ML20079S195

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP 1.3 Re Estimation of Source Term & EPIP 1.4 Re Radiological Dose Evaluation

ML20079S195
Person / Time
Site:	Point Beach
Issue date:	05/27/1983
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20079S183	List: ML20079S188 ML20079S195
References
PROC-830527-01, NUDOCS 8307110348
Download: ML20079S195 (64)

Text

i 6 e 05-27-83 TABLE OF CONTENTS Revision Date 1.0 CLASSIFICATION & ASSESSMENT 1.1 Initial Classification . . . . . . . . . . . 4 01-28-83 1.2 Plant Status ................ 0 03-31-81 1.3 Estimation of Source Term . . . . . . . . . . 5 05-27-83 1.4 Radiological Dose Evaluation . . . . . . . . 7 05-27-83 1.5 Protective Action Evaluation . . . . . . . . 4 09-10-82 1.6 Radioiodine 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 - Immediate 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 3 05-27-83 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actions . . . . . . . . . . 2 09-10-82 3.2 Alert - Plant & Company Personnel Notification ............... 1 07-01-81 3.3 Alert - Off-Site Agency Notification . . . . 2 05-27-83 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES 4.1 Site Emergency - Immediate 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 PROCFDURES 5.1 General Emergency - Immediate Actions . . . . 2 09-10-82 5.2 General Emergency - Plant & Company Personnel Nctification . . . . . . . . . . 1 07-01-81 5.3 General Emergency - Off-Site Agency

, Notification ............... 1 09-10-82 6.0 EVACUATION 6.1 Liz.ited Plant Evacuation . . . . . . . . . . 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 . . . . . . . . . . . . 1 05-27-83 8307110348 830624 PDR ADDCK 05000266

! F PER.

e a Page 2 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 04-30-82 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 5/oup Personnel . . . . . . . . 1 05-15-81 7.2 Health Physics Facility Activation 7.2.1 Activation of HP Facilities at Site Boundary Control Center . . 2 03-17-82 7.2.2 Activation of HP Facilities at . . .

Operations Support Center . . . . 2 05-27-83 7.2.3 DELETED 7.2.4 Health Physics Communications . . . 2 05-27-83 7.2.5 Control & Use of Vehicles . . . . . 1 03-17-82 7.3 Radiological Surveys 7.3.1 Airborne Sanpling & Direct Dose Rate Survey Guidelines . . . . . . 3 03-17-82 7.3.2 Post-Accident ~3ampling & 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 i .

Health Physics Emergency Plan Equipment . . . . . . . . . . . . 7 05-27-83 l 7.4.2 Emergency Plan Equipment Routine Check, Maintenance & Calibration l Instructions . . . . . . . . . . . 5 05-27-83 l 7.4.3 Use of Baird Model 530 Single l Channel Iodine Spectrometer to Determine Airborne Iodine Activities . . . . . . . . . . . . 1 05-15-81

e a Page 3 Revision Date {

l 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 i

9.1 Security . ... . . ... . . ... . . . . 0 03-31-81 10.0 Firefighting .. . . . ... . .. . . . .. 0 03-31-81 11.0 FIRST AID & MEDICAL CARE 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 12.1 Reentry Procedures for Emergency Operations 1 03-17-82 12.2 Personnel Exposure & Search & Rescue 4

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 C'risis 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 15.4 Emergency Preparedness Review . ... .... 0 09-10-82 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Section Notification &

Response .. .. . .... .... . . .. 3 09-04-81

. e a 05-27-83 TABLE OF EPIP FORMS EPIP EPIP Form Title Procedure 01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (01-83) 7.3.1 02 Emergency Plan Survey Record Site Boundary Control Center (01-83) 7.3.1

, 03 Dose Factor Calculations for Specific Noble Gas Analysis l 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 for Unit (03-81) 1.2 06 Worksheet for Status Report on Radiation Monitoring System for Plant (03-81) 1.2 07 For X/Q Determination (09-82) 1.4 08 Estimated Whole Body & Thyroid Projected Doses (09-82) 1.4 09 Estimated Whole Body Dose Calculation Worksheet for '~ -

4 Specific Noble Gas Releases (09-82) 1.4 10 Estimated Ground Deposition Calculation Worksheet for Particulate Radionuclide Releases (09-82) 1.4 10a Estimated Population Dose (09-82) , 1. 8 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 '

13 Status Update Form (09-82) 2.3, 3.3 4.3, 5.3

, 14 Unused 15 Unused 16 Event Data Checklist (03-81) 5.3 17 Accounting Short Form (04-82) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Drill / Exercise Scenario (03-81) 15.3 20 Drill / Observation Sheet (03-81) 15.3 21 Drill / Exercise Evaluation Report (03-81) 15.3 l 22 Plant & Company Emergency Call List (01-83) Call List Tab 23 offsite Agency Emergency Call List (01-83) Call List Tab 24a Site Boundary Control Center Emergency Plan Inventory l Checklist (01-83) .7.4.1 24b TSC, ESC, South Gate & OSC Emergency Plan Inventory Checklist (09-82) 7.4.1 l 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 (06-82) 7.4.1 24e Emergency Vehicle Inventory Checklist (04-82) 7.4.1 24f Emergency Plan First Aid Kit Invectory Checklist (09-82) 7.4.1 J

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8 e Page 2 EPIP EPIP Forms Title Procedure 24g Emergency Plan Burn Kit Inventory (09-82) 7.4.1 24h Emergency Plan First Aid Room Inventory (09-82) 7.4.1 241 Emergency Plan Stretcher Inventory (09-82) 7.4.1 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 27 Monthly Communications Test (01-83) 14.1 28 Emergency Plan Instrument Calibration Schedule (06-82) 7.4.2 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 31 Containment Atmosphere Post-Accident Sampling Analysis Report (12-81) 7.3.3 32 Search & Rescue and Emergency Operations' Checklist (04-82) 12.2  ;

33 Estimation of Core Damage (09-82) 1.7 34 Calculation of Xe-133 Equivalent Release Rates (05-83) 1.8 35 . Dose Calculations (09-82) 1.8 36 Unused 37 Medical Assistance call List (09-82) 11.1 O

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POINT BEACH NUCLEAR PLANT 1

CALCULATION OF Xe-133 EQUIVALENT RELEASE RATES RMponsibility - Shift Supervisor or designee.

Frequency - During classification only.

1.0 LOW RANGE OPERATIONAL VENT STACK READINGS Flow Rate Meter Reading Conversion Factor Release Rate (CFM) (CPH) Curies (Curies /sec) sec-cpm Auxiliary Building 61400 x 5.8 x 10 ~9 =

Drumming Area 43100 x 1.3 x 108 =

Gas Stripper Building 13000 x 2.0x10[6 =

Combined Air Ejector 25 x 8.0 x 10 9 =

2.0 EBERLINE RMS-11 VENT STACK READOUTS - -

Flow Rate Meter Reading Conversion Factor Release Rate (CFH) (R/hr) Curies - Hrs (Curies /sec) sec-R Auxiliary Building 61400 x 3.0 x 103 =

Drumming Area 43100 x 2.1 x 103 =

Gas Stripper Building 13000 x 6.2 x 102 =

Combined Air Ejector 25 x 3.4 =

9 EPIP-34 (05-83)

.s 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 Area 43100 x 2.3 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 (Ib/hr) (ft 3/lbm) hr-cm3 (R/hr) Curies-hr sec-ft3 cm 3 -R Main Steam !!eader x x 7.86 x x 8.0 x 103 =

Assume 1000 psia steam which will give a conservative specific volume. At 1000 psia specific volume = .446 ft 3/lbm. .

Steam generator safety valve rating is 8.33 x 105 lb/hr per valve. Atmospheric reliet valve capacity is 3.3 X 104 lb/hr with both valves open.

9 EPIP-34 (05-83)

t 4.0 ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATES ,

Xe-133 Vent Equivalent Release Rate (Curies /sec)

Auxiliary Building Drumming Area Gas Stripper Building Combined Air Ejector Decay Duct Main Steam Header TOTAL Completed By Date Time 9

EPIP-34 (05-83)

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j EPIP 1.3

_s . MINOR

/ Revision 5 1

)

05-27-83 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) 1.3 Gas Stripper Building Vent (GSBVNT) 1.4 Combined Air Ejector Decay Duct (CAE) 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 loss of r'eactor coolant ' system integrity has occurred, some or all of the following would be present:

3.1.1 The letdown radiation monitor (R9) may be unusually high or offscale.

3.1.2 The containment radiation monitors (R11 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.

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 system readouts and radio-logical hazards must be completed prior to any attempt to enter the a miliary 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 completed.

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 the radiation monitoring systems.

,b 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. I 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- i forming Section 5.2 of this procedure if required. I NOTE

IF STEP 5.1.3 NEEDS TO BE COMPLETED BECAUSE EBERLINE RMS II DATA IS NOT AVAILABLE, OR IF A STEAM GENIRATOR 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 l

THIS PROCEDURE AFTER APPROPRIATE MEASUREMENTS HAVE

. BEEN TAKEN IN SECTION 5.2.

._, .y . . - , . - -

EPIP 1.3 Page 3 5.1.4 Perform Section 5.3 of this procedure to determine the gross Xe-133 equivalent release rate estimate.

5.2 Direct 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 Step 5.2.1 to the stack

/ and record the survey instrument reading in contact with the

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Q stack in the columns provided on Worksheeti 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 SIDES FACING THE MAIN STEAM LINE AND i

THE CONTAINMENT.

i i 5.3 Chemistry / Health Physics Supervisor or Designated Alternate  :

a

5.3.1 Choose the appropriate vent stack readouts in Part A, B, or 1 C of Worksheet No. I to convert readings to a Xe-133 equiva- l lent release rate. That is if the low range monitors go l offscale, use the high range monitors. Conversely, if the  ;

normal monitors are onscale, use the normal monitors, or if i both normal and high range monitors are offscale or inoper-able, use the vent stack contact readings. '

5.3.2 Use the appropriate conversion factors for each of the plant effluent vent to convert the chosen vent stack readout, (cpm or R/ hour) and flow rate, from Step 5.3.1 to an Xe-133 equivalent release rate in Curies /second and record the value on Worksheet No.1, Part F, Estimate of Gross Xe-133 Equivalent Release Rate. Enter the appropriate word "offscale,"

l EPIP 1.3 l

. Page 4 "not monitored," or " inoperable" for the cases where the plant effluent vent was not monitored, offscale, or inoperable. l NOTE: THE FOLLOWING QUALIFYING NOTES MUST BE RECOGNIZED.

1. If the actual flow rate is different than the assumed conversion factor 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 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 header in ihm/ hour of steam being dumped to the environ-ment and the specific volume (v) of the steam.

2._,_

~ At 1000 psia, spe~cific volume is 0.446 ft.3/lbm.

At 500 psia, specific volume is 0.928 ft.3/lbm.

ee r lbm/hrxvfb; x 7.86 g , e_

b. Convert contact reading obtained at the main steam header to pCi/.c,c 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 rate (Xe-133 equivalent) from the main steam header.

1 Flow Rate Concentration , Main Steam Header (cc/sec.) 3 (pCi/cc) Release Rate 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, Part F, to determine the gross Xe-133 equivalent release rate.

h m - __.-__ __.__ -_-

EPIP 1.3

. Page 5 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 TO THE ABOVE IF THE RELEASE IS FROM AN UNMONITORED RELEASE PATH.

5.3.3 Report the calculated gross Xe-133 equivalent release rate to the Shift Supervisor and the Technical Support Manager.

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WORKSHEET NO. 1 Xe-133 EQUIVALENT RELEASE RATE A. LOW RANGE OPERATIONAL VENT STACK READOUTS Conversion Xe-133 Equiv.

Meter Reading Flow Rate Factor Release Rate Vent (cpm) (cfm) Ci/sec+ cpm Ci/sec

_9 Auxiliary Building R14 61400 5.8 x 10 8

Drumming Area R21 43100 1.3 x 10 U1 Containment Purge 12500 2.0 x 10 s 25000 4.2 z'108 U2 Containment Purge 12500 2.1 x 10 6 25000 4.2 x 108

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g ,y Gas Stripper Building GW-112 13000 2.0 x 10 Combined Air Ejector _g Decay CR-9 25 8.0 x 10 B. EBERLINE 5tMS - II VENT STACK READ 0UTS i

NOTE: THESE READINGS ARE ALSO AVAILABLE ON THE TECHNICAL SUPPORT CENTER DATA LOGGER. ATTACHMENTS 1.3-1, 2, 3.

Conversion Xe-133 Equiv.

Meter Reading Flow Rate Factor Release Rate Vent (R/ hour) (cfm) Ci/sec R/hr Ci/sec 3

Auxiliary Building Ch. #1 61400 3.0 x 10 Drumming Area Ch_._ #2 43100 2.1 x 103 ,

l U1 Containment Purge 12500 1.6 x 104 25000 3.2 x 104 U2 Containment Purge 12500 1.6 x 104 25000 3.2 x 104 2

Gas Stripper Building Ch. #6 13000 6.2 x 10 Combined Air Ejector l Decay Ch. #5 ,

25 3.4

. 1 C. PLANT EFFLUENT VENT STACK CONTACT READINGS i

Conversion Xe-133 Equiv.

Meter Reading Flow Rate Factor Release Rate Vent R/hr) (cfm) Ci/sec+R/hr Ci/sec Auxiliary Building 61400 300 2

Drumming Area 43100 2.3 x 10 U1 Containment Purge 12500 8.0 x 10 1 25000 1.6 x 102 U2 Containment Purge 12500 8.0 x 101 25000 1.6 x 102 4

Gas Stripper Building 13000

• 8 x 10 2

Combined Air Ejector Decay 25 1.6 x 10 5

Main Steam Header (See 8 x 10 See Section E Sect. E)

D. ACTUAL VERSUS CONVERSION CURVE FLOW RATE RATIO Actual Flow Rate x' Release Rate Value = Adjusted Releast Rate Assumed Flow Rate

( )x =

E. STEAM HEADER CONTACT READING CALCULATION

1. Iba/hr .x specific volume ft 3 /lba x 7.86 cc hr/ft 3 see NOTE: At 1000 psia specific volume =

.446 ft33/lba At 500 psia specific volume =

.928 ft /lba lbe/hr x ft 8/lba x 7.86 cc hr/ft 3sec . _ _

=

cc/see

2. Contact reading from Section C:

R/hr = pCi/cc , _

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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)

8. ESTIMATE OF GROSS Xe-133 EQUIVALEN'" RELEASE RATE Xe-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) 9.R,

7. Grab Sample Results = Ci/sec.

I Completed By Time

' Date i

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ATTACHMENT 1.3-1

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'6 DRUMMING AREA VENT STACK RMS-II CH #2 &

COMBINED AIR EJECTOR DISCHARGE RMS-II CH #5 VOLTAGE TO R/HR CONVERSION TABLE RANGE 1 to 10" R/HR Volts Units R/hr 0 0.001 0.1 0.00135 0.2 0.001847 0.3 0.002511 ,

0.4 0.003414 0.5 . 0.004641 0.6 0.006309 0.7 0.008576 0.8 0.011659 0.9 0.015848

. 1.0 0.021544

. 1.1 0.029286 1.2 0.039810 1.3 0.054116 1.4 0.073564 1.5 0.100 -

1.6' O.135935 1.7 0.184784 1.8 0.251188 1.9 0.341454 2.0 0.464158 2.1 0.630957 2.2 0.857695 2.3 1.165914 2.4 1.584893 2.5 2.154434 2.6 2.928644 2.7 3.981071 2.8 5.411695 "249 =I 7.356422 3.0 10.0 i

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ATIACHMENT 1.3-2 I

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UNIT 1 RMS-II CH #3 & UNIT 2 RMS-II CH #4 CONTAINMENT PURGE STACKS VOLTAGE TO R/HR CCNVERSION TABLES RANGE IO ' TC 10' R/HR Volts Units - R/HR O. 0.1 '

0.1 .135 O.2 .184 0.3 .251 0.4 .341 0.5 , .464 ,

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0.6 .630 -

0.7 .857 -

0.8 1.165 0.9 1.584

% 'l. 2.154 1.1 2.928 1.2 3.981 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 2.6 541.169

. 2.9 735.642

3. 1000.

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• l ATTACHMENT 1.3-3 AUXILIARY BUILDING VENT STACK RMS-II CH #1 &

• GAS STRIPPER BUILDING VENT STACK RMS-II CH #2 1 J

I VOLTAGE TO R/HR CONVERSION TABLE RANGE 10-' TO 10' R/HR ,

Volts Units - R/HR O. 0.01 0.1 .013 0.2 .018 0.3 .025 0.4 .034 0.5 .046 -

0.6 .063 0.7 .085 0.8 .116 0.9 .158

1. .215 1.1 .292 1.2 .398

[ 1.3 .541

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. 1.4 1.5

.735 1.

1.6

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1.35 1.7 1.847 1.8 2.511' 1.9 3.414

2. 4.641 2.1 6.309, 2.2 8.576 2.3 11.659 2.4 15.848 2.5 21.544 2.6 29.286

• 39.810 2.7 2.8 ' 54.116 2.9 73.564

3. 100.

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EPIP 1.4 MINOR

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Revision 7 05-27-83 RADIOLOGICAL DOSE EVALUATION 1.0 GENERAL The purpose of this procedure is to provide a method to quickly estimate (1) X/Q using meteorological overlays, (2) thyroid and whole body dose using X/Q and (3) ground deposition using an approximation of D/Q.

2.0 REFERENCES

2.1 U. S. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1,"

October 1977.

2.2 U. S. EPA, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," EPA-520/1-75-001, September 1975. See Appendix D " Technical Bases for Methods that Estimate the Projected

[ Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radioiodines and Radioactive Noble Gases."

2.3 U. S. NRC Regulatory Guide 1.4, " Assumptions used for Evaluating the Potential Radiological Consequences of a Loss-of Coolant Accident for Pressurized Water Reactors," Revision 2, June 1976.

2.4 TID 14844, " Calculation of. Distance Factors for Power and Test Reactor Sites," March 23, 1962.

, 3.0 PRECAUTIONS & LIMITATIONS 3.1 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.

3.2 Ensure that all PBNP maps to be used by this procedure and their corresponding meteorological overlays are based on the same scale.

3.3 This procedure will be accomplished in the technical support center by a person designated by the Shift Supervisor or the Technical

, Support Manager. It will usually be done in conjunction with the Chemistry / Health Physics Supervisor when available.

l 3.4 This procedure will also be accomplished in the ESC by a person j designated by the RadCon/ Waste Manager.

l

, EPIP 1.4 I Page 2 3.4 Wind speed and wind direction must be average values obtained from the analog recorders in the control room.

NOTE: DO NOT USE INSTANTANEOUS VALUES.

3.5 If the radiological release duration is unknown, assume a duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

3.6 If the meteorological parameters cannot be obtained from the control room, obtain the data from the following priority backup list.

3.6.1 Kewaunee Nuclear Power Plant. See EPIP-23, "Offsite Agency Call' List."

3.6.2 National Weather Service in Green Bay. Ask for Two Rivers Coast Guard information, if available. See EPIP-23, "Offsite Agency Call List."

~

4.0 INITIAL CONDITIONS 4.1 A release of airborne radioactivity has occurred or a release is anticipated.

4.2 An emergency or potential emergency condition is anticipated to have offsite dose consequences.

5.0 PROCEDURE / CHEMISTRY & HEALTH PHYSICS SUPERVISOR OR DESIGNEE 5.1 Determination of X/Q, Atmospheric Dispersion Factor 5.1.1 Obtain the following information from the indicated source and enter this data in the appropriate space on form EPIP-07 -

(attached).

Source Data '

EPIP-04 (a) wind speed in-mph EPIP-04 (b) wind direction EPIP-04 (c) time of reactor shutdown EPIP-04 (d) time of release to containment EPIP-04 (e) time of release from the plant Health Physics or Operating (f) duration or estimated dura-logs or projected estimate tion of the release in-hours

, EPIP 1.3 results (see note)

(g) gross Xe-133 equivalent release rate in Ci/sec ,

EPIP-04 (h) Stability Class in c6 degrees '

NOTE: IF RELEASE DURATION IS UNKNOWN, ASSUME 8 HOURS.

5.1.2 Determine stability class by use of the c6 chart recorder in the control room and Attachment 1.4-1. Enter the stability class (h) on form EPIP-07.  !

l I

EPIP 1.4 Page 3 5.1.3 Backup stability class determination ~. Visually check cloud cover and incoming solar radiation. With this information, use Attachment 1.4-3 to ascertain the appropriate stability class. Enter the stability class (h), on form EPIP-07.

NOTE: IF INCOMING SOLAR RADIATION IS STRONG AND WINDS ARE FROM THE EAST OR SOUTHEAST, IT IS A POSSIBILITY THE WIND IS PRODUCED BY A LAKE EFFECT. CALL THE GREEN BAY NATIONAL WEATHER SERVICE FOR AID IN THIS DETER-MINATION. IF A LAKE BREEZE IS SUSPECTED, OFFSITE SURVEY TEAMS MUST BE REMINDED TO PAY CLOSE ATTENTION TO WIND DIRECTION.

5.1.4 Place the overlay corresponding to the stability class on the map. Using the plant location as a pivot point, align the centerline of the overlay to the downwind direction from the plant.

NOTE: THE " TICK" MARKS ON THE CENTERLINE OF THE OVERLAYS ARE ONE MILE APART.

5.1.5 Determine the distance (i) to the dose projection location

( if different from the standard centerline distances listed on form EPIP-07. Note the location description, sector, and distance on form EPIP-07.

Enter the Xu/Q value (j) for the distances of site boundary, two miles, five miles, and ten miles on EPIP-07. The Xu/Q values (j) can be obtained from the overlay in the table in the lower righthand corner of the overlay. If a possible location other than the standard specified location is on a line, enter the Xu/Q (j) value for that line from the overlay on form EPIP-07. If the location is not on a line, move to the next inner-most line (toward the centerline) and enter the Xu/Q (j) value for that line on form EPIP-07.

Example:

Class "C" Xu/Q for 5 miles equals 1.21 x 10~8 m 2 5.1.5 Calculate the X/Q value from the Xu/Q value by using the equation:

J X sec.

md = 2.24(sec./m) A WindXu/Q (m 2)

Speed (mi/hr.)

Q (hrs./mi)

Enter the X/Q values on form EPIP-07.

5.2 Whole Body Dose Estimate _.

NOTE: IF THE NOBLE GAS SOURCE TERM IS DETERMINED BY GRAB SAMPLE RESULTS WHICH GIVES AN INVENTORY OF SPECIFIC NUCLIDES, THEN A CONSERVATIVE WHOLE BODY DOSE ESTIMATE CAN BE MADE BY COMPLETING FORM EPIP-09. -

a .

s

" EPIP 1.4

, Page 4 5.2.1 Enter the gross Xe-133 equivalent release rate (g) on form EPIP-08 from form EPIP-07.

5.2.2 Enter the estimated release duration, ERD, in hours (f) on form EPIP-08 from form EPIP-07.

5.2.3 Calculate the projected whole body dose on form EPIP-08 by using the equation:

(k) (g) 3 3 D(Rem) = X/Q (sec/m ) x Q (Ci/sec) x Kr (Rem m /Ci - Hrs) x ERD (Hrs) where:

D = whole body dose (Rem)

X/Q = atmospheric dispersion coefficient determined in Step 5.1.5 (sec/m3 ) (k)

Q = release rate (Ci/sec) (g)

{ 3 Kr=DoseFactor(['"hs) i achment 1.4-2 ERD = Estimated Release Duration (Hours) (f) 5.3 Thyroid Dose Estimate 5.3.1 Calculate the projected thryoid dose by using the whole body dose calculated in Section 5.2 of this procedure.

5.3.2 Record the projected whole body dose on form EPIP-08 in Section 2.

5.3.3 Choose the appropriate figure based upon the type of accident which has occurred.

a. Loss of Coolant Accident (LOCA) - Figure 1.4-1.

b. Gap Activity Accident - Figure 1.4-4.

, c. Fuel Handling Accident - Figure 1.4-4.

d. Steam Generator Tube Rupture - Figure 1.4-5. .

i l

NOTE: IF THE TYPE OF ACCIDENT IS UNKNOWN, USE THE.LOCA FIGURES.

5.3.4 Obtain the ratio factor that relates the whole body dose to a thyroid dose from the figure chosen with the corresponding

appropriate time after the accident and record on form l EPIP-08, Section 2.

EPIP 1.4 Page 5 5.3.5 Calculate the projected thyroid dose my multiplying the whole body dose by the ratio factor obtained in Step 5.3.4 cc form EPIP-08, Section 2.

5.4 Radionuclide Ground Deposition Estimation NOTE: FORM EPIP-10 CAN BE COMPLETED ONLY IF IODINE GRAB SAMPLE RESULTS OR PARTICULATE RELEASE RATES ARE AVAILABLE. IF FORM EPIP-10 CANNOT BE COMPLETED, PROCEED WITH STEP 5.4.5 0F THIS SECTION.

5.4.1 Enter the Xe-133 equivalent release rate or the specific particulate release rate on form EPIP-10 from grab sample results or from environmental monitoring results.

5.4.2 Enter the estimated duration of release (f) from form EPIP-07 on form EPIP-10.

5.4.3 Enter the value of X/Q (k) on form EPIP-10 as determined in Step 5.1.5.

5.4.4 Complete Section 2 of form EPIP-10 to calculate the ground

[ deposition using the equation:

2 Dep (pci/m ) = F x .05 (m/sec) x 3600 (sec/hr) x 10 8 -(pci/Ci) x X/Q (sec/m3) x Q (Ci/sec) x ERD (hrs)

(k) (g) (f) 8 Dep = F x 1.8 x 10 x X/Q x Q x EIP Dep = ground deposition (pCi/m3)

X/Q = atmospheric dispersion factor from Step 5.1.5 (sec/m3) (k)

Q = radionuclide release rate (Ci/sec) (g)

ERD = estimated release duration (hrs) (f)

F = fraction of isotope subject to deposition (unitless) 3600 = conversion (sec/hr) 108 = conversion (pCi/Ci) 0.05 = assumed deposition velocity (m/sec) 5.4.5 Complete form EPIP-11' from available data and calculations just performed.

5.4.6 Enter the date and time of these calculations and sign form EPIP-11.

o . -

EPIP 1.4 Page 6 5.4.7 Forward completed attachments to the Technical Support Manager for review. The Technical Support Manager will' relay results to the Site Manager.

5.5 Population Exposure 5.5.1 Calculate projected population exposure by using form EPIP-10a.

5.5.2 Enter from EPIP-08 whole body dose from center line on form EPIP-10a.

5.5.3 Enter population figures from Figure 1.4-6. Use population number corresponding to the quadrant and distance categories for dose.

5.5.4 Total population dose from each radius to find total population dose.

( -

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ATTACHMENT 1.4-1 CLASSIFICATION OF AT'MOSPHERIC STABILIT'l BY SIGMA THETA Stability Pasquill 00 i

Classification Categories (degrees)

Extremely unstable A 00 2 22.5 Moderately unstable B 22.5 > 00 2 17.5 Slightly unstable C 17.5 > 00 2 12.5 Neutral D 12.5 > 00 2 7.5 Slightly stable E 7.5 > 00 2 3.8 Moderately stable  : F 3.8 > 00 2 2.1 Extremely stable G 2.1 > 00 i

ATTACHMENT 1.4-2 WHOLE BODY DOSE RATE CONVERSION FACTORS

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ATTACHMENT 1.4-3 BACKUP DETERMINATION OF ATMOSPHERIC STABILITY CLASS Surface Wind Speed, Day Night (at 50 meters) Incoming Solar Radiation Thinly Overcast mph Strong Moderate Slight > 1/2 low cloud < 1/2 cloud

<4 A A-B B F G 4-7 l A-B B C E F 7-11 B B-C C D E 11-13 C C-D D D D

>13 C D D D D The neutral class D, should be assumed for overcast conditions during day or night.

" Strong" incoming solar radiation corresponds to a solar altitude greater than l 60* with clear skies; " slight" incoming solar radiation corresponds to a solar

[ altitude from 15 -35 with clear skies. Cloudiness will decrease incoming solar radiation and should be considered along,with solar altitude when determining solar radiation. Incoming radiation that would be strong with clear skies can be expected to reduce to moderate with broken (5/8 to 7/8 cloud cover) middle clouds and to slight with broken low clouds. Night refers to the period from ode hour before' sunset to one hour after sunrise.

• l ATTACHMENT 1.4-6 l l

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1 EPIP 2.3 MNOR Revision 3 05-27-83 UNUSUAL EVENT - 0FFSITE AGENCY NOTIFICATION 1.0 GENERAL The purpose of this procedure is to establish the initial offsite agency notification actions in response to plant conditions classified as an Unusual Event in accordance with EPIP 1.1, " Initial Classification."

Necessary phone numbers are included in form EPIP-23, "Offsite Agency Emergency Call List."

2.0 REFERENCES

None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 .0btain the name and title of the person being contacted prior to transmitting any information.

3.2 If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt to contact the persons or agencies who have not been notified.

3.3 All actions and notifications should be appropriately logged on form EPIP-12 (attached), " Unusual Event Incident Report Form," Sections 1, 2 and 3 and/or on EPIP-23, "Offsite Agency Emergency Call List."

4.0 INITIAL CONDITIONS 4.1 Unusual Event emergency conditions exist.

4.2 This procedure should be initiated as soon as possible after the initial classification.

, 5.0 PROCEDURE _ . . .

l ,

1 5.1 Designee 2 5.1.1 Complete Section 1 of the incident report form (form EPIP-12, attached) using the infennation given by the Shift Supervisor. {

Examples of emergency response include: shut the unit down, l call in additional firefighters or secure doors against high l

winds.

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EPIP 2.3 Page 2 5.2 Security Lieutenant or Designee 5.2.1 Notify the Manitowoc County Dispatcher by telephone (tele-phone number listed on form EPIP-23, "Offsite Agency Emergency call List"). Read Section 1 of the incident report form and ensure that the infarmation is fully understood.

5.2.2 Notify Kewaunee County Dispatcher by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Read Section 1 of the Incident Report Form and ensure that the information is fully understood.

5.2.3 Notify the State of Wisconsin Division of Emergency Govern-ment by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). Read Section 1 of the Incident Report Form and ensure that the information is fully understood.

5.2.4 Pick up the NRC Operations Center, Bethesda, dedicated line. =

, 5.2.5 When a response is heard, read 5ection 1 of the incident report form.

5.2.6 If no response is received, contact the NRC Operations by telephone (telephone number listed on form EPIP 23, "Offsite Agency Emergency Call List") and repeat Step 5.1.3.

5.2.7 Have the Shift Supervisor make an appropriate entry into the NRC Operations Center, Bethesda, phone log.

5.2.8 Attempt to contact the NRC resident inspector (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List"). This courtesy notification is to inform him of the unusual event.

e 0

j c I EPIP 3.3 MINOR Revision 2

'O" 05-27-83 l

1 ALERT - 0FFSITE AGENCY NOTIFICATION 1.0 PURPOSE The purpose of this procedure is to establish the initial offsite agency notification responsibilities in response to plant conditions classified as an Alert in accordance with EPIP 1.1, " Initial Classification." Necessary phone numbers are included in form EPIP-23, "Offsite Agency Emergency Call List."

2.0 REFERENCES

None

, 3.0 PRECAUTIONS AND LIMITATIONS ,

3.1 Obtain the name and title of the person being contacted prior to transmitting any information.

3.2 If unable to contact an individual or agency, continue with the notification of the other individuals or agencies and then attempt to contact the persons or agencies who have not been notified.

3.3 All actions and notifications should be appropriately logged in form EPIP-23, "Offsite Agency Emergency Call List," or form EPIP-13 (attached), Sections 1, 2, and 3.

4.0 INITIAL CONDITIONS 4.1 Alert emergency conditions, exist.

4.2 This procedure should be initiated as soon as possible after the initial classification. The goal is to complete this notification 1

within 15 minutes of the initial classification.

5.0 PROCEDURE _, _

a 5.1 Designee -

5.1.1 Complete Section 1 of the incident report form (form EPIP-12, attached) using the information given by the Shift Supervisor.

Examples of emergency response include: shut the unit down, call in additional firefighters, and secure the doors against high wind.

)

i

EPIP 3.3 l

, Page 2  !

, v-1 5.2 Security Lieutenant or Designee 5.2.1 Pick up the NAWAS handset and make the following trans-mission:

THIS IS POINT BEACH ('AT.T.ING WARNING CENTER 2, MANITOWOC COUNTY, AND KEWAUNEE COUNTY. THIS IS POINT BEACH CALLING WARNING CENTER 2, MANITOWOC COUNTY AND KEWAUNEE COUNTY.

NOTE: THE THREE CENTERS SHOULD RESPOND. NOTE ANY CENTERS NOT RESPONDING AND PROCEED WITH THE PROCEDURE.

i 5.2.2 Transmit Section 1 of the incident report form over the NAWAS system. Ensure that the three centers fully under-stand the transmission.

5.2.3 contact by telephone, the centers (noted in Step 5.1.2 of this procedure) which were unable to be contacted over the NAWAS system (phone numbers listed on EPIP-23, "Offsite Agency Emergency Call List").

5.2.4 Read Section 1 of the incident report form. Ensure that the information given is fully understood.

5.2.5 Pick up the NRC Operations Center, Bethesda, dedicated line.

When a response is heard, read Section 1 of the incident report form.

5.2.6 If no response is heard, contact the NRC Operations by telephone (telephone number listed on form EPIP-23, "Offsite Agency Emergency Call List") and repeat the appli-cable portion of Step 5.1.2.

5.2.7 Have the Shift Supervisor make an appropriate entry into the NRC Operations Center, Bethesda, phone log.

5.2.8 Attempt to contact the NRC Resident Inspector (telephone number listed on EPIP-23, "Offsite Agency Emergency Call List"). Inform him of the Alert emergency condition.

5.2.9 Notify Kewaunee Nuclear Power Plant (telephone number listed on EPIP-23, "Offsite Agency Emergency Call List"). Inform them of the alert emergency condition.

l l

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, EPIP 6.5 i MINOR

/ -

• Revision 1 05-27-83 TECHNICAL SUPPORT CENTER & OPERATIONS SUPPORT CENTER ACTIVATION 1.0 PURPOSE 1.1 To provide instructions for the activation of the technical support i

center after the declaration of an alert, site emergency or general emergency.

1.2 To outline the technical support center ventilation system operation in the event of high airborne activity.

1.3 operation of the technical support center emergency power supply is also a part of this procedure.

2.0 ACTIVATION OF TECHNICAL SUPPORT CENTER 2.1 Set up 10 tables as shcwn on Attachment 6.5-1. They may-be obtained from the rooms in the adjacent operations support center and health physics areas of the technical support center.

2.2 Install phones from the technical support center storage cabinets in j the appropriate areas as shown on Attachment 6.5-1.

2.3 Confirm that all phones operate by noting if dial tone is present when the receiver is lifted. Confirm that the numbers listed on the face of the phone matches the number on the wall jacks.

2.4 Distribute paper and pencils to.each table.

2.5 Distribute a copy of the EPIP's to the table in front of the black-board and the table near the dose plotting map (see Attachment 6.5-1).

2.6 Obtain a copy of each of the following manuals from the front office area and bring them to the technical support center. They may be obtained from the office of the Manager, General Superintendent, or the training offices.

2.6.1 Operating procedures.

2.6.2 Emergency operating procedures.

2.7 Shift the ventilation system from the normal to the emergency opera-ting mode by implementing Section 4.0.

2.8 Date and time the current charts on the safety parameter chart re-s corders in the technical support center.

O O i

. EPIP 6.5 Page 2 2.9 Dispatch a person with systems training (Duty Technical Advisor) to control room to aid in communications between the TSC and control

room. I 3.0 DATA LOGGER OPERATION 3.1 Push the' start button on the data logger. Enter the correct date and time on the printout frcm the data logger. The designations for each of the 37 channels are contained in Attachment 6.5-2.

I' 3.2 The conversion of incore thermocouple MV to degrees Fahrenheit with j the reference junction at 160* is accomplished by use of the incore thermocouple table (see Attachment 6.5-3).

3.3 The conversion of radiological monitoring point volts to mR/hr or

R/hr is accomplished by use of the conversion tables (see Attachments 6.5-4, 6.5-5 and 6.5-6).

4.0 EMERGENCY VENTILATION SYSTEM l 4.'1 The technical support center heating and ventilating system has a normal and emergency operating mode. Under normal operation the air intake is from the outside air vent on the east wall of the technical support center building. The intake air under normal operation is essentially unfiltered.

In the emergency mode, there are two optional air intake locations.

One is adjacent to the normal intake on the east wall of the techni-cal support center building and the other is on the north wall of the Unit 2 turbine hall 1.

4.2 To shift the heating, ventilating and air conditioning system from

! the. normal to emergency mode:

4.2.1 Turn the auto /off/ occupied switch on Panel M-1 to the occu-

pied position. See Attachment 6.5-7 for location of Panel j M-1.

i 4.2.2 Turn the normal / emergency control switch on Panel M-1 to the emergency position.

4.2.3 Select the north or south (east) emergency intake depending on meteorological conditions. Select the upwind intake duct.

5.0 TECHNICAL SUPPORT CENTER AUXILIARY AIR CONDITIONING 5.1 Turn on compressor CH2 on the west wall of El. 18.5' of the technical support center building (see Attachment 6.5-7).

y 5.2 Turn on air handling unit AHU2 on the technical support center building room north wall (see Attachment 6.5-1).

i .

EPIP 6.5 l Page 3 l 6.0 EMERGENCY POWER 6.1 The power source for the technical support center in 180'1 480 V. See Attachment 6.5-8 for the main disconnect location.

6.2 The emergency power source is not operational at this time.

6

/

I i

e i

1 .

j ATTACHMENT 6.5-1

l r

l l l

\

}.\. l TSC/HP l

, i w Area l mAaccoarc jAir A//v-2 l

Conditioner m

3 a

3 5 Table m o Site Mgr.

E I Plant Cperatiens ,,

R Table Manager jn N k

\' N m u 2 2 - -

Table b b

_ ,k2Q 717 8eriz/

/ccthen Safety _

Parameter E I Display Tech. O, Suc Mg$.. port

- S torage Red Phene Cabinet NAN Table Table Offsite j Comtunicator o

CSC Core Coord.

Data Proc. Coord.

Table (311) * *

! S 'E *

• Table Ek Environmental Dose Plot M

~

Status Map TECHNICAL SUPPORT CZ!TI'ER

\

.o .

ATTACHMENT 6.5-2

~ .

( .

Data Loccer Point Desicnations Channel Unit Status Parameter 0 mV Active 3) )

1 mV Active 12) Unit 1 Reference )

2 , mV Active 13) RTD )

I 3 mV Active 18) Junction Box "A" )

Unit 1 Incora 4 mV Active 22)

A erm c up es

)

5 mV Active 26) Unit 1 Reference )

6 mV Active 29) RTD )

7 mV Active 36) Junction Box "B" )

l 8 mv Active 3) )

9 mv Active 12), Unit 2 Reference )

10 mV Active 13) RTD )

1 11 mv Active 18) Junction Box "A" Uni 2 Incora

)

. 12 mV Active 22) Thermocouples

)

13 mv Active 26) Unit 2 Reference )

14 mV Active 29) RTD )

15 mv Active 36) Junction Box "B" )

16 *F Active Unit 1 Reference RID Junction Sox "A" 17 *F Active Unit 1 Reference RTD Junction Box "B" l 18 *F Active Unit 2 Reference RTD Junction Box "A" 19 *F Active Unit 2 Reference RTD Junction Sox "B" i '20 gpm Active Unit 1 Auxiliary Feed Flow "A" SG 21 gpm Active Unit 1 Auxiliary Feed Flow "B" SG 22 gpm Active Unit 1 SI Flow Train "A" 23 gpm Active Unit 1 SI Flow Train "B" i 24 ft Unit 1 Containment Sump Level l 25 ---

Unit 1 Containment High Range RMS 26 V Active Unit 1 Containment Purge Stack mm-II Ch #3 27 gpm Unit 2 Auxiliary Feed Flow "A" SG 28 gpm Unit 2 Auxiliary Feed Flow "B" SG 29 gpm Active Unit 2 SI 71ow Train "A" 30 gpm Active Unit 2 SI Flow Train "B" 31 ft Unit 2 containment Sump Level 32 ---

Unit 2 Containment High Range RMS '

33 V Active Unit 2 Containment Purge Stack RMS-II Ch #4

, 34 V Active Drumming Area Vent Stack RMS-II Ch #2 35 V Active ccmbined Area vent Stack RMS-II Ch #5 36 V Active Gas Stripper Building Vent Stack RMS-II Ch #6 37 V Active Auxiliary Building Vent Stack RMS-II Ch #1

, 'N . -

.._..7

O

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3 -

POINT DEAi. NUCLEAR PLANT INCORE T/C TABLE - REFE. .4CE JUNCTION AT 160. DEG F t MV DEG F MU DEG F MV DEG F HV DEG F HV DEG F MU DEG F 0.00 152. 7.60 497. 15.20 824. 22.00 1146. 30.40 1472. 30.00 1011.

'O.20 161. 7.00 505. 15.40 033. ~23.00 1155. 30.60 1401. 30.20 1021. .

'O.40 170. 0 00 514. 15.60 041. 23.20 1163. 30.00 1490. 30.40 1029.

0.60 100. 0.20 523. 15.00 050. 23.40 1171. 31.00 1490. 30.60 1039.

0.00 109. 0.40 532. 16.00 050. 23 60 1100. 31.20 1507. 30.00 1040.

1.00 190. 0.60 - 540. '16.20 067. 23.00' 1100. 31.40 1516. 39.00 1857.

1.20 200. 0.00 549. 16.40 075. 24.00 1197. 31.60 1524. 39.20 1867.

1.40 217. 9.00 550. 16.60 003. 24.20 1205. 31.00 1533. 39.40 1876.

1.60_ 227. 9.20 567. 16.00 092. 24.40 1214. 32.00 1542. 39.60 1085.

1.00 236. 9.40 576. 17.00' 901. 24.60 1223. 32.20 1551. 39.00 1894.

2.00 245. 9.60 '

584. 17.20 909. 24.00 1231. 32.40 1560. 40.00 1904.

2.20 254. 9.00 593. 17.40 910. 25.00 1240. 32.60 1560. 40.20 1913.

2.40 263. 10.00 602. 17.60 926. 25.20 1240. 32.00 1577. 40.40 1922, 2.60 272. 10.20 610. 17.00 935. 25.40 1256. 33.00 1506. 40.60 1932, 2.00 282. 10.40 410. 10.00 943. 25.60 1265. 33.20 1595. 40.00 1941.

3.00 290.. 10.60 627. 10.20 951. 25.00 1274. 33.40 1604. 41.00 1950.

3.20 300. 10.00 636. '10'.40 960. 26.00 1202. 33.60 1613. 41.20 1960.

3.40 309. 1 1'. 0 0 445. 18.60 968. 26.20 1291. 33.00 1621. 41.40 1969.

3.60, ~310. 11'.20 ~653, 10.00 977. 26.40 1299. 34.00 1631. 41.60 1979.

3.00' 327. 11(40 , 662.- 19.00 905. 26.60 1300. 34.20 1639. 41.00 1900.

4.00 336. 11.60- 671. 19.20 993. 26.'80 1316. 34.40 1649. 42.00 1990.

4.20 345. 11.00 679. 19.40 1002. 27.00 1325. 34.60 1657. 42.20 2000.

4.40 354. 12.00 600.' 19.60 1010. 27.20 1334. 34.00 1666. 42.40 2017.

4.60 363. 12.20 696. 19.00 1019. 27.40 1342. 35.00 1675. 42.60 2026.

4.00 372. 12.40~ 705. 20.00 1020. 27.60 1351. 35.20 1604. 42.00 2036.

5.00 301, 12.60 714. 20.20 1036. 27.00 1359. 35.40 1693. 43.00 2045. p 5.20 390. 12.00 722. 20.40 1045. 20.00 1360. 35.60 1702. 43.20 2055.

5.40 Q 399. 13.00 7 3 0,. , 20.60 1053. 20.20 1377. 35.00 1711. 43.40 2065. M 5.60 400, 13.20 739.- 20.00 1061. 20.40 1305. 36.00 1720. 43.60 2074.

I @

5.00 417. 13.40 747. 21.00 1070. 20.60 1394. 36.20 1729. 43.00 2004. M 6.00 426, 13.60 756, 21.20 1070. 20.00 1403. 36.40 1730. 44.00 2094. U 6.20 434. 13.00 765. 21.40 1007. 29.00 1411. 36.60 1740. 44.20 2103.  ?

6.40 444, 14.00 773. 21.60 1095. 29.20 1420. 36.00 1756. 44.40 2113. Y 6.60 452. 14.20 702. 21.00 1103. 29.40 1429. 37.00 1766. 44.60 2123.

6.00 462. 14.40 790. 22.00 1112. 29.60 1437. 37.20 1775. 44.00 2133.

7.00 470. 14.60 799. 22.20 1120. 29.00 1446. 37.40 1704. 45.00 2142.

7.20 479. 14.00 007. 22.40 1129. 30.00 1455. 37.60 1793. 45.20 2152.

7 40 400. 15.00 016. 22.60 1130. 30.20 1463. 37.00 1802. 45.40 2162.

ATTACHMENT 6.5-4 i

l DRUMMING AREA VENT STACK RMS-II CH #2 &

COMBitlED AIR EJECTOR DISCHARGE RMS-II CH #5 VOLTAGE TO R/HR CONVERSION TABLE RANGE 1 to 10" R/HR Volts Units R/hr 0 0.001 0.1 0.00135 .

0.2 0.001847 0.3 0.002511 0.4 0.003414 .

' O. 5 0.004641 1 0.6 0.006309 l

0. 7. 0.008576  ;'

O.8 0.011659  !

0.9 0.015848 '

1.0 0.021544 '

( 1.1 1.2 0.029286 0.039810 1.3 0.054116 1.4 0.073564 1.5 0.100 '

1.6 0.135935 1.7 0.184784 1.8 0.251188 1.9 0.341454 2.0 0.464158 -

2.1 0.630957 2.2 0.857695 2.3 1.165914 2.4 1.584893 2.5 2.154434 2.6 2.928644 2.7 3.981071 4 2.8 5.411695 2.9 7.356422 ,

3.0 10.0 l I

1 4

-a_.- . . . - . .

O O ATTACHMENT 6.5-5 r . . .

UNIT 1 RMS-II CH #3 & UNIT 2 RMS-II CH #4 CONTAINMENT PURGE STACKS VOLTAGE M R/HR CONVERSION TABLES RANGE 10-' TO 10' R/HR Volts Units - R/HR

0. 0. l' O.1 .135 I 0.2 .184 0.3 .251 0.4 .341 0.5 .464 -

0. 6 . _ . .630 0.7 .857

. 0.8 1.165 0.9 1.584

1. 2.154 1.1 2.928 1.2 3.981 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

3. 1000.

s Q

ATTACHMENT 6.5-6 4

AUXILIARY BUILDING VENT STAC'K 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 Vbits Units - R/HR

0. 0.01 0.1 .013 0.2 .018

. 0.3 .025 0.4 .034 0.5 .046 0.6 .063 0.7 .085 0.8 .116.

0.9 .158

1. .215 1.1 .292 1.2 .398 1.3 .541 1.4 .735 1.5 1.

1.6 1.35 1.7 1.847 1.8 2.511 1.9 3.414

2. 4.641 2.1 6.309 .

2.2 8.576 2.3 11.659 2.4 15.848 2.5 21.544 2.6 29.286 2.7 39.810 2.8 54.116 2.9 73.564 3 100.

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4 EPIP 7.2.2 MINOR Revision 2 i 05-27-83  ;

i l

ACTIVATION OF CHEMISTRY & HEALTH PHYSICS AT TECHNICAL SUPPORT CENTER /0PERATIONS SUPPORT CENTER 1.0 PURPOSE 1.1 The purpose of this procedure is to establish guidelines for acti-vating the Chemistry & Health Physics facilities at the technical i

support center / operations support center (TSC/OSC) in support of an emergency situation which may require evacuation of the main plant buildings.

1.2 The Chemistry / Health Physics Supervisor and certain designated mem-

, bers of the Chemistry & Health Physics Group are responsible for activating the health physics equipment at the TSC/OSC The extent and sequence of implementation of these guidelines will be outlined in EPIP 7.1.1.

2.0 ACTIVATION OF HEALTH PHYSICS FACILITIES AT TSC/OSC 2.1 For emergency conditions during which a plant evacuation is not required, the Chemistry / Health Physics Supervisor and Health Physics Director will determine to what extent, if any, health physics cover-

, age will be provided at the TSC/OSC.

2.2 For emergency conditions which require plant evacuation, Appendix "A" guidelines of EPIP 7.1.1 should be followed. The sequence for imple-mentation of Appendix "A" guidelines depends upon whether Chemistry &

Health Physics Group personnel are on or off-site when notification is received (EPIP 7.1.1 and EPIP 7.1.2).

3.0 HEALTH PHYSICS RESPONSIBILITIES FOR TSC/OSC/ RAD SUPPORT TEAM 3.1 When Chemistry & Health Physics Personnel are on-Site (EPIP 7.1.1) 3.1.1 Obtain five (5) t 'C-6A survey instruments.

I 3.1.2 Proceed to the TSC/OSC and:

l .

a. Move the AMS-2 continuous air sampler (cart-mounted) into the TSC/OSC hallway and set up for operation.

, , , , , _ . , , y , _g m 2 - 4 e- ' + - - - -

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EPIP 7.2.2 Page 2

b. Place the Vamp area monitor at the south gate in oper-ation.

c. Set up and place into operation the south gate low volume air sampler.

d. Collect two portable radios W ) and:

1. Return one (1) radio ( M to the TSC.

2. The second radio M should be taken to the OSC counting room.

e. Proceed to the TSC/OSC and begin preparation to provide health physics support as described under OSC/HP equip-ment activation, Section 3.3 of this procedure.

3.2 Notification When Chemistry & Health Physics Personnel are Off-Site (EPIP 7.1.2) 3.2.1 Upon receipt of instruction to activate the TSC/OSC, one member of the OSC/ rad support team will proceed to the ESC located in the basement of the Energy Information Center and:

a. Set up and place into operation the low volume air sampler and Vamp area monitor.

b. Perform a communications check of the portable radio (KRQ 717) located in the Duty Technical Advisor's sleeping quarters.

c. Proceed to the TSC/OSC.

3.2.2 The remainder of the OSC/ rad support team will' set up and place into operation the Vamp area monitor and the low volume air sampler at the south gate.

l 3.2.3 Proceed to the TSC/OSC and move the AMS-2 continuous air sacpler (cart-mounted) into the TSC/OSC hallway; set up and place the AMS-2 into operation. ,

l l

3.2.4 Begin preparation to provide health physics coverage as I described under OSC/HP equipment activation, Section 3.3 of this procedure.

EPIP 7.2.2 Page 3 3.3 OSC/HP Equipment Activation 3.3.1 Prepare the health physics equipment from the emergency locker for use.

3.3.2 Prepare 6 radio for communications check.

3.3.3 Provide health physics support as required at the TSC/OSC and in-plant support as requested by the Chemistry / Health Physics Supervisor.

3.3.4 Assist in response to medical emergencies within the pro-tected area (EPIP 11.0).

3.3.5 Coordinate with the Chemistry / Health Physics Supervisor at the TSC/OSC on in-plant personnel exposure and documenta-i tion.

3.3.6 Verify that all personnel who are departing from the OSC are certain as to cetails of their approved assignments and are ccmplying with all health physics requirements. Whenever practicable, ' entries into high radiation or airborne areas will be made under the radiation work permit system.

(

, EPIP 7.2.4 MINOR

/ -

Revision 2 05-27-83 HEALTH PlWSICS COMMUNICATIONS 1.0 PURPOSE The purpose of this procedure is to provide communications guidelines for the Chensistry & Health Physics group to assist in the performance of their duties during an Emergency Plan situation requiring plant evacuation and/or in the event that surveys outside of the protected area are required.

2.0 COMMUNICATIONS, GENERAL 2.1 Radiological response activity communications between the health

physics response teams (EPIP 7.2.1) will normally be accomplished utilizing the M radio network. Telephone communications should be held to a minimum.

2.2 The following locations of eggEEEF radios will be maintained during a

. Site or General Emergency:

Location Type 2.2.1 Control Room Base station 2.2.2 Technical Support C, enter Portable 2.2.3 Operations Support Center Portable 2.2.4 Site Boundary Control Center Portable 2.2.5 Emergency Vehicle Mobile 2.2.6 Other Plant Vehicles (2 each) Mobile 2.2.7 Emergency Support Center Portable **

• • 0ne available from Duty Technical Advisor rest station 2.3 KRQ 717 radio communications network functional check:

2.3.1 Upon arrival at their assigned locations health physics personnel shall place the radios ) in an operating mode and stand by for a radio check. The site boundary control center is responsible for initiating the radio check. The results of the communications check should be recorded in the site boundary control center logbook.

2.3.2 Mobile or portable radio unita should also be given a func-tional check prior to departing from the site boundary control center for the performance of assigned duties.

\

a

. EPIP 7.2.4 Page 2

.~

2.3.3 Communications between portable or mobile radio units is limited by the distance or terrain between them. In some cases, communications to another portable or mobile unit will have to be relayed through the control room base station.

2.3.4 Radio antennas must not be in contact with etal structures when being used to transmit.

3.0 RADIO PROTOCOL 3.1 To eliminate confusing radio transmissions and to expedite communi-cations, the following should be adhered to:

3.1.1 Identify the radio call-sign and your unit or location at the start of each transmission.

EXAMPLE: THIS IS W , SURVEY TEAM #1 3.1.2 Identify unit or location being c'alled.

EXAMPLE: THIS IS 6 , SITE BOUNDARY CONTROL CENTER CALLING THE TECHNICAL SUPPORT CENTER.

3.1.3 ' Use of radios are for business purposes only.

3.1.4 Limit the time of all transmissions.

3.1.5 FCC regulations prohibit the use of vulgar or profane language.

3.1.6 Upon completion of the conversation, sign off as follows:

EXAMPLE: KRQ 717, SURVEY TEAM #1, CLEAR & STANDING BY.

4.0 USE OF TELEPHONES 4.1 The use of the telephone communications network by health physics personnel during an Emergency Plan situation will be limited to the following:

l 4.1.1 NRC Health Physics Dedicated Line

( These lines are located in the Chemistry & Health Physics group office and at the site boundary control center. They

~

provide a means of direct communications with the NRC health physics offices during an emergency. The use of these lines l will be only as directed by the Chemistry / Health Physics l Supervisor, the Health Physics Director or other ranking plant supervisors.

EPIP 7.2.4 Page 3 4.1.2 Plant PBX Telephone System This system provides direct dialing between plant locations within the on-site and protected areas. The use of these .

lines is to be limited to business-related calls.

4.1.3 Off-Site Telephone Lines These lines provide for direct dialing to off-site loca-tions. The use of these lines is to be limited to business-related calls. Use should be minimized to the extent practicable.

(

8 i

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. . _ , _ e

EPIP 7.4.1 HINOR

. Revision 7 05-27-83 ROUTINE CHECK, MAINTENANCE, CALIBRATION & I!NENTORY SCHEDULE FOR HEALTH PHYSICS EMERGENCY PLAN EQUIPMENT 1.0 PURPOSE The purpose of this procedure is to establish the routine checks, mainte-nance, calibration and inventory schedules for health physics related material and equipment applicable to the Emergency Plan.

20 EMERGENCY PLAN EQUIPMENT STORAGE LOCATIONS 2.1 Emergency Plan equipment is normally maintained in a state of opera-tional readiness at the following locations.

2.1.1 Health physics station

• 2.1.2 Technical support c' enter (TSC) 2.1.3 Emergency support center (ESC) 2.1.4 Operations suppor,t center (OSC) 2.1.5 S'ite boundary control center'(SBCC) .

2.1.6 Control room 2.1.7 Two Rivers Community Hospital (NFAR and triage area) 2.1.8 Point Beach Nuclear Plant first aid room (see EPIP 11.0) 2.1.9 South gatehouse.

2.1.10 Other items of Emergency Plan equipment such as first aid

. kits, burn kits, trauma kits, stretchers, and the emergency vehicle are maintained at specified locations throughout the plant.'

3.0 ROUTINE CHECK, MAINTENANCE AND CALIBRATION SCHEDULES , . . .

Routine checks, maintenance and calibration of Emergency Plan equipment will be consistent with the schedule outlined in Attachment "A" and the l

instructions contained in EPIP 7.4.2, " Emergency Plan Equipment Routine j Check, Maintenance & Calfbration Instructions."

,- a . , , ., ,

-- - +

EPIP 7.4.1 Page 2 4.0 IINENTORY SCHEDULE 4.1 Inventory of health physics related Emergency Plan equipment will be i consistent with the schedules provided in Attachment "A".

4.2 Inventory of Emergency Plan equipment will be accomplished utilizing the inventory checklists listed belc'a and attached to this procedure.

Missing or deficient items noted by the inventory will be promptly replaced by personnel assigned to accomplish the inventory. The results of all inventories will be reviewed by the Health Physics

- Supervisor. The completed inventory forms will then be forwarded to the Nuclear Plant Specialist /HP assigned this responsibility. He will prepare a report, including any deficiencies. The report will be forwarded to the Health Physicist, Superintendent - CHP and Superintendent - Technical Services. Discrepancies will be corrected on the lowest possible level of review and noted on the appropriate

, checklist or report.

4.2.1 Inventory Checklists

a. Site boundary control center (form EPIP-24a)*

b. OSC, ESC, and South Gateho,use (form EPIP-24b)*

c. Two Rivers Community Hospital (form EPIP-24c)*

. d. Control room (form EPIP-24d)*

e. Emergency vehicle (form EPIP-24e)

f. First aid kits (form EPIP-24f)

g. Burn kits (form EPIP-24g)

h. PBNP first aid room (form EPIP-24h)*

i. Stretchers (form EPIP-24i)

j. Trauma kits (form .EPIP-24j) -

• The form needs to be filled out with an item by item count on an annual basis. Quarterly checks can be accomplished by verification of administrative controls such as seals.

i I

I l

l ATTACIDiENT "A" EMERGENCY PLAN EQUIPMENT ROUTINE CHECK, MAINTENANCE, CALIBRATION AND INVENTORY SCHEDULE 3 a

>, N $ $ s Cross

$o $e U e

b a

e Reference ;I $ [): d $

1. Emergency Vehicle

a. Radio operational test X

b. Vehicle visual inspection and engine start x

c. Emergency equipment inventory x

d. Vehicle test drive x1 x2

1. November through March

2. April through October

(' 2. First Aid Kits, Burn Kits, Trauma Kits and Stretchers 3

a. Inventory X

3. January, April, July, September

3. Vamp Portable Area Monitors

a. Functional check X

b. Calibration x

4. Emergency Center Air $iamplers -

(115 V AC) }

a. Functional test x

b. Preventive maintenance .

(where applicable) x

c. Flow rate calibration X

5. SBCC Air Sampler (Battery 12 V DC)

a. Functional test X

b. Flow rate calibration X.

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6. AC Generator (Gasoline Powered)

a. Functional test X

b. Spare gasoline changed. X

c. Maintenance X

7. Batteries - Replacement

a. Traffic warning lights x

b. Survey / counting instruments X

c. Flashlights X

d. , Portable radios NEEEEEEE9 X

e. Dosimeter chargers X

4. Alkaline type batteries to be used where possible and to be replaced' yearly. Standard carboncells,i{used,tobe load tested for 5 minutes quarterly and replaced yearly or as load test dictates.

8. Potable Water (Stored)

a. Water changed x

9. Counting Instruments l a. Functional test X i b. Calibration x

c. Counting efficiency determination x

10. Frisker Type Instruments

! a. Functional test X

b. Calibration X

c. Efficiency determination X

11. Portable Survey Instruments i

[ a. Functional test X

b. Cal,ibration -

x P

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% f U L E Cross g g g g g Reference 3 E O M 4

12. Pocket Dosimeters and TLD's Dosimeter drift / response check X

a. '

X

b. TLD'.s changed

13. Respirators

a. Inspection X

14. MSC SCBA Units

a. Inspection X

b. Functional test X

15. Bio-Paks (Oxygen Reb pathers)

a. Inspection X

b. Functional test X ~~

c. Periodic maintenance X

16. Inventory of Emergency Plan Equipment - Complete X

5. This inventory includes all equipment listed for each center on forms EPIP-24a, b, c, d and h.

17. Portable Radio (KRQ 717) i Functional Check X

! Rechargeable Battery Load Test X

18. Traffic Warning Light Functional

. Check X

19. Technical Support Center AMS-2/RM-14 Air Monitoring System

a. Calibration . X l 20. Silver Zeolite (AqZ) Moisture Indicator Check x t

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EPIP 7.4.2

' MINOR Revision 5 05-27-83 EMERGENCY PLAN EQUIPMENT ROUTINE CHECK, MAINTENANCE AND CALIBRATION INSTRUCTIONS 1.0 PURPOSE The purpose of this procedure is to provide instructional guidelines for the performance of routine checks, maintenance, calibration and inventory of health physics related Emergency Plan equipment.

2.0 PRECAUTIONS 2.1 Personnel handling radioactive sources or other radioactive material will use remote handling equipment, shielding as appropriate and common sense to prevent unnecessary personal exposure.

2.2 A. calibrated survey meter will be used when working with sources of radioactive material. .

2.3 Appropriate personnel monitoring devices (TLD, high and low range

( dosimeters) will be worn.

2.4 General safety precautions will be adhered to at all times.

3.0 GENERAL INSTRUCTIONS 3.1 Shortages of material or equipment found during inventory will be noted on the appropriate inventory form. Restocking of all missing items will be accomplished expeditiously as possible and noted on the inventory record.

3.2 Items of equipment requiring repair or calibration by other than Health Physics requires the initiation of a maintenanc( request. The words " Emergency Plan Equipment" will be written in bold letters in the " Defect / Request" block of the maintenance request form. .

3.3 Equipment removed from an Emergency Plan location for other than short periods (one day) for calibration or routine maintenance will be replaced with a similar item from the health physics station unless otherwise directed by the Health Physics Supervisor.

4.0 PORTABLE SURVEY INSTRUMENTS AND AREA MONITORS (VAMP)-

4.1 Portable survey instruments and area monitors normally assigned for Emergency Plan use (forms EPIP-24a-h) are scheduled for routine calibration consistent with HP 13.2, " Portable Survey Instruments and Calibration Procedures," and form EPIP-28, " Emergency Plan Instrument Calibration Schedule."

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EPIP 7.4.2 Page 2 i

4.2 Functional checking and testing of portable survey instruments and vamp area monitors will consist of response testing each instrument with a radioactive source placed in a known and consistent geometry.

Results are recorded on form EPIP-25b.

4.3 Functional check and Test 4.3.1 Eberline PIC-6A, Rad Owl Two, Radector III, Mini-Rad, HPI-1010 and VAMP Ar*1 Monitors These instruments do not have an installed check source. A small Cs-137 check source, serial number CS-11, will be utilized for response testing of these instruments.

5.0 FRISKER-TYPE SURVEY INSTRUMENTS 5.1 Frisker-type survey instruments normally assigned for Emergency Plan usage (form EPIP-24a-h) are scheduled for routine calibration and efficiency determinations consistent with HP 13.3, " Personal Friskers

and Portal Monitor Description and. Calibration," and form EPIP-29,

" Emergency Plan Counting Equipment and Frisker Calibration Schedule."

5.2 Functional checking and testing of frisker-type instruments will

('~ consist of exposing the instrument to a known source in a consistent geometry. Results are recorded on fccm EPIP-29.

5.3 Functional Check and Test 5.3.1 Install fresh batteries and verify that the battery check position operates where applicable.

5.3.2 Tnyac III, Model 490 Retract the beta shield and expose the GM tube detector.

Place the detector opening directly over the uranium beta source that is attached to the instrument case. Record the results.

5.3.2 GSM-5 Attach a HP-210 detector to the GSM-5 and place the detector .

on the SH-4 holder for reproducible geometry. Use the Sr-90 l check source, serial number S-23, for the response check.

Record the results.

5.3.3 RM-3C Attach an HP-210 detector to the RM-3C and place the detector on the SH-4 holder for reproducible geometry. Use the Sr-90

\

check source, serial number S-23, for the response check.

Record the results.

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EPIP 7.4.2 Page 3 7 ,

6.0 COUNTING INSTRUMENTS i

6.1 Counting equipment normally assigned for Emergency Plan use (form  ;

EPIP-24a-h) are scheduled for routine calibration and efficiency determinations on form EPIP-29, " Emergency Plan Counting Equipment and Frisker Calibration Schedule," and will be completed cenristent with HP 13.5, " Counting Equipment Efficiency Determinations.".

6.2 Functional checking and testing of counting equipment will consist of response testing each instrument with a known radioactive source in a consistent geometry. Results are recorded on form EPIP-29.

1 6.3 Functional Check and Test

? 6.3.1 Nuclear Chicago Counter Scaler Attach an HP-210 detector to the instrument and place the detector on the SH-4 holder for reproducible geometry. Use the Sr-90 check source, serial number S-23, for the response check. Record the results.

. 7.0 AIR SAMPLERS i

7.1 Air samplers normally assigned for Emergency Plan usage (form Nos. EPIP-24a-h) will be maintained and flow calibrated using the procedures in HP 13.6, " Maintenance and Calibration of RAP-1 and RAS-1 Air Samplers," and HP 13.10, " Maintenance and Calibration of High volume Air Samplers." Record results on applicable forms listed in the above procedures.

7.2 Functional checking and testing of the various types of air samplers is described below. Record results on form EPIP-25b.

7.3 Functional Check and Test 7.3.1 115 V AC Power Air Samplers _

Install filters and operate air samplers for five minutes.

7.3.2 Battery (12 V DC) Powered Air Samplers -_

a. Check electrical leads for damage. The battery clips should not be bent and should engage the battery termi-

, . nals firmly.

l l b. Install air filters and connect the electrical leads to l

a vehicle battery and operate the vehicle engine at a fast idle rate.

c. Operate the air sampler for approximately two minutes.

Any overheating of the sampler is an indication of a t

problem.

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EPIP 7.4.2 Page 4 7 ,

8.0 D0'SIMETRY DEVICES 8.1 Dosimeters normally assigned for Emergency Plan use will be drift and response checked consistent with HP 10.1.3, " Dosimeter Calibration /

Response and Drift Check Procedure." Note the required entry on form EPIP-25d.

9.O RESPIRATORY EQUIPMENT Respiratory protection equipment assigned for Emergency Plan use will be inspected, tested and maintained consistent with HP 12.1, " Respiratory Protection." Note required entry on form EPIP-25c, and d.

10.0 FIRST AID KITS, BURN KITS, AND STRETCHERS 10.1 First aid and burn kits found with the lead seal intact do not have to be physically inventoried. Kits found with the lead seal broken will be inventoried and the missing items replaced. Note required entries on EPIP-24f, "First Aid Kit Inventory Checklist," form EPIP-24g, " Emergency Burn Kit Inventory," and EPIP 24-i, " Stretchers."

11.0 EMERGENCY VEHICLE

(' visual inspection of the emergency vehicle will be accomplished per form EPIP-25a, " Emergency Vehicle Checklist". The test run; when required, should follow the route from the plant to Highway 42 via Nuclear Road, then right to Tapawingo Road and return to the plant. The radio operational check between the vehicle and the control room will be made from Highway 42.

12.0 SILVER ZEOLITE FILTER MOISTURE CHECK Visual inspection of the moisture indicating devices should be performed annually. Check each filter's indicator. If it is blue, the filter has no moisture in it. If it is pink, moisture is present and the filter should have the excess moisture driven off. (Reference file HP 9.6, RadeCo Company letter to R. S. Bredvad from Francis S. Smith, dated 5-29-81, for procedure.)

13.0 GASOLINE POWERED AC GENERATOR 13.1 Functional Test 13.1.1 Check oil level at full mark.

13.1.2 Ensure all loads are disconnected from the alternator and install grounding stake.

13.1.3 Add a small amount of gasoline to the fuel tank.

13.1.4 open the fuel valve.

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EPIP 7.4.2 1 l ,

Page 5 I I

l 13.1.5 Make sure the stop switch is away from the spark plug.

13.1.6 Choke the engine.

13.1.7 Start, by pulling the starter cord.

13.1.8 Run for at least 30 minutes, place a small load on the unit during the test (high volume or low volume air sampler).

! 13.1.9 Remove the load from the unit and shut the fuel valve.

Allow the unit to stop on loss of fuel.

13.2 Maintenance Annual maintenance to be done according to Maintenance callup pro-cedure by Maintenance group.

14.0 CARBON CELL POWERED EQUIPMENT 14.1 Traffic warning lights equipp'ed with carbon cell batteries are to be load tested and documented on EPIP-25c in the following manner:

14.1.1 Ensure correct battery installation.

14.1.2 Turn on light and allow to operate for-5 minutes.

14.1.3 If the light appears to be bright and not diminishing in intensity after the 5-minute test, battery is suitable for continued use.

14.1.4 If the light fades or goes dead after 5 minutes, replace the battery in storage with a new one.

19.1.5 Carbon cells are to be replaced once per year.

15.0 PORTABLE RADIO / RECHARGEABLE BATTERY LOAD TEST 15.1 To ensure that the rechargeable batteries used with the portable radios do not develop a shallow use cycle, the following test will be conducted on the radio units.

15.1.1 Disconnect battery charger and remove the battery unit from radio.

15.1.2 Connect the battery discharge unit. Note that the voltage shown must be multiplied by two to equal the battery voltage.

15.1.3 The discharge unit is to be connected at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or until the battery voltage is about 7 to 8 v.

s 15.1.4 Remove the discharger, reconnect the battery pack to the radio and connect the battery charger.

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