j
- b. Contaminated patients will normally be taken to the s entrance on the west end of the hospital.
! 2.4.4 Enroute to the hospital, call the control room via the
- vehicle radio to establish contact for relaying information on changes in the patient's condition or other pertinent
} information. s i 2.4.5 Upon arrival, assis't in transferring the injured person to j
) the treatment room and if the patient is radioactively contaminated, maintain radiation control and monitoring
] until relieved by Health Physics personnel.
1
] 2.5 Health Physics Personnel 4
2.5.1 Upon notification, proceed to the Two Rivers Community
- Hospital to assist in patient decontamination procedures.
! , ,. Arrive in advance of the emergency vehicle carrying the'
] victim, if possible.
l 2.5.2 Upon arrihal, identify yourselves to hospital personnel and i
provide assistance as requested.
l 2. 5 .,3 Insure that radioactive contamination is not being spread
- into hallways of the hospital or outside the entrance door.
j Maintain restricted areas and post as necessary.
1 l 2.5.4 Monitor hospital personnel (refer to Section 4.3) and i
equipment entering and leaving the restricted area.
i NOTE: POINT BEACH NUCLEAR PLANT PERSONNEL SHOULD ~
REMEMBER THAT THE ATTENDING PHYSICIAN!S ORDERS
. . .s MUST BE OBEYED AND ONLY THE PHYSICIAN IS IN-paq DIRECT CHARGE OF THE SITUATION.
L. / .
2.5.5 Following the emergency treatment, monitor the patient prior to transferring to another area.
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EPIP 11*3' Page 6
.I 2.5.6 Monitor equipment and personnel and decontaminate as required.
2.5.7 Bag all dispesable or radioactively contaminated items and place bags in the plant emergency vehic,le. Note items of -
hospital-owned equipment which may require replacement.
2.5.8 Decontaminate the treatment room and adjoining areas as necessary.
2.6 Health Physicist As scon as possible following the emergency, the Health Physicist will have the treatment room surveyed and insure that decontamination of any hospital facilities used is complete.
2.7 Duty & Call Superintendent 2.7.1 Notify the Manager - Point Beach Nuclear Plant of the
. emergency.
2.7.2 If the Two Rivers Fire _ Department emergency vehicle was used to transport a radioactively contaminated patient, notify
, the Fire Department and request that the vehicle remain at
, i the hospital until plant personnel check for radioactive contamination of the vehicle and/or its equipment.
3.0 PROCEDURE FOR HOSPITAL PERSONNEL The information obtained from the Point Beach Nuclear Plant Duty Shift Supervisor will determine the. actions of hospital personnel.
3.1 Patient Not Contaminated by Radioactive Material These patients will be handled by standard Two Rivers Community Hospital emergency procedures.
3.2 Patient Contaminated by Radioactive Material 3.2.1 The hospital will assure that a qualified physician and sufficient qualified personnel are available to ackninister treatment to the injured person. -
3.2.2 The NFAR will be evacuated of all personnel not involved in the treatment of the incoming patient.
3.2.3 Those hospital personnel needed for treatment or handling of the injured will don protective clothing.
s j 3.2.4 After the victim is in the NFAR, all persons exiting, and
- items being ren:oved from, the NFAR will1e monitored for contamination.
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EPIP-11.3 Page 7
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3.2.5 All contaminated items will be sealed in plast.ic bags and deposited in the NFAR for further disposition.
. 3.2.6 After treatment has been completed, the patient will be transferred to another location. Point Beach Health Physics-personnel will then decontaminate the NFAR and. transfer all contaminated material to Point Beach Nuclear Plant for ultimate disposal. .
NOTE: ALL ITEMS SUCH AS PROTECTIVE CLOTHING, ABSORBENT PAPER, ETC., NECESSARY FOR USE BY HOSPITAL PERSONNEL IN TREATMENT OF CONTAMINATED PATIENTS WILL BE SUPPLIED BY WISCONSIN ELECTRIC POWER COMPANY AND WILL BE KEPT IN THE NFAR.
4.0 MONITORING OF MEDICAL PERSONNEL Assisting personnel will be provided with monitoring devices whenever contamination is involved or whenever such personnel are required on site or within any evacuated area.
4.1 Plant Emergency Vehicle ,
} Use of plant emergency vehicle with plant personnel in attendance e
requires no additional personnel monitoring devices during the transient from the plant to the hospital.
4.2 Two Rivers Fire Department Emergency Vehicle Use of the Two Rivers Fire Department emergencye v'hicle with Fire Department personnel in attendance requires personnel monitoring devices for all non-plant personnel. A self-reading pocket dosimeter and a TLD badge will be issued from the unu' sed TLD supply stored at the south gatehouse. A Visitor TLD Badge Issue Report will be completed as soon as practicable. Upon releasing these personnel,-
their pocket dosimeters will be read and recorded on the Visitor TLD Badge Issue Report. The TLD badges will be retrieved and processed as soon as possible.
4.3 Hospital Personnel Self-reading 'ocket p dosimetry devices and TLD badges will be issued to all hospital personnel assisting in the treatment of an i'n jury which has been further complicated with significant radioactive contamination that could pose as a source of exposure to those per-sonnel. These devices are maintained in the Emergency Vehicle and taken directly to the NFAR at the Two Rivers Community Hospital by
- m. the Health Physics personnel dispatched to the hospital.
- A Visitor's
( 3 TLD Badge Issue Report will be completed as soon as practicable. As j soon as hospital personnel have. completed their treatment of the injured person, the pocket oosimeter will be read and recorded on the Visitor TLD Badge Issue Report and the TLD will be retrieved and
, processed as soon as possible. \
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! 4.4 Additional Facilities i i
If there are requirements to transport an injured employee with j significant radioactive contamination to additional hospital facili-ties or to another hospital, all personnel in the proximity of the injured person will be issued self-reading pocket dosimetry devices and TLD badges. These devices will be retrieved and processed as soon.
j as practicable.
4.5 High Whole Body Exposure Incidents l
For those incidents where personnel may be transferred to the hospital ,
due to a high whole body exposure (greater than 25 R), personnel monitoring for non-plant personnel is not necessary unless the high whole body exposure is complicated by radioactive contamination. In this case, personnel monitoring devices would be issued as outlined in preceding sections.
5.0 ARRANGEMENTS FOR OFFSITE MEDICAL ASSISTANCE FOR SERIOUS INJURIES OR CONTAMINATED INJURIES 5.1 Two Rivers Community Hospital -
3 . ,
) Arrangements have been made with the hospital for treatment of Point
_> Beach Nuclear Plant patients. Hospital personnel have been instructed and trained with regard to potentially radioactive patients and contamination. Hospital personnel are periodically retrained by plant personnel and Company medical representatives. Refer to Attachment 11.1-1 for telephone numbers.
The following health physics supplies are available in the nuclear first. aid room at the two Rivers Community Hospital.
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i NFAR Triage
~
Item Quantity Area l\
Absorbent paper 50 feet --
Bags, plastic, assorted sizes (need garbage can size) 50 50
, Bucket, plastic- 1 1 Decontamination supplies:
Cotton applicators, pkg. 1 1 Decon soap, l qt. bottle 1 'l Hand brush 2 2 Potassium permanganate, 7 cap. pkg. I 1 Sodium bisulfite, 7 cap. pkg. 1 1 Filter paper for smear surveys, pkg. and envelopes 2 2 Gloves:
Cotton pall bearers, pair 8 8 Rubber; pair 8 8 Half-face respirators with particulate filters 4 4 Marking pens, pkg. 1 1
Mops, sponge, with spare sponge 2 2 Protective clothing:
Lab coats - 6 6 Surgeon's cap 6 6
.s . Plastic shoe covers 25 25
') Medical Assistance Plan 1 1
, / Emergency Call List 1 1
Radiation warning signs and tags, assorted 10 10 Radiation warning tape, roll 1 _
1 .
Tape, masking:
1" roll 2 2 l 2" roll 2 2 Victoreen Thyac survey meter with end window, GM probe 1 1 D-cell batteries, box 1 1 4 . 'Masslinn mop 1 1 Barrier tape 1 1 Dosimeters: -
0-500 mrem 10 --
0-2 Rem 5 --
Mini-rad survey instrument 1 1 Scissors 1 1 Tuck tape, rolls 2 2 Miscellaneous. forms CHP-21, Survey Form (Blank) 1 pad *.
CHP-34, Dosimetry Rezero Sheet 5 5 CHP-39, Personnel Contamination Report 5 5 CHP-82, Quarterly Inventory Hospital 5 5 CHP-83, High-Range Dosimeter Issue Sheet 5 5
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Page 10
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5.2 Area Physicians At least two area physicians have taken radiological health instruc-tion courses under full or partial sponsorship of_the Company and are on the Two' Rivers Community Hospital staff.
5.3 Two Rivers Fire Department' Emergency Vehicle Arrangements have been made for the City of Two Rivers emergency vehicle to respond in the event cf injury to persons at the Energy Info'rmation Center or in the event. the plant emergency vehicle is already in use. Refer to Attachment 11.1-1 for telephone numbers.
5.4 Backup Hospital - University of Wisconsin Hospital, Madison Arrangements have been made with the University of Wisconsin Hospital in Madison, Wisconsin, to provide backup services in the event that the services of Two Rivers Community Hospital become temporarily unavailable or that additional. services are required. The University Hospital provides its own training and equipment; Point Beach Nuclear Plant has no maintenance obligations in these areas.
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. POINT BEACH NUCLEAR PIhT
- 4 EMERGENCY PLAN AIRBORNE RADIATION SURVEY RECORD SITE BOUNDARY CONTROL CENTER Q
DATE LOCATION w.
Helpful Information h
b TOTAL SAMPLE TIME (MIN.)
4
- 2.832 x 10 cc/cu. ft.
' AVERAGE FLOW RATE y 1075 cc.in 1 liter gas sample w
$ FLOW CORRECTION FACTOR 2.22 x 106 dpm/pci N Net cpm SAMPLE DATA (2.22 x 106 dpm/pci) (Eff) (Vol/cc) 3 3
g SAMPLE START SAMPLE STOP
- SAMPLE SAMPLE SAMPIER BY o VOLUME o DATE TIME DATE TIME NUMBER TYPE NUMBER (INITIALS) e g) m C
b REMARKS: Plotted COUNTING INSTRUMENT GROSS BETA-GAMMA COUNTING DATA '
USED:
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E.TEGENCY P!.AN SAMPI.Z I::ENTITICAT!!N SUK'/EY MAP EPIP-01 l . . . . . . . _ . _ . _ _ _ . . . . _ _ . . . . . , . . . - - . . . _ _ . . _ . . .. _ _ _ . . _ _ _ . . , _ . _ _ . . , . _ , , _ . , . .%
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EERGDICY PT.Jul SURVEY RECCPD SI1T BOUN"RY CONT 90L CEMTR ,
Type Instrument Date Instrtment Serial No. Survey No.
, Indicate survey location (s) on the attached map.
(A) (8) (C) (D) (E) (F) (G) (H)
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s 1 POINT BEACH NUCLEAR PLANT ,
f3 STATUS REPORT ON PLANT SYSTEMS AND CONTROLS FOR AFFECTED UNIT ,
.- x
- 1. Basic Accident Informa' tion
- a. Unit No.:
- b. . Status Report Date/ Time: /
(Date) (Time-24 Hours)
- c. Emergency Classification Declared: [ Check (/) one]
Unusual Event Site Emergency Alert General Emergency
- d. Time of Reactor Shutdown (if applicable):
(Time-24 Hours)
- e. Time of Radiological Release to Containment (if applicable):
(Time-24 Hours) _ _ .
- f. Time of Radiological Release from Plant (if applicable): ,
'4 (Time-24 Hours)
- 2. Status of Reactivity Control
, Parameters
- a. Control Rod Position (hll33rodbottombistableslit) Yes No
- b. Neutron Flux Decaying- Yes No
- 3. Status of Core Cooling Parameters
- a. Pressurizer Heaters Available Yes No
- b. Th Loop A *F Loop B *F
- c. Tc Loop A *F Loop B *F
- d. Flow Loop A % Loop B %
m EPIP-04 Page 1 of 4 (01-83)
, . , . . . . . , - . . - . . . . - . . . . . . . - . . . . . . .-, .-_....~:.
. . 1
. . 1 Status Report Time:
)
.I
\ 3. Status of Core Cooling- (continued)
, ,s
- e. Incore Thermocouples: Average Temperature *F
- f. Degree of Subcooling Margin: *F i
- 4. Status of Reactor Coolant System Integrity Parameters
- a. Pressurizer or Reactor System Pressure psig a
bl Pressurizer Level %
- c. Primary System Relief Valves Closed Yes No ,
- d. Letdown Flow gpm 1 e. Charging Pump Flow gpm
- 5. Status of Secondarv Systems t
Parameters _.
s.
- a. Steam Generator Pressure "A" Generator psig "B" Generator psig
- b. Steam Generator Level "A" Generator . %, increasing or steady Yes No ,
"B" Generator %,. increasing or steady Yes No -
- c. ' Auxiliary Fiedwater Flow gpm
- 6. Status of containment Integrity Parameters .
- a. Containment Pressure psig
- b. Containment Isolation Valve (Note any not closed)
- c. Containment Spray Pumps Running Yes No
[:-
by EPIP-04 Page 2 of 4 (01-83)
- ,, y _ _ -- - . . _ , _ -
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Status Report Time:.
rm 4 6. Status of Containment Integrity (Continued)
. .]
- d. Containment Recirculation Coolers Running _
1 2 3 4 (Circle one)
- e. NaOH Addition Yes No Time i Level
- 7. Status of Auxiliary Systems Parameters
- a. High Pressure Safety Injection Flow Train A gpm Train B gpm
- b. Refueling Water Storage Tank Level %
- c. Accumulator A Level %
Pressure psig Isolation Valve Open Yes No Accumulator B Level %
Pressure -- psig Isolation Valve Open Yes No
~
') d. RHR Flow FI-928 FI-626 e '. Component Cooling Water Temperature *F Flow gpm
. Number of pumps running Temperature *F
- 8. Status of Meteorology
. Parameters
- a. Wind Direction
- b. Wind Speed. mph -
l
- c. Ambient Temperature *F
- d. Stability Class 09 degrees
.h.; .,
EPIP-04 Page 3 of 4 (01-83)
.___,.7_- ..,.-7._.___. ;_. _ . .__
____,,_y,
3 Status Report Time:
)) 9. Status of Power Supplies s
Parameters s s
' x., \
- a. Offsite Power Available Yes' No
- b. Diesel Generator Running 3DG01 Yes No __
4DG02 Yes No Loaded 3DG01 Yes No 4DG02 Yes No
- c. Onsite Power Available Yes No 4
other Equipment Remarks:
I f
Completed By Time Date
'h i b)
EPIP-04 Page 4 of 4 (01-83)
,7 . .- . - . .-. -
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PLANT AND COMPANY EMERGENCY CALL LIST l N ' '
PBNP PLANT PERSONNEL:
- l. Duty & Call Superintendents Name Plant Ext. Home Phone Time Notified J. J..Zach T
I f.J.Koehler R. E. Link J. C. Reisenbuechler }
G. J. Maxfield .
Duty & Call Beeper No. .
r
- 2. Shift Supervisors
- Name Plant Ext.
Home Phone ' Time Notified L. J. Kamyszek $
l R. D. Mitchell I. L. Bleeker C. M. Gray , ,
o E. Ziller l R. J. Mulheron ;
l-T. W. Garot !
K. J. Draska .
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"5 EPIP-22 Page- 1 of 4
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l . .. 3. Chemistry i .: .
Name Plant Ext. Home Phone Time Notified '
P. J. Skramstad .
T. L. Slack #
1 R. A. Neustadter T. L. Fredrichs !
- 4. Health Physics Name , Plant Ext. Home Phone Time Notified P. Skramstad R. S. Bredvad f L. E. Epstein C. D. Bolle M. D.'Moseman
~
l E. J. Manos 1 I
l '5. Instrument & Control -
I Name Plant Ext.
,, . .Home Phone Time Notified A. J. Pohl I
G. L. Rau E. A. LeClair .
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( 6. Maintenance Name Plant Ext. -Home Phone Time Notified W. J. Herrman
\.
D. A. Magyar M. E. Crouch j R. O. Gerroll i J. O. Schoenberger G. Bernhoft T. R. Branam ,
l E. H. Wellenstein.
- 7. Reactor Engineering i
~
l
- R. L. Harris r i/
-s N. L. Pitterle 1 j .
- 8. Plant Administration and Security ,
Name .
Plant Ext. Home Phone Time Notified' J. J, Zach ,
T. J. Koehler .
R. Krukovski J. D. Mielke F. A. Flentje J. E. Knorr -
- 9. Fire Brigade Members -
Note: Refer to PBNP Fire Protection Manual Call List, Section FEP 2.0.
- '3 EPIP-22 Page 3 of 4 (01-83)
I ,
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-).WEPCOCOMPANYPERSOtINEL: .
~~s,
- 1. Company Administraton and Departments Name Company Ext. Home Phone Time Notified l' ' C. W. Fay, s Duty Emergency Support Manager i
- Wisconsin Electric Power Company f l
Medical Department ,
Nuclear Engineering Section; Office f
/
I Communications Department e WE Accident Prevention
- 2. Nuclear Engineering Section Personnel .
Name Company Ext. Home Phone Time Notified
.s D. K. Porter g
W R. A. Newton \
)
G. D. Frieling E. J. Lipke '
i' :
S..A. Schellin I
. . . C.. W. Krause .
i -
j J. E. Knorr l 3. Insurance Personnel * ~~
J Name Company Ext.
4 Home Phone Time Notified W. J. Dundas, Supt. Insurance &
Claims Div.
. . ~
W. E. Staum, Alternate I
'J. G. Remmel, Alternate '
. 1
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EPIP-22 Page 4 of 4 (01-83)
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. m, OFFSITE AGENCY EMERGENCY CALL LIST FEDERAL AGENCIES:
- 1. United States Nuclear Regulatory Commission Telephone Person Time 4
Name Frequency Number Notified Notified Initials NRC Operations All hours , nad Phana Center or j
- NRC Office of All hours -
Inspection and (Ask for !
Enforcement, Duty Officer) ,
Region III
~
I NRC Resident Inspectors: Plant Ext. Home
- a. .R. L. Hague
- b. B. E. Fitzpatrick
- 2. United States Department of Energv -- -
^^g Telephone -Person , Time ame Frequency Number Notified Notified Initials Chicago Operations Weekdays Center,. Region V (8AM-5PM) .
(Radiological Assistance. Team) All other . .
hours 1 ,
- 3. United States Coast Guard ,. . .
Telephone Person Time Name Frequency ~ Number Notified Notified Initials MSO, Milwaukee USCG, Sturgeon All hours .
Bay USCG,' Two All hours -
Rivers 1
./
EPIP-23 Page 1 of 4 '
(01-83)
~.
_4. United States National Weather Service
/ Telephone Person Time
_ Name Frequency Number Notified Notified Initials NWS, Green Bay All hours NAWAS STATE AGENCIES:
- 1. State of Wisconsin - -
Telephone Person Time Name Frequency Number Notified Notified Initials Wisconsin Dept. of Weekdays -
Health and Social (9AM-5PM)
Services, Section of Radiation Pro-tection Lawrence J. McDonnell, Homa a'---
Chief Section of Radiation '
Protection ,
isconsin' Division 'All hours
--of Emergency /
[
Government Wisconsin State All hours .
- Patrol ,
COUNTY AGENCIES: ,
- l. Manitovoc County .
Telephone Person Time Name Frequency Number Notified Notified Initials Manitowoc County All hours ;
Sheriff, County -
Traffic , ,
~'
- 2. Kewaunee County Telephone Person Time Name -
Frequency Number Notified Notified Initials Kewaunee County All Hours Dispatcher s
t EPIP-23 Page 2 of 4 (01-83)
- o- ,
' PRIVATE AGENCIES: *
. Telephone Person N. Time Name Frequency Number Notified ' Notified Initials Kewaunee Nuclear All hours -
Power Plant
- PRIVATE AGENCIES: (Cont'd)
Telephone Person
- Time Name Frequency Number Notified Notified Initials
. Institute of All hours !
Nuclear Power !
Operations .
American Nuclear .
Insurers All hours '
Wes.tinghouse -
Electric Corp.
Operating Plant Regional Mgr. Office (B. Johnson) Home !
s 1st Alternate Home t
) (C. Sprument) Office .!
2nd Alternate Home !
(C. Rowland) Office Stone & Webster All hours Engineering Corp.
Bechtel Power All hours Corporation -
{, .
i University of office I Wisconsin -
- Milwaukee Seismic Center (D. Willis)
FIRE AND MEDICAL AGENCIES
- 1. Fire Emergency * *
. Telephone Person Time Name Frequency Number Notified Notified Initials l
! Two Creeks Fire All hours -
l Departnent (Emergency ,
, line) .
- 'T r
t i .
i EPIP-23 Page'3 of 4 (01-83) .
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- 2. Medical Assistance -
- j. Telephone Person Time
,, .4ame Frequency Number Notifihd Notified Initials Doctors Clinic, Ltd.
S. Lawrence Kaner, M.D.
Stephen L. Weld, M.D. -
University Hos-pital, Madison
~
Emergency Room All hours _
Frank C. Larson, M.D.
Robert F. Schilling, M.D. i Robert R. Radtke, Ph.D.
-(Health Physicist)
Two' Rivers All hours Emergency i Uehicle l
Community Hos- All hours I pital, Two Rivers '
i N .
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EPIP-23 \ Page 4 of 4 (01-83) \
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, h POINT BEACH NUCLEAR PLANT .
SITE BOUNDARY CONTROL CENTER
, EMERGENCY PLAN INVENTORY CHECKLIST 3 .
J Item No. Item Required On Hand Sampling Equipment and Supplies i 1. AC generator (5,000 watt) 1 i
- 3. Electric high volume air sampler 1
- 4. Poly gas sample bottles 12
- 5. Charcoal cartridges for air sampler, high volume 48
- 6. Charcoal cartridges for air sampler, low volume 50
- 7. Silver zeolite cartridges for air sampler, low volume 5
3
- 8. Filters for air samplers (pkg. of 100) 2
- 9. Gasoline for AC genera' tor (gallons) 2
- 10. Sample tags 50
. 11. Plastic bags 50 l 12. 100' extension cord 2
- 13. Planchets 20 Respiratory Protection Equipment
~
i
- 14. Full-face respirators 2 15 Half-face respirators 2
/ 16. Full-face filter cartridge 12
- 17. Half-face filter cartridge 10 Fire Protection Equipment
- 18. Fire extinguisher, dry chemical 1 >
Radiation' Survey and Monitoring Instrument i 20. Radector.III (.1 mR/hr - 1,000 R/hr) '1 l'
- 21. Victoreen Model 490 Thyac III 1
- 22. PIC-6A survey instrument (1 mR/hr - 1,000 R/hr) 2
- 23. RM3C personnel survey frisker 1
- 24. Johnson Associates, GSM-5, 0-50k cpm, 0-200 mR/hr 1
- , 25. MSC-1 sampler holder for GSM-5 1
, 26. Check sources; 2 - Cs-137 and 1 - Sr-90 3
! 27. Filters for smears (pkg. of 100) 2 l'
- 28. Nuclear Chicago counter scaler 1
- 29. Coin envelopes (box) 1/2 --
j 30. HP-210 probe 2
! 31. SH4 probe holder 1
- 32. Earphones for Thyac-III survey instrument 3
- 33. Side window probe 2
- 34. Cord, BNC-BNC conne~ctor .
2
- 35. Cord, amphenol - BNC connector 2 EPIP-24a (01-83) s --+.se. -.-~~.e. ..-.~w.. .n. m--.e.,r - ~
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6- .
~Page 2 Required On Hand
- , "N
. Personnel Monitoring Equipment N.
- 36. Personnel Thermoluminescent Dosimeters (TLD) 100
- 37. Radiological dosimeters, 0-5 R - - 12
- 38. Radiological dosimeter charger -
2 First Aid and Decontamination Supplies
- 39. .First aid kit 1
- 40. Burn kit 1
- 41. Emergency drinking water tablets (bottles: ,
50 tables per bottle) 5
- 42. Water.(gallons) 20 -
- 43. Decon soap, powder (5 lb.) 1
- 44. Decon soap, liquid (qt.) 1
- 45. Hand brush 4
- 46. Cotton applicators (box) 1 '
- 47. Potassium permanganate (4 oz.) 1
- 48. Sodium bisulfate (1 lb.) 1
- 49. Kim towels (box) 1
- 50. Masselin (pkg.) 1
- 51. "409" cleaner (btl.)
~
2
~
- 52. " Spic'n Span" (box)~ 2
- 53. Masselin mop 1 i 54. Regular sponge map 2
- 55. Rag mop 1
- 56. Wringer 1
- 57. - Large mop bucket 1
- 58. Kimwipes (box) 1
- 59. Bucket, plastic ,2
- 60. - Cotton swabs (packets) 5
- 61. - Gauza sponges, 2" x 2" (100 per pkg.) 1
- 62. Nail brushes 4 .
Radiation Hazard Signs and Supplies .
- 63. Radiation warning tape (roll) 1
- 64. Radiation placards 10
- 65. Radioactive material and radiation hazard signs 10
- 66. Radiation contamination hazard tags 10
- 67. Contamination, high radiation, radioactive material, and radiation area inserts (ea.) 10 .
- 68. Yellow / magenta ribbon (rolls) 8 *-
- 69. Yellow / magenta rope (roll) 1
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EPIP-24a (01-83) .
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- Page 3 Required On hiand .
Communication Equipment and Supplies ,
- 70. Portable 2-way radio KRQ-717 1
- 71. Telephone, plan PBX-extension with outside line capability 1
- 72. WE telephone book 1
- 73. Two Rivers /Manitowoc telephone book 1 Traffic Signs and Equipment *
- 74. Traffic cones for barricades 20
- 75. Traffic lights for barricades 8
- 76. Chains and padlocks for barricades 4
- 77. Traffic flashlight 4
- 78. " Closed Area" placards 6
- 79. Traffic warning light batteries (spare)
Clothing and Toiletry Supplies
- 80. Coveralls 25 *
- 81. Rainwear 6
- 82. Rubber boots -
10
- 83. Shoe covers, plastic 25
/ 84. Overshoes, winter 6
/ 85. Gloves, rubber disposable 6
- 86. Gloves, cotton disposable 6
- 87. Mittens, winter 6
- 88. Towels 12
- 89. Washcloths 12 Stationery anel Miscellaneous Supplies
- 90. . Desk. table and enair. -
1
- 91. Writing paper (pad) 1
- 92. Pens and pencils Assortment
- 93. Tape, masking (rolls)_ 2 94, Tuck tape (rolls) 10
- 95. Logbook ,
1
- 96. Absorbent paper (roll) 1
- 97. Paper cups (bag) 1
- 98. Plastic bags 50
- 99. Scissors 1
- 100. Pocketknife 1
. 101. Screwdrivers (set) 1 l
102. Plastic funnel 4 103. Flashlight 1 104. Batteries (for flashlight and survey instruments) 50 105. Flashlight bulbs 6
') -
l l
\
EPIP-24a \
(01-83) \
l l
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Page 4
,S Required On Hand stationery and Miscellaneous supplies, continued ...
106. Bulbs, incandescent 8
, 107. Electric clock 1 108. Electric heater 5 109. Wet / dry vacuum cleaner 1 110. Metal drum (55-gallon) I 111. Dzl-lene (quart), gasonline stabilizer 1 112. Lead bricks '
12 113. Safety solvent (low) 1 114. Metal funnels 2 115. Pencil sharpener 1 116. Chalk 1 J 117. Bulletin Board I 118. Chalkboard / 1 J- 119. Table (reg.) 1 120. Picnic tables 2 121. Calculator 1 l
Emergency Plan Documents 122. PBNP Emergency Plan --
1 122a. Emergency Plan Implementing Procedures 1
! '1 123. Health Physics Administrative Control Policies
~/ & Procedures Manual 1
) 124. Dose Isopleth/ Map Package 1 125. Personnel Roster 10 l 126. Potassium Iodide Approval, Use List 1 127. DOE, Region V, Radiological Assistance Handbook 1 128. State of Wis. Peacetime Radiological Response Plan 1 EPIP Forms 129. EPIP-01, Emergency Plan Airborne Radiation Survey 5' 130. EPIP-02, Emergency Plan Survey Record -
5 131. EPIP-03, Dose Factor Calculation Sheet 5 .
132. EPIP-04, Status Report on Plant Systems and controls 5 133. EPIP-05, Worksheet for Status Report on RMS for Unit 5 134. EPIP-06, Worksheet for Status Report on RMS for Plant 5
- 135. EPIP-07, X/d Determination 5 136. EPIP-08, Estimated Whole Body and Thyroid Projected 5 137. EPIP-09, Estimated Whole Body calculation Worksheet 5 i 138. EPIP-10, Estimated Ground Deposition Cal'culation 5 --
139. EPIP-17, List of Missing Personnel 5 i
141. Xe-133 Equivalent Release Rate, Worksheet No.1 5 141a. EPIP-36, Master Dose Logsheet ---
- 5
^
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a%
,y EPIP-24a (01-83)
__.,~__..-__...._m_.__,___ . _ . ..-.. _ _ _. _ _ _. ,
Page 5 Required On Hand -
~ ~
EPIP Procedures -
142. EPIP 1.4, Radiological Dose Evaluation 5 143. EPIP 1.5, Protective Action Evaluation 5 _-
144. EPIP 7.1.1, Chemistry & Health Physics Personnel Notification and Initial Response when Chemistry &
Health Physics Personnel are On-Site 5 145. EPIP 7.2.1, Activation of Health Physics Facilities at Site Boundary control Center 5 146. EPIP 7.2.2, Activation of Health Physics Facilities at Operations Support Center 5 147. EPIP 7.2.3, Activation of Health Physics Facilities at Technical Support Center 5 CHP Forms l l
148. CHP-02, Iodine Airborne Survey (pad of 50) 1 149. CHP-21, Miscellaneous Survey ,(pad of 50) 1 150. CHP-31, Radiation Work Permit (pad of 50) 1 151. CHP-34, Dosimeter Rezero (pad of 50) 1 152. CHP-37, Irregular or Offscale Dosimeter Report -
(pad of 50) 1
.' 153. CHP-22, Air Particulate Sample (pad of 50) 1 154. CHP-25, Counting Log Sheet (pad of 50) 1
_/ 155. CHP-33b, Visitors Monitored per 10 CFR 20 (pad of 50) 1 156. CHP-33c, Visitor Personnel Monitoring Record (pad of 50) - -
1 -
157'. CHP-35, Dosimeter Summary Sheet (pad of 50) 1 158. CHP-38, Lost or Damaged TLD Report (pad of 50) 1 159. CHP-39, Personnel Contamination Report (pad.of 50) 1 160. CHP-40, Visitor TLD Badge Issue Report (pad of 50) 1 161. CHP-44, Timekeeping Log - High Radiation Work -
Location (pad of 50) 1 162. , CHP-56, Personal Bioassay Evaluation (pad of 50) 1 163. CHP-106, Occupational External Radiation Exposure History (pad of 50) 1 Emergency Plan Sampling Kits 164. Emergency Plan Sampling Kits - Each kit contains the following: 2
- 1. Battery powered air sampler 1
- 2. Scott cartridge holder 1
- 3. Silver Zeolite cartridge holder 1
- 4. Stop watch with batteries 1
- 5. Air Particulate filters (env.) 1
- 6. Silver Zeolite cartridge / 5 N;g7- ) . 7. Scott charcoal cartridge C -' 5 a 8. PIC-6A survey meter 1
- 9. Water filled gas sample bottle (1 liter) 2 EPIP-24a (01-83) .
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~
."'- Required On Hand i
~'
- 10. Liquid sample cubitainers (1 liter) . 2
- 11. Scissors 1 pair
- 12. Plastic suit 2 sets
- 13. Gloves (surgeons) 6 pair
- 14. Dosimeters (0 - 5,000 mR) 2
- 15. Dosimeter charger 1
- 16. Plastic Bags 12 x 18 inch size 6 5x8 inch size 6 3x5 inch size 12
- 17. Flashlight with spare bulb and batteries 1
- 18. Smears (100 each/ box) 2
- 19. Tuck Tape (roll) 1
- 20. Sharpie, Flair pen, grease pencil and pencil 4
- 21. Sample ID tags (pad) 1
- 22. Sampling Procedures EPIP 7.3.1 Airborne Sampling and Direct Dose Rate 5 ea Survey Guidelines
. EPIP 7.3.1 Atmospheric Radioactive Iodine Sample 5 ea Attachment Collection and Counting
- 23. Sampling Forms EPIP-01 Airborne Radiation Survey Record 5 ea
~S EPIP-02 Emergency Plan Survey Record 5 ea
' Sample Identification Survey Map 5 ea 2 and 5 Mile Sample Identification Survey Map 5 ea
- 24. CHP-34 Rezero Sheet 5 ea By Date
~
Reviewed By Date (Health Physics Supervisor) l
. ~5 -
.. ' )
EPIP-24a (01-83)
/
POINT BEACH NUCLEAF. 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
,s 3. RM-3C S-23 cpm cpm,
)
- 4. PIC-6A Cs-11 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-ll mR/hr mR/hr
- 9. HPI-10.10 -
Cs-ll mR/hr mR/hr
- 10. Nuclear Chicago S-23 cpm cpm
~
AIR SAMPLERS ,
Item Satisfactory No. M. Functional Test ..
NOTE: SOURCE CHECK CRITERIA
- 1. High Volume TO BE ENTERED FROM CURRENT CALIBRATION STICKER ON EACH 4
- 2. Battery (12 V DC) UNIT. RESULTS MUST BE ~
WITHIN 120% OF THIS VALUE. -
-. g a <h l s' j EPIP-25b Page 1 of 4 l (01-83)
_ . _ . m._.. _ . . . _ . - . _. ._ _ . _ . _ . _ . _ . . _ _ _
7 _ . . _ . , _ . . _ _
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F . .
. OPERATIONS SUPPORT CENTER
.+ INSTRUMENTATION Source l Item Type of Serial Check Check l 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 Scurce Criteria- Criteria
- a. AMS-2 cpm cpm b: RM-14 -
cpm cpm Use check source CS-6.
l r
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EPIP-25b Page 2 of 4 (01-83) i .
a EMERGENCY SUPPORT CENTER
.)
.) INSTRUMENTATION Check Check Item Type of Serial Check Source Source A
N Equipment Number Source Criteria Results
- 1. Rad Owl II Cs-5 mR/hr mR/hr
- 2. Vamp Area Monitor Cs-5 mR/hr mR/hr AIR SAMPLERS Item Satisfactory l No. Description Functional Test 4
SOUTH GATE INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. VAMP Monitor Cs-6 mR/hr mR/hr AIR SAMPLERS-Item Type of Satisfactory 1 -
No. Equipment Functional Test
- 1. Low Volume CONTROL ROOM INSTRUMENTATION Check Source Item Type of Serial Source Check No. Equipment Number Used Criteria Results
- 1. Radector III Cs-3 mR/hr mR/hr s%
4\.i).
EPIP-25b , Page 3 of 4 (01-83)
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FIRST AID ROOM ,
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-/ INSTRUMENTATION ~w. .
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 -
l .
Reviewed By -
Date Health Physics Supervisor l
EPIP-25b Page 4 of 4 (01-83) .
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1 POINT BEACH UUCLEAR PLANT
- f. QUARTERLY EMERGENCY PLAN CHECKLIST u '
'. DATE N
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 RESPIRATORY EQUIPMENT Item No. M Serial No. Inspection
- 1. Full-face
- 2. Full-face
- 3. Full-face '
~
... 4. Full-face
) .
../ COMMUNICATIONS Portable Radio KRQ-717 Functional check with control room WARNING LIGHTS, TRAFFIC Traffic Warning Lights 'All traffic warning -
lights functioning AC GENERATOR (Gasoline Powered)
Functional Test
.?
i m:
EPIP-25c Page 1 of 4 (01-83)
L _ _. 7 . . ~ _ . _ . . . - - _ _
.m- . - - - -
7--,- - - -
, l DRY CELL BATTERY REPLACEMENT
g
. NOTE: If alkaline batteries are used, battery changeout is required annually
'j rather than quarterly. If carbon or mercury batteries are used, a quarterly 5-minute test shall be completed to verify operability.
Item Batterv Changed /
No. Type of Equipment Tyge Quantity Tested Date Due
- 1. Traffic Warning Light
- 2. Survey /Frisker Instruments
- 3. Flashlights
- 4. Portable Radio
- 5. Stop Watch
- 6. Dosimeter Ch'arger CO- (ROL ROOM RESPIRATORY EQUIPMENT Item Type of Serial Functional s No. Equipment Number Inspection Test
_.' 1. Bio-Pak
- 2. Bio-Pak
- 3. MSA-SCBA
- 4. MSA-SCBA
. 5. Supplied Air Mask l 6. Supplied Air Mask
- 7. Supplied Air Mask
- 8. Supplied Air Mask-
- 9. Supplied Air Mask
- 10. Supplied Air Mask _
- 11. Supplied Air Mask Hose
- 12. Supplied Air Mask Hose 13.- Supplied Air Mask Hose
- 14. Supplied Air Mask Hose i 15. Supplied Air Mask Hose
- 16. Supplied Air Mask Hose
- 17. Supplied Air Valve
- 18. Supplied Air Valve '~'
l 19. Supplied Air Valve
- 20. Supplied Air Valve
- 21. Supplied Air Valve
- 22. Supplied Air Valve
- $3
- EPIP-25c Page 2 of 4 (01-83) l , - . , ,.L . . . .-
e ,.
N
' Controf Room Respiratory Equipment, continued ... -
~ Item Type of Serial -
) No. Equipment Number Inspection
_) -
- 23. Supplied Air Hose
- 24. Supplied Air Hose
- 25. Supplied Air Hose Supplied Air Hose 26.
- 27. Supplied Air Hose
- 28. Supplied Air Hose
- 29. Spare Mask
- 30. Spare Mask '
- 31. Spare Mask
- 32. Spare Mask
- 33. Bio-Pak
- 34. Bio-Pak
- 35. Bio-Pak
- 36. Bio-Pak TECHNICAL SUPPORT CENTER /0PERATIONS SUPPORT CENTER RESPIRATORY EQUIPMENT Item Type of Serial Serial
- No. Equipment Number In?pection Number Inspection
- 1. . Clear-Vue 1. 4.
'i, 2. 5.
- 3. 6.
- 2. Ultra-Vue 1. 4.
- 2. 5.
- 3. 6.
- 3. Bio-Pak 1. 6.
- 2. 7.
- 3. 8.
- 4. 9.
- 5. 10.
COMMUNICATIONS Portable Radio KRQ-717 Functional Test with (1 unit) Control Room "
.GATEHOUSE COMMUNICATIONS -
Portable Radio KRQ-717 Functional Test with (1 unit) Control Room
]
- ) n EPIP-25c Page 3 of 4 '
(01-83)
-.3 .-- _ ,- - - - .. ; - . - 7 - ---. , - - - -. -
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EMERGENCY SUPPORT CENTER ,
k ,
i
)-r y RESPIRATORY-EQUIPMENT Item Type of y Serial \ Serial No. Equipment .,'
N Number Inspection Number Inspection
- 1. Clear-Vue 1. 4.
- 2. 5. -
e
- 3. _
6.
- 2. Ultra-Vue 1. 4. -
- 2. 5.
- 3. 6.
i f
REMARKS:
NOTE: Include maintenance request numbers for all items requiring repairs.
Inventory By. - Date Reviewed By Date .
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EPIP-25c '
Page 4 of 4 ;-
(01-83)
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POINT BEACH NUCLEAR PLANT MONTHLY COMMUNICATIONS TEST ,
I Date/ Time Initials NAWAS Warning Center 2 NAWAS Manitowoc County i
NAWAS Kewaunee County PBX System l
General Telephone Lines Gai-tronics County Sheriff FM
,s
) ENS - CR ENS - TSC ENS - ESC NOTE: Precede and follow any test conununication with the s wo'rds "This a test."
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EPIP-27 -
J (01-83) '
. m -
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POINT BEACH NUCLEAR PLANT -
^
CALCULATION OF Xe-133 EQUIVALENT RELEASE RATES R sponsibility - Shift Supervisor or designee.
Frequency - During classification only. ,
1.0 LOW RANGE OPERATIONAL VENT STACK READINGS
- l Flow Rate Meter Reading Conversion Factor Release Rate (CFM) (CPM) Curies (Curies /sec) sec-cpm Auxiliary Building 614,00 x 5.8x10[98 =
L Drumming Area 43100 x 1.2 x 10 =
Unit 1 Containment Purge 12500 x 2.1x10[6 =
.1 25000 x 4.2 x 10 6 =
1 Unit 2 Containment Purge 12500 x 2.1 x 10 ~6 =
4.2 x 10 ~8
~ '
25000 x = -
Gas Stripper Building 13000 x =
Combined Air Ejector 25 Ix 7.8 x 10,9 =
~
l 2.0 EBERLINE RMS-11 VENT STACK. READOUTS .
6
! Flow Rate Meter Reading Conversion Factor Release Rate f (CFM) (R/hr) Curies - Hrs (Curies /sec) sec-R
- n
. Auxiliary Building 61400 x 3.0 x 103 =
4 Drumming Area 43100 x 2.2 x 103 =
l Unit 1 Containment Purge 12500 x 1.6 x 104 =
j 25000 x 3.2 x 104 =
i Unit 2 Containment Purge 12500 x 1.6 x 104 =
! 43000 x 3.2 x 104 = 7 Gas Stripper Building r3000 x 6.2 x 102 =
Combined Air Ejector- 25 x 3.6 =
1 EPIP-34 (01-83)
i o
~
I 1 %
Q.0> ,
--) ,e 3.0 PLANT EFFLUENT VENT STACK CONTACT READINGS .
Flow Rate Meter Reading Conversion Factor Release Rate .
(CFM) (R/hr)
- Curies-hr (Curies /sec) sec-R .
, Auxiliary Building 61400 . x 3.0 x 102 =
! Drumming Arca 43100 x 2.3 x 10 2 = -
2 Unit 1 Containment 12500 x 8.0 x 101 =
I 25000 x 1.6 x 102 =
f Unit 2 Containment 12500 x 8.0 x 101 = ,
i 25000 x 1.6 x 102 =
Gas Stripper Building 13000 . x 8.0 x 104 =
- Combined Air Ejector 25 x 1.6 x 102 =
Estimated Steam x Specific x Conversion x Meter X Conversion Release Rate Release ~ Volume Factor Reading Factor =
Ci/sec 3 hr-cm3
(.lb/hr)
(ft /lba) (R/hr) Curies-hr
! sec-ft3 ca"-R ,
Main Steam Header x x 7.86 x x 8.0 x 101 =
Assume 1000 psia steam which will give a' conservative specific volume. At 3
1000 psia specific volume = .446 ft /lbm.
Steam generator safety valve rating is 8.33 x 105 lb/hr per valve. Atmospheric relief valve capacity is 3.3 X 104 lb/hr with both valves open.
)
i EPIP-34 .
(01-83) i -
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4.0 ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATES
. Xe-133 Vent Equivalent Release Rate (Curies /sec)
Auxiliary Building Druauning Area Unit 1 Contaisunent Purge Unit 2 Contaitunent Purge Gas Stripper Building Combined Air Ejector Decay Duct .
Main Steam Header TOTAL -
Completed By Date ! Time
~
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EPIP-34 (01-83) 2 .
.