ML20207A855

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Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 3 to EPIP 2.2, Unusual Event-Plant & Company Personnel Notification & Rev 3 to EPIP 3.2, Alert.... W/860715 Release Memo
ML20207A855
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/27/1986
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20207A843 List:
References
PROC-860627-02, NUDOCS 8607170296
Download: ML20207A855 (141)


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s 06-27-86 EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS Revision Date 1.0 CLASSIFICATION & ASSESSMENT 1.1 Plant Operations Manager Initial Response .

. . . . . . . .. ... 4 04-01-86 1.2 Event Classification . . . . . . . . . . . . 14 09-03-85 1.3 Offsite Agency Notification . . . . . . .. 1 04-01-86 1.4 Radiological Dose Evaluation . . . . . . . . 12 03-22-85 1 1.5 Protective Actior. Evaluation . . . . . . . . 11 04-01-86 1.6 Radioiodine Blocking & Thyroid Exposure Accounting . . . . . . . . . . . . . . .. 3 08-15-84 h

1.7 3

Evaluation of Core Damage . . . . . . . .. 8 12-30-85. '

1.8 Emergency Off-Site Dose Estimations . . .. 9 09-03-85 2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES 2.1 Unusual Event - Immediate Actions . . . .. 6 04-01-86 2.2 Unusual Event - Plant & Company Personnel Notification . .............. 3 06-27-86 2.3 DELETED

(_ 3.0 ALERT IMPLEMENTING PROCEDURES 3.1 Alert - Immediate Actions . . . . .. . . . 8 04-01-86 3.2 Alert - Plant & Company Personnel Notifi-cation . . . ............... 3 06-27-86 3.3 DELETED 1 l

l 4.0 SITE EMERGENCY - IMPLEMENTING PROCEDURES l 4.1 Site Emergency - Immediate Actions . . . . . 11 04-01-86 4.2 Site Emergency - Plant & Company Personnel Notification . .............. 3 06-27-86 4.3 DELETED 5.0 GENERAL EMERGENCY - IMPLEMENTING PROCEDURES 5.1 General Emergency - Immediate Actions . . . 11 04-01-86

, 5.2 General Emergency - Plant & Company Personnel i

Notification . . . . . . . . . . . . . . . 3 06-27-86 5.3 DELETED N6 e 8607170296 860627 ~

PDR ADOCK 05000266 F PDR

f Page 2 Revision Date 6.0 EVACUATION 6.1 Limited Plant Evacuation . . . . . . . . . . 3 09-09-83 I 6.2 Plant Evacuation . ............. 6 03-22-85 6.3 Exclusion Area Evacuation ......... 4 03-22-85 6.4 Energy Information Center Evacuation . . . . 3 03-22-85 6.5 TSC & OSC Activation . . . . . . . . . . . . 8 05-27-86 6.6 DELETED 6.7 Emergency Operations Facility Activation . . 4 06-27-86 7.0 CHEHISTRY AND HEALTH PHYSICS RESPONSE & PREPAREDNESS 7.1 Internal Chemistry and Health Physics Personnel Notification / Initial respor.se 7.1.1 Chemistry and Health Physics On-Site Notification and Response . . . . 7 03-22-85 7.1.2 Chemistry and Health Physics Offsite 1 Notification and Response . ... 4 03-22-85 3 7.1.3 Health Physics Protective Actions by

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Operations Personnel Prior to Arrival of HP Personnel . . . . . . . . . 4 03-22-85 7.2 Health Physics Facility Activation 1

7.2.1 Activation of HP Facilities at Site Boundary Control Center . . . . . 7 06-27-86

! 7.2.2 Activation of Health Physics Facili-ties at Technical Support Center /

Operations Support Center 7 06-27-86 7.2.3 DELETED 7 . 2 . 4, Health Physics Communications . . . 4 03-22-85 t 7.2.5 DELETED 7.3 Radiological Surveys 7.3.1 Airborne Sampling & Direct Dose Rate Survey Guidelines . . ...... 10 01-86 7.3.2 Post-Accident Sampling & Analysis of Potentially High Level Reactor Coolant . . ........... 17 06-27-86

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e i Page 3 Revision Date 7.3.3 Post-Accident Sampling of Contain-ment Atmosphere . .. . . . . . . 16 06-27-86 7.3.4 Movement of Required Chemistry Equipment & Material to the Technical Support Center Counting Room & Mini-Laboratory .... . 4 06-27-86 7.3.5 Post-Accident Sampling of the Auxiliary Building & Drumming Area Vent Stacks Using the Iso-kinetic Stack Sampling System . . 3 04-01-86 7.4 Emergency Equipment 7.4.1 DELETED 7.4.2 DELETED _ , ,

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7.4.3 DELETED 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 DELETED f- 8.1 Personnel Assembly & Accountability .... 6 12-30-85

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Y- 9.1 DELETED 10.1 Firefighting . . . . ... . . . . .... 1 12-30-85 11.0 FIRST AID & MEDICAL CARE 11.1 On-Site First Aid Assistance . . . . . . . . 5 03-22-85 11.2 Injured Person's Immediate Care . .. . .. 3 03-22-85 11.3 Hospital Assistance . . .. . . . . .. . . 5 03-22-85 11.4 DELETED 12.0 REENTRY & RECOVERY PLANNING 12.1 Reentry Procedures for Emergency Operations 5 05-24-85 12.2 Personnel Exposure & Search & Rescue Teams 6 05-24-85 12.3 Recovery Planning . .... . . .. . .. . 1 05-04-84 12.4 Personnel Monitoring Exposure Guidelines . . 4 09-03-85 C

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Page 4 Revision Date 13.0 PRESS 13.1 Crisis Communications . . . . . . . . . . . 5 06-27-86 14.0 COMMUNICATIONS 14.1 DELETED 14.2 Paging System Operation . . . . . . . . . . 7 06-27-86 15.0 TRAINING, DRILLS & EXERCISES 15.1 DELETED 15.2 DELETED 15.3 DELETED 15.4 DELETED 15.5 DELETED 16.0 WISCONSIN ELECTRIC GENERAL OFFICE PROCEDURES 16.1 Nuclear Engineering Notification & Response. . 9 06-27-86 I

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C6-27-86 TABLE OF EPIP FORMS EPIP EPIP Form Title Procedure 01 Emergency Plan Airborne Radiation Survey Record Site Boundary Control Center (11-85) 7.3.1 02 Emergency Plan Survey Record Site Boundary Control Center (08-84) 7.3.1 03 Dose Factor Calculations for Specific Noble Gas Analysis Results (03-81) 7.3.1 04 Status Report on Plant Systems & Controls for Affected Unit (01-83) 6.5 05 RMS Status (Release Point Monitors) (08-84) 6.5 06 RMS Status (Area Type Monitors) (08-84) 6.5 06a RMS Status (Process Monitors) (05-84) 6.5 07 For X/Q Determination (03-85) 1.4 08 Estimated Whole Body & Thyroid Projected Doses (03-85) 1.4 09 Estimated Whole Body Dose Calculation Worksheet for -

Specific Noble Gas Releases (03-85) 1.4 10 Estimated Ground Deposition Calculation Worksheet for Particulate Radionuclide Releases (03-85) 1.4 10a Estimated Population Dose (03-85) f 11 12 Summary of Radiological Dose Evaluation Calculations (03-85)

Incident Report Form (12-85) 1.4 1.4 1.3 13 Status Update Form (12-85) 1.3 14 NRC Event Notification Worksheet (12-85) 1.3 15 Unused 16 Unused 17 Accounting Short Form (07-84) 8.1 18 Assembly Area Roster (03-81) 8.1 19 Unused 20 Technical Support Center Activation Checklist (06-86) 6.5 21 Emergency Operations Facility Activation Checklist (06-86) 6.7 22 Plant & Company Emergency Call List (06-86) Call List Tab 23 Offsite Agency Emergency Call List (06-86) Call List Tab 24 Emergency Response Facility Telephone Directory (06-86) Call List Tab 25 Wisconsin Electric Headquarters Support Personnel Emergency Call List (06-86) Call List Tab 26 Unused 27 Unused 1 28 Unused 29 Unused l

Page 2 EPIP EPIP Forms Title Procedure 30 Reactor Coolant Post-Accident Sampling Analysis Report (06-86) 7.3.2 31 Containment Atmosphere Post-Accident Sampling Analysis Report (06-86) 7.3.3 32 Search & Rescue and Emergency Operations checklist (06-86) 12.2 33 Unused 34 Calculation of Xe-133 Equivalent Release Rates (04-86) 1.8 35 Dose Calculations (09-85) 1.8 36 Unused 37 Unused 0

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EPIP 2.2

_ . MINOR Revision 3 3 1

06-27-86 UNUSUAL EVENT - PLANT AND COMPANY PERSONNEL NOTIFICATION l

1.0 PURPOSE l

1.1 To establish the notification responsibilities and sequence for designated plant personnel; 1.2 To provide notification of corporate office support personnel; and 1.3 To augment plant personnel as necessary during plant conditions classi-  ;

fled as an Unusual Event in accordance with the Emergency Plan Implementing Procedures,

2.0 REFERENCES

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] Necessary phone numbers are found on forms EPIP-22, " Plant Personnel Emer-gency Call List," and EPIP-25, "WE Headquarters Support Personnel Emergency i

Call List."

l 3.0 PRECAUTIONS AND LIMITATIONS 3.1 If unable to contact an individual, continue with the netification of j the other individuals and then attempt to contact the persons who have not been notified.

3.2 All actions and notifications should be appropriately logged on EPIP-22 and/or EPIP-25 as appropriate.

4.0 INITIAL CONDITIONS Unusual Event emergency conditions exist.

5.0 PROCEDURE Key plant personnel may be notified via the pager system. Refer to EPIP 14.2, " Paging System Operation."

5.1 Shift Superintendent 5.1.1 Contact the Duty & Call Superintendent and discuss plant ,

conditions with him. -

5.1.2 Notify the Duty Technical Advisor and discuss plant conditions '.

, with him.

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EPIP 2.2

. Page 2 5.2 Duty & Call Superintendent 5.2.1 If required, contact the Duty & Call Chemistry Supervisor and the Duty & Call Health Physics Supervisor and discuss manpower needs. Ensure that all information and needs are understood.

5.2.2 If required, contact other Duty & Call Superintendents and needed plant and company personnel (phone numbers are listed on form EPIP-22, " Plant Personnel Emergency Call List")

5.2.3 Contact the Emergency Support Manager (phone numbers are in form EPIP-25, "WE Headquarters' Support Personnel Emer-gency call List") and provide information concerning plant status as necessary.

5.3 Duty & Call Chemistry Supervisor If required, contact and notify Chemistry personnel concerning plant j status and required actions.

5.4 Duty & Call Health Physics Supervisor

(' r*S"ir'd * "t*** ""d " "I'Y "*a th physi 5 Personnel concerning s_ plant status and required actions. ,

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EPIP 3.2

. MINOR Revision 3 06-27-86 ALERT - PLANT AND COMPANY PERSONNEL NOTIFICATION 1.0 PURPOSE 1.1 To establish the notification responsibilities and sequence for desig-nated plant personnel; 1.2 To provide notification of corporate office support personnel; and 1.3 To augment plant human resources as necessary during plant conditions classified as an Alert in accordance with the Emergency Plan Implemen-ting Procedures.

2.0 REFERENCES

Necessary phone numbers are found on form EPIP-22, " Plant Personnel Emer-gency Call List," and EPIP-25, "WE Headquarters Support Personnel Emergency Call List."

3.0 PRECAUTIONS AND LIMITATIONS 3.1 If unable to contact an individual continue with the notification of the other individuals and then attempt to contact the persons who have not been notified.

3.2 All actions and notifications should be appropriately logged on forms EPIP-22, and/or EPIP-25 as appropriate.

4.0 INITIAL CONDITIONS Alert emergency conditions exist. -

5.0 PROCEDURE Key plant personnel may be notified via the pager system. (Refer to EPIP 14.2, " Paging System Operation.")

5.1 shift Superintendent 5.1.1 Contact the Duty & Call Superintendent and discuss plant conditions with him.

5.1.2 Notify the Duty Technical Advisor and discuss plant condi-tions with him.

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EPIP 3.2 Page 2 5.2 Duty & Call Superintendent 5.2.1 Contact a Secondary Duty & Call Superintendent. Inform him an Alert has been declared. Discuss manpower needs and assure that he performs Section 5.3 of this procedure.

5.2.2 Contact the Duty & Call Health Physics Supervisor (phone numbers listed on form EPIP-22, " Plant Pe rsonnel Emergency Call List"). Inform him that an Alert has been declared.

Discuss manpower needs.

5.2.3 contact the Duty & Call Chemistry Supervisor (phone numbers listed in form EPIP-22, " Plant Personnel Emergency Call List"). .

Inform him that an Alert has been declared. Discuss manpower needs.

5.3 Secondary Duty & Call Superintendent 5.3.1 Contact the Emergency Support Manager (phone numbers in -

EPIP-25, " Wisconsin Electric Headquarters Support Personnel Emergency Call List,") and provide information concerning plant status as necessary.

i /' 5.3.2 Contact other Duty & Call Superintendents and needed plant

( ' personnel listed on EPIP-22, " Plant Personnel Emergency Call List," and inform them an Alert has been declared. Discuss manpower needs with the appropriate supervisors.

5.4 Notified Supervisory Personnel including the Duty & Call Chemistry and Duty & Call Health Physics Supervisors Contact and notify personnel under your supervision concerning plant status and actions expected of them.

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EPIP 4.2

, MINOR Revision 3 06-27-86 l SIT! EMERGENCY - PLANT AND COMPANY PERSONNEL NOTIFICATION 1.0 PURPOSE I

1.1 To establish the notification responsibilities and sequence for desig-nated plant supervisory personnel, 1.2 To provide notification of corporate office support personnel; and 1.3 To augment plant human resources as necessary during plant conditions classified as a Site Emergency in accordance with the Emergency Plan implementing procedures.

2.0 REFERENCES

Necessary phone numbers are found on forms EPIP-22, " Plant Personnel Emergency Call List," and EPIP-25, "WE Headquarters Support Personnel Emergency Call List."

3.0 PRECAUTIONS AND LIMITATIONS 3.1 If unable to contact an individual continue with the notification of the other individuals and then attempt to contact the persons who have not been notified.

3.2 All actions and notifications should be appropriately logged on forms EPIP-22, and/or EPIP-25 as appropriate.

4.0 INITIAL CONDITIONS Site Emerg'ency conditions exist.

5.0 PROCEDURE Key plant personnel may be notified via the pager system. (Refer to EPIP 14.2, " Paging System Operation." )

5.1 Shift Superintendent 5.1.1 Contact the Duty & Call Superintendent and discuss plant l conditions with him.

5.1.2 Assure that the Duty Technical Advisor is aware of the Site

s. Emergency.

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EPIP 4.2

. Page 2 5.2 Duty & Call Superintendent 5.2.1 Contact a secondary Duty & Call Superintendent. Inform him that a Site Emergency has been declared. Discuss manpower needs and assure that he performs Section 5.3 of this procedure.

5.2.2 Contact the Duty & Call Health Physics Su;pervisor (phone numbers listed on form EPIP-22, " Plant Personnel Emergency call List"). Inform him that a Site Emergency has been declared. Discuss manpower needs.

5.2.3 Contact the Duty & Call Chemistry Supervisor (phone numbers listed on form EPIP-22, " Plant Personnel Emergency Call List"). Inform him that a Site Emergency has been declared.

Discuss manpower needs.

5.3 Secondary Duty & Call Superintendent 5.3.1 Contact the Emergency Support Manager (phone number in EPIP-25, "WE Headquarters Support Personnel Emergency Call List,") and provide information concerning plant status as necessary.

5.3.2 Contact other Duty & Call Superintendents and needed personnel listed on form EPIP-22, " Plant Personnel Emergency Call List," and inform them that a Site Emergency has been declared. Discuss manpower needs with appropriate supervisors.

5.4 Notified Supervisory Personnel Including the Duty & Call Chemistry and Duty & Call Health Physics Supervisors Contact and notify personnel under your supervision concerning plant status and actions expected of them.

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. MINOR

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Revision 3 06-27-86 GENERAL EMERGENCY - PLANT AND COMPANY PERSONNEL NOTIFICATION 1.0 PURPOSE 1.1 To establish the notification responsibilities and sequence for designated plant personnel; 1.2 To provide notification of corporate office support personnel; 1.3 To augment plant human resources as necessary during plant conditions classified as a General Emergency in accordance with the Emergency Plan implementing procedures.

2.0 REFERENCES

Necessary phone numbers are found on forms EPIP-22, " Plant Personnel Emergency Call List," and EPIP-25, "WE Headquarters Support Personnel Emergency Call List."

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( 3.0 PRECAUTIONS AND LIMITATIONS 3.1 If unable to contact an individual continue with the notification of the other individuals and then attempt to contact the persons who have not been notified.

3.2 All actions and notifications must be appropriately logged on forms EPIP-22 and/or EPIP-25 as appropriate.

4.0 INITIAL CONDITIONS General Emergency conditions exist.

5.0 PROCEDURE l

Key Company personnel may be notified via the pager system. (Refer to l EPIP 14.2, " Paging System Operation.")

5.1 Shift Superintendent 5.1.1 Contact the Duty & Call Superintendent and discuss plant conditions with him.

5.1.2 Assure that the Duty Technical Advisor is aware of the General Emergency.

EPIP 5.2

, Page 2 5.2 Duty & Call Superintendent 5.2.1 Contact a seccndary Duty & Call Superintendent. Inform him that a General Emergency has been declared. Discuss man-power needs and assure that he performs Section 5.3 of this procedure.

5.2.2 Contact the Duty & Call Health Physics Supervisor (phone numbers listed in form EPIP-22, " Plant Personnel Emergency call List"). Inform him that a General Emergency has been declared. Discuss manpower needs.

5.2.3 contact the Duty & Call Chemistry Supervisor (phone number listed in form EPIP-22, " Plant Personnel Emergency Call List."). Inform him that a General Emergency has been declared. Discuss manpower needs.

5.3 Secondary Duty & Call Superintendent 5.3.1 Contact the Emergency Support Manager (phone numbers in EPIP-25, "WE Headquarters Support Personnel Emergency Call l List,") and provide information concerning plant status as necessary. -

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5.3.2 Contact other Duty & Call Superintendents and needed plant personnel listed on form EPIP-22, " Plant Personnel Emergency Call List." Inform them that a General Emergency has been declared. Discuss manpower needs with the appro-priate supervisors.

5.4 Notified Supervisory Personnel Including the Duty & Call Chemistry And Duty & Call Health Physics Supervisors contact and notify personnel under your supervision concerning plant status and actions expected of them.

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e EPIP 6.5

. MINOR Revision 8 06-27-86 TECHNICAL SUPPORT CENTER & OPERATIONS SUPPORT CENTER ACTIVATION 1.0 PURPOSE 1.1 To provide instructions for the activation of the technical support 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 - TECHNICAL SUPPORT MANAGER 2.1 Set up tables as shown 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.

I 2.2 Install phones from the technical support center storage cabinets in 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-t ting mode by implementing Section 5.0.

EPIP 6.5

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

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

2.10 Turn on the sample pump for the iodine and noble gas monitors per Section 9.0.

j 3.0 ACTIVATION OF TSC PERSONNEL (Site Manager or Technical Support Manager) 3.1 Site Manager or Technical Support Manager contact appropriate

! personnel to fill the following positions in the TSC:

Checkoff Site Manager j

Technical Support Manager

  • Plant Operations Manager chemistry Director System Analysis / Procedural l' _

Support Coordinator

/ Core Physics coordinator j (_ Health Physics Director 3.2 Formally assume responsibility for offsite radiological assessment, l

dose projection and offeite protective action recommendation (from ,

l, the control room) as soon as possible after arriving at the TSC by completing Form EPIP-20, " Technical Support Center Activation Check-t list." (Attached) t , 3.3 Assume respoasibility from the control room for communications with offsite agencies until relieved by EOF activasion.

3.4 When the EOF is capable, offsite protective action recommendations I

and 6ffsite dose projections will be transferred from the TSC to the EOF.

4.0 DATA LOGGER OPERATION I

4.1 Push the start button on the data logger. Enter the correct date and time on the printout from the data logger. The designations for each of the 37 channels are contained in Attachment 6.5-2.

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EPIP 6.5

. Page 3 4.2 The conversion of incore thermocouple MV to degrees Fahrenheit with the reference junction at 160' is accomplished by use of the incore thermocouple table (see Attachment 6.5-3).

4.3 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).

5.0 EMERGENCY VENTII.ATION SYSTEM 5.1 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.

3 One is adjacent to the normal intake on the east wall of the techni-l cal support center building and the other is on the north wall of the -

Unit 2 turbine hall 1.

i 5.2 To shift the heating, ventilating and air conditioning system from the normal to emergency mode:

5.2.1 Turn the auto /cff/ occupied switch on Panel M-1 to the occu-pied position. See Attachment 6.5-7 for location of Panel M-1.

5.2.2 Turn the normal / emergency control switch on Panel h-1 to the em.ergency position.

5.2.3 Select the north or south (east) e.nergency intake depending on meteorological conditions. Select the upwind intake .

duct.

6.0 TECHNICAL SUPPORT CENTER AUXILIARY AIR CONDITIONING 6.1 Turn on compressor CH2 on the west wall of El.18.5' of the technical support center building (see Attachment 6.5-7).

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

7.0 EMERGENCY POWER 7.1 The power source for the technical support center is 1B01 480 V. See Attachment 6.5-8 for the main disconnect location.

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EPIP 6.5 l

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I i 7.2 The emergency power supply is available by operation of the auxiliary Diesel for SG and the auto bus transfer switch. See Attachment 6.5-8 for the emergency transfer switch location.

8.0 Plant Status (DTA Assigned to Control Room) 8.1 Complete Form EPIP-04 attached by evaluating and monitoring available control room instrumentation as appropriate.

i 8.2 Forward completed form to the technical support center after review by

, the Shift Superintendent.

S.3 Complete Forms EPIP-05, 06 and 06b as appropriate to compensate if TSC RMS failure.

j 9.0 ACTIVATION OF IODINE & NOBLE GAS MONITORS 9.1 Coordinate with the Health Physics Director to have the iodine and noble gas sample pump started. The pump is on the west side of the -

El. 18.5' mechanical equipment room. Ensure that a new charcoal canister is installed and that the initial sample flow rate and start time are recorded, f' 9.2 Interpretation of RMS readouts l

' 9.2.1 The concentration of noble gas is determined by multiplying the observed countrate on the readout labeled "RE-238" by l the calibration constant posted adjacent to the meter. The

units are pCi/cc Xe-133 dose equivalents.
  • 9.2.2 The iodine activity in the charcoal cartridge is determined i

by multiplying the observed countrate on the readout labeled -

"RE-237" by the calibration constant posted adjacent to the meter. The units are pCi I-131 dose equivalents.

I 9.2.3 To convert the iodine activity into a concentration, calculate the volume of air that passed through the filter.

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j The concentration of iodine is approximately the activity on the filter (pci) divided by the total volume (cma ) for senpling periods less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> assuming no short-lived isotopes are present.

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EPIP 6.5

, Page 5 NOTE: FOR LONGER SAMPLING PERIODS AND WHEN SHORT-LIVED ISOTOPES ARE EXPECTED TO BE PRESENT, THE FOLLOWING FORMULA MAY BE USED TO CALCULATE THE IODINE CONCENTRATION.

s C _ AAe

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F p(1-e s)

Where: Units C = concentration in air pCi/cc F = sample volume cc A = decay constant, 0.693/ Tis min ~1 A = total activity on filter pCi t = elapsed time from sample stop to count start min t* = total sample time min p = filter collection efficiency 9.2.4 Any changes to the alarm setpoints shall be made in accordance with the Radiation Monitoring System Alarm Setpoint Response Book (RMSASRB), kept in the control room.

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,_ . Page 6 ATTAODENTS 6.5-9 & 6.5-10 The purpose of Attachments 6.5-9 through 6.5-10 is to provide guidelines to aid in evaluating in-pinat radiation dose rate estimates and the potential for airborne activity using the installed RMS instrumentation.

Area monitors calibrated in mrem / hour provide direct indications of area radiation dose rates. Process-type monitors calibrated in counts per-minute may be used to estimate area dose rates by converting the readout in counts-per-minute to mrem / hour. The conversion factor is approximately one mrem / hour for 3 each 1,000 cpm indicated.

Vent stack monitors which measure noble gas discharges from plant areas should always be considered to indicate potential airborne activity.

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ATTACHMENT 6.5-1 TSC/HP

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cend. Blackboard lay I u _

j 3 System ,

Analysis /

o y Procedural TABLE Site Manager l

!. .$ Support n UN " Coord.

Plant Ops. $ " II l

veu TABLE Manager f.#

ma g

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DESK 4 A'erial g'

!', safety DESK c j;.

i Parameter g . g Display g .

j j w

  • Technical q j- NAWAS, 2-Digit yg i Support Ringdown Phone j t j Manager I

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!f Re Phone i Storage TABLE TABLE Cabinet ]

OSC

, Radio Com::2unications r - -- --- - m 1

/ Console

  • j s

Chem /HP TABLE i Supervisor

l Personnel Status 1

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'l p Core Physics Coord.

TABM TABE Consold I i

! DESK Data Proc. Coord. l SBCC Ringdown Environmental Dose Plot Status Map

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ATTACHMENT 6.5-2

(

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

1 mv Active 12) Unit 1 Reference )

2 av Active 13) RTD )

3 mV Active 18) Junction Box "A"

)

Unit 1 Incore 4 mV Active 22) Thermocouples

)

5 mV Active 26) Unit 1 Reference )

6 my Active 29) RTD )

7 mV Active 36) Junction Box "B" )

8 mv Active 3) )

9 mv Active 12) Unit 2 Reference ) -

10 mv Active 13) RTD )

11 mV Active 18) Junction Box "A" )

Unit 2 Incore

! ., 12 mV active 22) Thermocouples

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- 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 RTD Junction Box "A" 17 *F Active Unit 1 Reference RTD Junction Box "B"

'F Active 13 Unit 2 Reference RTD Junction Box "A" 19 'T Active Unit 2 Reference RTD Junction Box "B" 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" l i

23 gpm Active Unit 1 SI Flow Train "B" I 24 ft Unit 1 Containment Sump Level 26 *v Active Unit 1 Containment Purge Stack Ims-II Ch #3 27 gpa Unit 2 Auxiliary Feed Flow "A" SG 28 gpa Unit 2 Auxiliary Feed Flow "B" SG 29 gpm Active Unit 2 SI Flow Train "A" 30 gpm Active Unit 2 SI Flow Train "B" 31 ft Unit 2 Containment Sump Level 1 l

33 V Active Unit 2 Containment Purge Stack RMS-II Ch #4 34 V Active Drunning Area Vent Stack RMS-II Ch #2

! 35 V Active Combined 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 6

- _ _ _ _ - - - - , - - - - _ _ . ,,_.,...-,m._,-, m w, ---m__-..--*w -

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.3 POINT DEAu NUCLEAR PLANT - INCORE T/C TABLE - REFL .dCE JUNCTION AT 160. DEG F -

l MV DEG F MV DEO F MV DEG F HV DEG F MV DEG F NV DEG F 0.00 152. 7.60 497. 15.20 824. 22.00' 1146. 30.40 1472. 30:00 1H11.

3 0.20 161. 7.80 505. 15.40 033. 23.00 1155. 30.60 1481. 30.20 1821.

0.40 170. 0.00 514. 15.60 841. 23.20 1163. 30.00 1490. 30.40 1829.

I 0.60 100. 8.20 523. 15.00 050. 23.40 1171. 31.00 1498. 30.60 1039.

l 0.00 109. D.40 532.* 1,6 . 0 0 050. 23.60 1180. 31.20 1507. 30.80 1848.

1.00 198. 0.60 540. 16.20 067. 23.80 1188. 31.40 1516. 39.00 1857, 1.20 200. 0.00 549. 16.40 875. 24.00 1197. 31.60 1524. 39.20 1867.

1.40 217. 9.00 558. 16.60 883. 24.20 1205. 31.80 1533. 39.40 1876. -

1.60 227. 9.20 567. 16.80 892. 24.40 1214. 32.00 1542. 39.60 1085.

1.00 236. - 9.40 576. 17.00 901. 24.60 1223. 32.20 1551. 39.80 1894.

2.00 245. 9.60 584. 17.20 909. 24.00 1231. 32.40 1560. 40.00 1904.

2.20 254. 9.80 593. 17.40 918. 25.00 1240. 32.60 1568. 40.20 1913. ,

1 2.40 263. 10.00 602. 17.60 924. 25.20 1240. 32.00 1577. 40.40 1922.

2.60 272. 10.20 610. 17.00 935. 25.40 1256. 33.00 1584. 40.60 1932.

2.00 282. 10.40 618. 18.00 943. 25.60 1265. 33.20 1595. 40.00 1941.

3.00 290. 10.60 627. 18.20 951. 25.80 1274. 33.40 1604. 41.00 1950.

3.20 300. 10.80 636. 18.40 960. 26.00 1282. 33.60 1613. 41.20 1960.

3.40 309. 11.00 645. 18.60 968. 26.20 1291. 33.80 1621. 41.40 1969.

3.60 310. 11.20 653. 18.80 977. 26.40 1299. 34.00 1631. 41.60 1979.

3.00 327. 11.40 662. 19.00 985. 26.60 1308. 34.20 1639. 41.00 1988.

j 4.00 336. 11.60 671. 19.20' 993. 26.00 1314. 34.40 1649. 42.00 1998.

i 4.20 345. 11.00 679. 19.40 1002. 27.00 1325. 34.60 1657. 42.20 2008.

4 4.40 354. 12.00 688. 19.60 1010. 27.20 1334. 34.80 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 1028. 27.60 1351. 35.20 1684. 42.00 2036.

5.00 381. 12.60 714. 20.20 1036. 27.80 1359. 35.40 1693. 43.00 2045. p 5.20 390. 12.00 722. 20.40 1045. 28.00 1368. 35.60 1702. 43.20 2055. y i 5.40 399. 13.00 730. 20.60 1053. 28.20 1377. 35.00 1711. 43.40 2065. g j 5.60 408. 13.20 739. 20.80 1061. 28.40 1385. 36.00 1720. 43.60 2074. E 5.80 417. 13.40 747. 21.00 1070. 28.60 1394. 36.20 1729. 43.80 2004.

6.00 g

426. 13.60 756. 21.20 1078. 28.00 1403. 36.40 1738. 44.00 2094.

i 6.20 434. 13.80 765. 21.40 1087. 29.00 1411. 36.60 1748. 44.20 2103.  ?

) 6.40 444. 14.00 773. 21.60 1095. 29.20 1420. 36.80 1756. 44.40 2113. Y

6.60 452. 14.20 782. 21.80 1103. 29.40 1429. 37.00 1766. 44.60 2123.
6.80 462. 14.40 790. 22.00 1112. 29.60 1437. 37.20 1775. 44.80 2133.

J 7.00 470. 14.60 799. 22.20 1120. 29.80 1446. 37.40 1784. 45.00 2142.

] 7.20 479. 14.00 807. 22.40 1129. 30.00 1455. 37.60 1793. 45.20 2152.

7.40 408. 15.00 816. 22.60 1138. 30.20 1443. 37.80 1802. 45.40 2162.

i '

(_____.____.... _ _ _ _ _

A'I"rACHMEN'S 6. 5-4 i

DRUMMING AREA VENT STACK RMS-II CH #2 &

COMBINED AIR EJECTOR DISCHARGE RMS-II CH #5 1

VOLTAGE TO R/HR CONVERSION TABLE i RANGE 1 to 10" R/HR t

t

] Volts Units R/hr 0 0.001 0.1 0.00135 j 0.2 0.001847 5

0.3 0.002511 j 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 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 1 2.8 5.411695

{

2.9 7.356422 3.0 10.0 l l

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ATTACHMERT 6.5-5 i

UNIT 1 RMS-II CF #3 & UNIT 2 RMS-II CH #4 '

CON'J\INMENT PURGE STACKS VOLTAGF TO .t/HR CONVERSION TABLES RANGE 10 ' 'IO 10' R/HR Volts Units - R/HR O. 0.1 0.1 .135 0.2 .184 0.3 .251 0.4 .341

  • 0.5 .464 i 0.6 .630 0.7 .857 O.8 1.165 0.9 1.584

('" l.

1.1 2.154 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 l 2.3 116.591  !

2.4 158.489 l 2.5 215.443 2.6 292.864 2.7 398.107 2.8 541.169 2.9 735.642

3. 1000.

i

\

ATTACHMENT 6.5-6 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-' '!O 10' R/HR

, Volts Units - R/HR O. 0.01 0.1 .013 0.2 .018 0.3 .025 i 0.4 .034 0.5 .046 0.6 .063 0.7 .085 0.8 .116 4 0.9 .158 -

1. .215 1.1 .292 l.2 .398 1.3 .541

[-

1.4 l.5

.735 1.

1.6 1.35 1.7 1.847 .

, 1.8 2.511 1 1.9 3.414 j 2. 4.641 j 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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ATTACHMENT 6.5-9 LISTING OF RMS AREA MONITORS BY PLANT LOCATION Monitor Location Indication '

RE-101 Control Room Aest yall of control room. Shifts control room ventilation to 100%

recirculation.

1(2)RE-102 Containment El. 66' near access hatch on east Provides dose rates within containment i Low Range side, around access hatch.

RE-103 Chemistry Lab East wall of chemistry lab near Provides indication of dose rates in counting room door, chemistry lab and associated hallways.

j 1(2)RE-104 Charging Pump Mounted on west side of shield wall Indicates dose rates in hallways east of Room Low Range east of cubicles on El. 8' of aux, charging pump cubicles.

building.

RE-105 Spent Fuel Pit Mounted on railing just northeast Provides indication of dose rates in the l

Low Range of spent fuel pit on El. 66' of aux. vicinity of the spent fuel pit. This building. monitor is affected by high radiation levels in containment.

i 1(2)RE-106 Primary Side Mounted on west wall, towards north When sampling system is in operation, it Sample Room Low Range corner of sample room on El. 26' of indicates dose rate inside sample room.

aux. building.

1(2)RE-107 Seal Table Mounted on wall just above seal table Provides an indication of general area

! on El. 46' of containment. dose rate near seal table.

j RE-108 Drumming Station Mounted inside the Atcor waste Provides dose rate indication within the processing cubicle. drumming station.

I 4

1(2)RE-109 Failed Fuel Mounted on south wall near east Provides an indication of failed fuel by corner of primary side sample room monitoring the primary coolan'. sample on El. 26' of aux. building. activity.

Attachment 6.5-9, Cont'd.

Monitor Location Indication l RE-110 SI Pump Room Located on north wall just west of Provides an indication of the dose rate j passageway in SI pump room. in general area of SI pumps.

RE-111 C59 Panel Mounted on top of C59 instrument Provides general area dose rate near C59 panel'on El. 26' of aux. building. panel. .

3 RE-112 Central PAB Mounted on north wall just east of Indicates general area dose rate on El. 8'

pipeway No. 3 on El. 8' of aux. of aux. building.

building.

RE-113 El. -19' Auxiliary Mounted in general area of El. -19' Provides an indication of the dose rate in Building of aux. building. aux. building sump and general area of El. -19'.

RE-116 Letdown Valve Mounted by north entrance to valve Indicates general area dose rate in letdown Gallery gallery on El. 26' of aux. building. valve gallery.

1(2)RE-134 Charging rump Mounted next to 1(2)RE-104 on west Provides an indication of general area dose Room High Range ,

side of shield wall, east of cubicles rates in the event low-range monitor pegs on El. 8' of aux. building. offscale high.

RE-135 Spent Fuel Pit Mounted next to 1(2)RE-105 on railing Provides an indication of general area High Range ,. just northeast of spent fuel pit on dose rates in the event low-range g El. 66' of aux. building. monitor pegs offscale high. '

1(2)RE-136 Primary Side Mounted next to 1(2)RE-106 on west Provides an indication of general area V Sample Room High Range wall, towards north corner of sample dose rates in the event low-range y room on El. 26' of aux. building. monitor pegs offscale high. 1 RE-140 SI Pump Room High Mounted next to RE-110 on north Provides an indication of general areac Range' wall just west of passageway in dose rates in the event low-range SI pump room, monitor pegs offscale high. '

e

.m

)

ATTACHMENT 6.5-10 LISTING OF RMS PROCESS MONITORS BY PLANT LOCATION Monitor Location Indication

' The following process monitors may be used in evaluating potential airborne contaminatica levels within.the plant.

Whenever there are indications of high airborne activity being discharged through a vent stack, there

is always the possibility of in-plant airborne contamination.
  • 1RE-215/2RE-215 Steam Air West side of turbine building Ejector Monitor. El. 46'.

Indicative of steam generator primary-to-secondary leakage. May be indicative of potential radiation exposure sources within turbine building.

1(2)RE-211 Containment Located in cubicle on east side of Air Particulate Indicates particulate activity inside con-El. 52' of containment facade. tainment, facade, or purge exhaust stack.

l There are no control functions associated with 1(2)RE-211B Containment Located next to 1(2)RE-211 in Background cubicle. Provides background activity for both 1(2) RE-211 and 1(2)RE-212 for background subtraction, if used.

1(2)RE-212 Containment Located in series with 1(2)RE-211 Noble Gas Provides indication of containment noble i

on detector skid in the cubicle on gas activity. Isolates containment El. 52' of containment facade. ventilation upon high activity.

RE-214 Aux. Building Vent Mounted on aux. building exhaust Stack Noble Gas Indicates any gaseous release from spent stack at about El. 80' in Unit 1 fuel pit area and the drumming station.

< facade just south of elevator. Indicative of potential aux. building air-borne activity. Shuts the vent gas release valve and initiates aux. building exhaust filtration.

1 5

4 9

l

.O Attachment 6.5-10, cont'd.

l  !

j Monitor Location Indication l

1(2)RE-215 Condenser Air Mounted on west wall of El. 46' in Indicative of steam generator primary-to-Ejector Noble Gas turbine hall between MSR's. secondary leak. May be indicative of a potential airborne radiation exposure in turbine hall.

1(2)RE-216 Containment Fan In Unit 1, located west and slightly Provides indication of potential contamipa' ion j Coolers Liquid Process south of C59 panel. In Unit 2, of cooling water.

located west and slightly north of C59 panel.

1(2)RE-216B Containment Located next to 1(2)RE-216 monitor. Provides background data for the 1(2)RE-216 Fan Coolers Background liquid process monitor, if used.

1(2)RE-217 Component In Unit 1, located in overhead Cooling Water Liquid Provides indication of component cooling just north of stairs going from water contamination. Shuts component Process El 8' of aux. building to C59 cooling water surge tank vent.

panel area. In Unit 2, located in overhead just west of Unit 2 '

component cooling water pumps.

4 i

RE-218 Waste Disposal Located on east wall of waste con-System Liquid Process Monitors waste condensate activity being dis-densate cubicle across from component charged. Upon exceeding high level setpoint, cooling water pump on El. 8' of aux. discharge of waste condensate is secured.

building.

RE-2188 Waste Disposal Located next to RE-218 monitor.

System Background Provides background activity level for RE-218 liquid process monitor, if used.

1(2)RE-219 Steam Generator Located outside each primary side Provides an indication of steam generator Blowdown Liquid Process sample room on El. 26' of aux.

building.

blowdown activity. Secures steam genrator blowdown and blowdown tank outlet valves, and steam generator s:mple valves.

1 i

e

I

) 9 Attachment 6.5-10, Cont'd.

j Monitor Location Indication 1(2)RE-219B Steam Generator Located next to 1(2)RE-219 Provides background activity level for 4

Blowdown Background monitor. 1(2)RE-219 liquid process monitor, if used.

~

i 4

RE-220 Spent Fuel Pit Heat Located on El. 46' of aux. building Provides an indication of service water con-Exchanger Service Water on north wall just west of door to tamination from a spent fuel pit heat -

Liquid Process Unit 2 containment facade, exchanger tube leak.

)

, RE-220B Spent Fuel Pit Heat Located next to RE-220 monitor. Provides background activity level for i Exchanger Service Water RE-220 liquid process monitor, if used.

1 Background i

RE-221 Drumming Area Vent Located in exhaust ducting above Indicates noble gas activity released from Stack Noble Gas crumming area SPING in northwest spent fuel pit and drumming area. May be I

corner of Unit I facade. indicative of a potential aux. building airborne release.

1(2)RE-222 Steam Generator Located on El. 26' of aux. building Provides an indication of activity level in.
Blowdown Tank Outlet on east side of steam generator blow-Liquid Process blowdown tank. Secures blowdown of steam down tank. generators and closes blowdown tank outlet valves.

RE-223 Waste Distillate Mounted on east side of "C" component Monitors activity of waste distillate during Discharge Liquid Process cooling water heat exchanger on discharge. Secures discharge valves upon j El. 46' of aux. building, exceeding setpoint.

RE-223B Waste Distillate Located next to RE-223 monitor. Provides background activity level for RE-223 Discharge Background liquid process monitor, if used.

I

RE-224 Gas Stripper Vent Located in northeast corner of Indicates activity of gaseous release from

, Stack Noble Gas Unit 2, El. 26' containment facade letdown gas stripper building.

by exhaust duct.

, RE-225 Combined Air Ejector Located above door on El. 46' of Indicative of primary-to-secondary leak in Low-Range Noble Gas turbine hall leading to I&C office. steam generators.

4 I

I

. .5-10, cont'd.

Monitor Location Indication RE-226 Combined Air Ejector Located adjacent to RE-225 low-range Provides an indication of the noble gas High-Range Noble Gas noble gas monitor. activity in combined air ejector discharge in the event RE-225 monitor is pegged off-

~

scale high.

1(2)RE-229 Service Water For Unit 1, located on El. 8' of Monitors activity of service water discharge.

Discharge Process aux. building in vent area. For Unit 2, located in aux. feed pump room on east side of tunnel.

1(2)RE-2298 Service Water Located adjacent to 1(2)RE-229 liquid Provides background activity level for Discharge Background process monitor. the 1(2)RE-229 monitor, if used.

RE-230 Retention Pond Located on El. 8' of turbine hall Monitors activity level in retention pond Discharge Liquid Process outside entrance to water treatment. effluent.

RE-230B Retention Pond Located adjacent to RE-230 liquid Provides background activity level for Discharge Background process monitor. RE-230 liquid monitor.

1(2)RE-231 - Line "A" Located on El. 88' of containment Monitors activity of steam released.

1(2)RE-232 - Line "B" facade in the area of atmospheric Steam Line Atmospheric relief valves - one per steam Release generator.

RE-234 Control Room Iodines Located on top of control room Monitors iodine activity in control room.

building on El. 46' of turbine hall. Initiates 100% recirculation (Mode 4) of control room ventilation upon exceeding setpoint.

RE-234B Control Room Located adjacent to RE-234 iodine Provides background activity level for Background monitor. RE-234 iodine monitor.

c Attachment 6.5-10, Cont'd.

Monitor Location Indication RE-235 Control Room Noble Located adjacent to RE-234 iodine Monitors noble gas activity in control room.

Gas monitor. Initiates 100% recirculation (Mode 4) of control room ventilation upon exceeding setpoint.

RE-237 Technical Support Located ?7 ductwork on El. 18.5' Monitors iodine activity in the TSC air Center Iodines of TSC building, in northwest duct.

corner.

RE-237B Technical Support Located adjacent to RE-237 iodine Provides background activity for RE-237 Center Background monitor. monitor.

RE-238 Technical Support Located adjacent to RE-237 iodine Monitors the noble gas activity in TSC Center Noble Gas monitor, air duct.

1(2)RE-305 SPING Located in unit rod drive room. Monitors noble gas activity in unit Unit Containment containment purge exhaust.

Purge Exhaust Low Range Gas .

1(2)RE-307 SPING Located in unit rod drive room. Monitors noble gas activity in unit Unit Containment containment purge exhaust.

Purge Exhaust Mid Range Gas 1(2)RE-309 SPING Located in unit rod drive room. Monitors noble gas activity in unit Unit Containment containment purge exhaust.

Purge Exhaust High Range Gas RE-315 SPING Unit I rod drive room. Monitors noble gas activity in the Auxiliary Building auxiliary building vent.

Vent Low Range Gas

rh i

. .5-10, cont'd.

Monitor Location Indication RE-317 SPING Unit I rod drive room. Monitors noble gas activity in the Auxiliary Building auxiliary building vent.

Vent Mid Range Gas .

RE-319 SPING Unit I rod drive room. Monitors noble gas activity in the Auxiliary Building auxiliary building vent.

Vent High Range Gas RE-325 SPING Drumming area vent fan area. Monitors noble gas activity in the Drumming Area Vent drumming area vent.

Low Range Gas RE-327 SPING Drumming area vent fan area. Monitors noble gas activity in the Drumming Area Vent drumming area vent.

Mid Range Gas i

EPIP 6.7 MINOR

(~

~

! Revision 4

, 06-27-86 l

r

EMERGENCY OPERATIONS FACILITY ACTIVATION

} 1.0 PURPOSE j 1.1 To provide instructions for the activation of the emergency operations 1

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

4 1.2 To outline the emergency operations facility ventilation system operation in the event of high airborne activity.

t 2

2.0 ACTIVATION OF EMERGENCY OPERATIONS FACILITY 2.1 Set up tables as shown on Attachment 6.7-1. They may be obtained from rooms adjacent to the operations area. .

2.2 Install phones, which may be found in the NRC office, in the appropriate areas as shown on Attachment 6.7-1.

, 2.3 Confirm that all phones operate by noting if dial tone is present when

\s the receiver is lifted. Confirm that the numbers listed on the face of the phone matches the number on the wall jacks.

2.4 Install telecopier (obtain from HP office in the extension building).

J 2.5 Distribute paper and pencils to each table. I I 2.6 Distribute one copy each of the Emergency Plan and EPIP's to the table in front of the chalk board and the table near the dose plotting map (see Attachment 6.7-1). l

, 2.7 Shift the ventilation system from normal to the emergency operating

mode per Section 4.2.

2.8 Turn on the sample pump for the iodine and noble gas monitors per Section 8.0.

3.0 ACTIVATION OF EOF PERSONNEL 3.1 Health Physics Personnel See EPIP 7.2.1, " Activation of Health Physics Facilities at Emergency Operations Facility," for activation of health physics personnel.

2 I

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I I

EPIP 6.7 Page 2 f -

l i

i

! 3.2 Site Manager j 3.2.1 Personnel to f.ll the following positions have not been e

contacted, proceed to do so.

Emergency Support Manager Rad / Con Waste Manager 2-Duty Technical Advisors 3.2.2 If any followup data is available which may be of help to offsite agencies, have that information relayed to those agencies.

3.3 Emergency Support Manager 3.3.1 Assume responsibility for offsite radiological assessment,  !

, dose projection and offsite protective action recommendations as soon as the EOF is staffed sufficiently to take that 1

responsibility. Formalize the transfer of responsibilities by using Form EPIP-21, " EOF Activation Checklist."

(Attached) 3.3.2 Assume responsibility from the TSC, for status update com-

munications with offsite agencies as soon as able.

1 o I \- 3.4 Rad / Con Waste Manager Provide dose projections, offsite survey direction, and offsite 4

' protective action recommendations to the appropriate emergency or,ganization personnel.

J q 4.0 EMERGENCY VENTILATION SYSTEM 1

4.1 The EOF heating and ventilation system has a normal and emergency operation mode. Under all modes of operation any fresh air is taken in from a vent on the south end of the west wall of the building.

The intake air under normal operation is coarsely and electrostatically

filtered.

! In the ecergency mode, a minimum of outside air is taken in and

! a high efficiency particulate air filter is added to the filter j media.

I j 4.2 To shift the heating, ventilating and air conditioning system from normal to emergency mode, manually select the emergency position of j switch S3 on control panel M1 located on the south wall of the

] mechanical equipment room. Access to this room is obtained from the men's locker room.

J 1

EPIP 6.7 Page 3 .

(

5.0 EOF ?OWER SUPPLY Power supply to the EOF is obtained from Wisconsin Public Service Corporation distribution feeder. In case of total power failure, call Wisconsin Public Service Corporation. See form EPIP-23, "Offsite Agency Emergency Call List."

6.0 EOF ANNUNCIATOR PANEL 6.1 The annunciator panel monitors 8 parameters in the building. The control room will receive an alarm upon annunciation of any of the 8 alarms.

6.2 Alarms " holding tank high level" and " dosing tank high level" will announce upon tank high level. The holding tank must be pumped by a contractor. The dosing tank has an internal pump which pumps the contents to the mound septic system.

6.3 The " fire detector" annunciates upon the detection of a fire.

6.4 The " emergency mode" window annunciates upon switchover to the emergency mode of the NVAC system.

6.5 The " building temperature low" window lights upon exceeding the

( setpoint for the building temperature. This usually indicates a heating system failure.

6.6 If a pump has not started after a 30-second delay upon demand from control panel M-1, the " pump failure" window will light.

6.7 The " air filter plugged" window will light when the electrostatic air filter is plugged and the differential pressure across the filter exceeds the setpoint.

6.8 The " compressed air low pressure" window will light when the air pressure in the supply header to the Johnson Control control system falls below the setpoint.

7.0 ACCESS OF TSO AND MAD 7.1 Power up the terminal and modem and set the modum (right-most switch) to "MA."

7.2 Call our switchboard operator (Dial "0") or the control room (after hours) and tell him/her to transfer and the next call 7.3 Place the phone call to the WE computer by dialing l

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- _,c- -. , -

EPIP 6.7 Page 4 e -

7.4 Following an answer by the security equipment at the Pewaukee Data Center, wait about 10 seconds then enter on the phone touchtone key pad the appropriate predefined 6-digit location identifier number (LIN) which relates to your calling location. The LIN for this terminal location is NOTE: IF THE PROPER CODE IS NOT ENTERED OR NOT RECOGNIZED, THE SECURITY EQUIPMENT SIMPLY TERMINATES THE CALL. IT WILL THEN BE NECESSARY TO RETURN TO STEP 7.2.

7.5 A proper code is acknowledged with a tone. Once this tone is heard, the phone which originated the call should be hung up. The security hardware will automatically disconnect the call.

j 7.6 Within 15 to 30 seconds, the security equipment will place a call l back to the number that relates to the LIN which was entered.

7.7 In a correct sequence of events, the uscr's phone will ring. After picking up the receiver, enter the "*" key on the touchtone key pad.

This lets the security equipment know that its call was received and a data carrier is to be provided.

7.8 Once the carrier signal is heard, change the setting on the modem

['_ (right-most switch) to the "DA" position.

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7.9 The terminal will respond with:

ENTER LOGON ID-7.10 Using the deckwriter keyboard, enter the letters To EN'TER, press " Return."

7.11 The- terminal will respond with:

ENTER PASSWORD -

7.12 Using the deckwriter keyboard, enter your password.

(Up to 8 alphanumeric characters)

<MMMM) l To ENTER, press " Return."

w

EPIP 6.7 Page 5 7.13 A correct ID and password results in access to TSO. After a successful LOGON, TSO will respond -

READY <

7.14 To gain access to MAD, enter -

7.15 HELP -

If there are problems executing Steps 7.1 - 7.13, contact the HELP desk If you experience difficulty in gaining access to MAD, contact 8.0 ACTIVATION OF IODINE & NOBLE GAS RADIATION MONITORS 8.1 Coordinate with the off-site Health Physics Director to have the iodine and noble gas sample pump started. The pump is in the heating and ventilation room adjacent to the men's lavoratory. Ensure that a

-- new charcoal cannister is installed and that the initial sample flow

~

( rate and start time are recorded.

8.2 Interpretation of RMS readouts 8.2.1 The concentration of noble gas is determined by multiplying the observed concentrate on the readout labeled "RE-242" by the calibration constant posted adjacent to the meter. The units are pCi/cc Xe-133 dose equivalents.

8.2.2 The iodine activity on the charcoal cartridge is obtained by

. multiplying the observed countrate on the readout labeled "RE-241" by the calibration constant posted adjacent to the meter. The units are pCi - I-131 dose equivalents.

8.2.3 To convert the iodine activity into a concentration, calculate the volume of air that passed through the filter.

The concentration of iodine is approximately the activity on the filter (pci) divided by the total volume (cm3) for sampling periods less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, assuming no short-lived isotopes are present.

=

EPIP 6.7

. Page 6 NOTE: FOR LONGER SAMPLING PERIODS AND WHEN SHORT-LIVED IODINE ISOTOPES ARE EXPECTED TO BE PRESENT, THE FOLLOWING FORMULA MAY BE USED TO CALCULATE THE IODINE CONCENTRATION:

C=

F p(1-e" s)

Where: Units I

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C = concentration in air pCi/cc F = sample volume cc ,1 A, = decay constant, 0.693T\ min i A = total activity on filter pCi

t = elapsed time from sample stop to count start min t = total sample time min p' = filter collection efficiency 8.2.4 Any changes to the alarm setpoints shall be made in i accordance with the Radiation Monitoring System Alarm Setpoint Response Book (RMSASRB) kept in the control room.

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! e . HINOR Revision 7 l 06-27-86 i

j ACTIVATION OF HEALTH PHYSICS FACILITIES AT l SITE BOUNDARY CONTROL CENTER i

I j 1.0 PURPOSE f

l The primary purpose of this procedure is to provide guidelines for

activating the site boundary control center (SBCC) during an alert, site '

l or general emergency. Hodifications to these guidelines may be imple-

! mented by the Health Physics Director (Health Physicist) to meet the  ;

j existing plant and site radiological conditions so as to ensure the con- '

tinued safety of plant personnel and the general public. 5 i 2.0 ACTIVATION OF HEALTH PHYSICS FACILITIES AT SBCC

)

I 2.1 Offsite Health Physics Director -

/ .

The Offsite Health Physics Director or designated alternate is responsible for directing health physics activities at the SBCC  ;

and for providing radiation protection assistance as requested ~

by the Chemistry Director. When the Radeon/ Waste Hanager is avail-

(, . able, the offsite Health Physics Director should report to him.
  • i 4 -

Appendix "A," Offsite Health Physics Director Duties, provides the

specific guidelines for accomplishment of these duties.

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2.2 Assistant to the Offsite Health Physics Director a

When manpower allows, another individual in health physics super-  !

]

vision will be assigned the duties of Assistant Offsite Health Physics  ;

Director. This individual is responsible for directing Health Physics ~

personnel from the SBCC and for the coordination of all health physics-related activities with the offsite HP director. Appendix "B" provides

! the guidelines for accomplishment of these duties, a'

l 2.3 The Yo11owing teams will be manned by personnel as assigned by the i

I Offsite Health Physics Director. Team duties are outlined in the t respective appendix.  ;

j Team Appendix

} Site Boundary Control Center / Radiation Control Team B Survey Teams C i,

Kewaunee/ Environmental Shuttle Team C I

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EPIP 7.2.1

  • Page 2 i

i 2.4 Appendiz "D," " Guidelines for Off-Site Survey Team Management," should

! be used as a guide for managing the activities of off-site survey teams.

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~ . . . . - _ _ - . - - - - - - -. --- -- - - - - - - --

EPIP 7.2.1 f .- . Page 3 APPENDIX "A" l SITE BOUNDARY CONTROL CENTER OFFSITE HEALTH PHYSICS DIRECTOR RESPONSIBILITIES & D'JIIES i

1. Obtain environmental data (wind speed, direction and stability i class) from the Chemistry Director in the technical j support center or the RadCon/ Waste Manager as appropriate. ,

1 2. Use results from EPIP 1.4, " Radiological Dose Evaluation," and

EPIP 1.5, " Protective Action Evaluation," and determine the extent j and location for the initial and followup environmental surveys as
required.
3. When manpower availability allows, designate another individual in Health Physics supervision to perform the duties of Assistant Offsite 1 Health Physics Director at the SBCC (EPIP 7.2.1, Appendix "B"). If *

. manpower is not sufficient, perform the duties listed in Appendix "B."

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4. Coordinate with the RadCon/ Waste Manager, when available, the control l
of dose and personnel exposure documentation within the exclusion  ;

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area and off site.

1 i j 5. Coordinate with the RadCon/ Waste Manager, when available, on the

! evaluation of environmental radiological survey results, and make i recosumndations consistent with the Emergency Plan with respect to

! the general population (EPIP 1.4 and EPIP 1.5).

! 6. Coordinate off-site surveys with RadCon/ Waste Manager when available.

I j 7. Assist in evaluating radiological aspects of medical emergencies and

! coordinate response with the Health Physics Director in the TSC.

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8. With Security, establish access controls to coordinate access to the TSC/OSC l and the protected area. Ensure that all personnel entering or exiting

] the site are properly accounted for and are equipped with the neces- ,

i sary dose evaluation devices. Issue TLDs and SRDs as necessary. I 1

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., _ _ .. _ . -.__ - -- - - . -- - .- - ., , _ _ .. _ . _ . m_ - - _ . _ , , _ , , , . , _ _ - - - - - . , - . . . . - - _ . _ -

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. Page 4 l l.

APPENDIX "B" SITE BOUNDARY CONTROL CENTER ASSISTANT TO THE OFFSITE HEALTH PHYSICS DIRECTOR RESPONSIBILITIES & DUTIES

1. Direct the available Health Physics personnel in setting up and making available for use all SBCC health physics equipment. Verify the availa-j bility and operational status of equipment after it is checked out.

1

2. Designate Health Physics personnel to man the following radiation control teams as personnel become available for duty.
a. SBCC/ radiation support team (remaining Radiation Control Operators and Auxiliary Operator Trainees),
b. Kewaunee/ environmental shuttle team.

l 3. Initiate health physics radio communications radio check (Channel 3 of FM I radios).

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4. Receive environmental radiological survey instructions from the Offsite (s Health Physics Director and direct survey team leader to conduct the surveys.
SITE BOUNDARY CONTROL CENTER I

SITE BOUNDARY CONTROL CENTER / RADIATION CONTROL TIAN RESPONSIBILITIES & DUTIES l 1. Set up and verify operational status of personnel friskers.

2. Monitor personnel and equipment for contamination and perform decontami-l nation as necessary.
3. With Security, implement control and documentation of personnel entering or exiting the exclusion area. l
4. Implement controls for dosimetry issue, use, and documentation of personnel exposure and control of exposure data. Issue TLDs and SRDs as necessary.
5. Coordinate all health physics activities with the Assistant to the offsite Health Physics Director.
6. Perform as communicator / logger in the HP area of the SBCC.

{ 7. . Perform other duties as directed.

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EPIP 7.2.1

- . Page 5 APPENDIX "C" SITE BOUNDARY CONTROL CENTER SURVEY TEAM RESPONSIBILITIES & DUTIES i 1. set up and verify the operational status of the SBCC air sampling and radiological survey equipment.

2. Conduct all radiological surveys and air sampling. Record all air sample data and radiological survey results.

l 3. Ensure that all air samples and radiological surveys are properly logged and identified prior to turning them over to the shuttle team.

4. Perform other duties as directed.

SITE BOUNDARY CONTROL CENTER KEWAUNEE/ ENVIRONMENTAL SHUTTLE TEAM RESPONSIBILITIES & DUTIES

1. Transport samples to Kewaunee Nuclear Plant for analysis as directed by the Assistant to the Offsite Health Physics Director.
2. Retrieve samples from mobile survey teams and transport to TSC for analysis.
3. Document results of analysis and report results to the Health Physics Director by radio or telephone.
4. Perform other duties as directed.

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Page 6 1

. APPENDIX "D" i

GUIDELINES FOR OFFSITE SURVEY TEAN MANAGEMENT l The following is a discussion concerning tracking of radioactive " plumes" from <

an accidental release of radioactivity from Point Beach Nuclear Plant. These items would be appropriate to use during drills / exercises, as well as an actual ,

release. These are not necessarily in the order they would be done, nor is this l list necessarily complete.

L i 1. Offsite survey teams should be well briefed before they depart initially

  • l from SBCC. They should have an idea of the plume's suspected location and l where they are going. The initial briefing should also include a  ;

j discussion of current wind speed and direction. Throughout the drill /  :

q exercise or actual emergency, the teams should be informed of changes in l wind speed and direction. ,

) 2. When it can be reasonably assumed that a release has occurred and that the -

wind direction will allow the plume to be detected (i.e., the wind is 4

blowing over land) it is appropriate to send out survey teams. When first j sending teams out to find the plume, they should be sent out approximately one to two miles to find the boundaries and the centerline. Samples may be jl g taken at this time. After finding the plume at one mile, tracking the plume to five to ten miles (if necessary) should be done, taking samples as i

desired.

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j When it can be reasonably assumed that the plume is nearing land (i.e., the  !

1 wind direction is taking the plume from being over Lake Michigan to over  !

land) it is permissible to send survey teams out before a release has i

actually been detected at the plant and is encouraged. The team (s) sent I

out should be instructed to proceed approximately one mile out on the road  !

i I most accessible to the suspected location where the plume will make landfall. The team (s) should be told to read their meters often when doing

{ this to avoid being taken by surprise by the plume.

4. The teams should always be given specific directions, e.g., road / routes to follow from the SBCC to a sample location, one sampling location to another., to the SBCC from a sample point, etc. This can prevent the teams from needlessly traversing through the plume or from going too far out of

{ the way. '

1 1 5.

Radio comununications should be frequent .between SBCC and the mobile survey 1 teams. The teams should be asked where they are, what the dose rates are, 3

how the sampling is going, any problems, etc. Many communications will

) have to be initiated from the SBCC.

1

6. Generally speaking, the teams should be kept within the Emergency Planning j .

Zone (EPZ) of ten miles.

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t EPIP 7.2.1 '

. Page 7 i

7. Teams should be told when to don and remove bio-paks, if they don't ask, and a discussion of the need for taking KI tablets should be done before the teams initially leave the SBCC.
8. "This is a drill" should be stated sometime during each and every communication, preferably at the beginning and end, if not a real emergency.
9. Use of pylons by survey teams should be considered, especially on the busier roads.

. 10. Teams should be reminded to use and to refer to procedure EPIP 7.3.1. This should be done as part of the initial briefing. .

11. Teams should perform a quick inventory of the survey kits before initial departure. This should include a response check of the survey instrument.

Teams should ensure that tha poly bottles are filled initially and that as bottles are used, they obtain a sufficient number of filled bottles for future use. -

12. The teams should be asked for the reading from their SRDs periodically, as appropriate.

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EPIP 7.2.2

. HINOR Revision 7 G6-27-86 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 and Health Physics facilities at the technical support center / operations support center (TSC/OSC) in support of an emergency situation.

l 1.2 The Chemistry Director and Health Physics Director and certain designated members of Chemistry and Health Physics are responsible for activating the health physics equipment at the TSC/OSC The i

extent and sequence of implementation of these guidelines is I

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 I

(' required, the Health Physics Director will determine to what extent, if any, health physics coverage will be provided at the

TSC/OSC.

i l 2.2 For emergency conditions which require plant evacuation, either j EPIP 7.1.1 or 7.1.2 will be followed, depending upon whether

Chemistry and Health Physics personnel are on or off-site when

, notification is received.

1 3.0 HEALTH PHYSICS RESPONSIBILITIES FOR TSC/OSC RAD SUPPORT TEAM

. 3.1 When Chemistry and Health Physics Personnel are on-Site (EPIP 7.1.1) 3 .1.'1 Obtain five (5) PIC-6A survey instruments.

3.1.2 Obtain own personal respirator prescription eyeglass inserts i if necessary.

3.1.3 Proceed to the TSC/OSC and:

I

a. Hove the AMS-2 continuous air sampler (cart-mounted) into the TSC/OSC hallway and set up for operation.
b. Place the VAHP area monitor at the south gate in oper-i ation.

)

EPIP 7.2.2

- Page 2

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

d. 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.

3.1.4 Set up the Nuclear Chicago counter-scaler in the TSC.

(HPIP 5.51).

3.1.5 Activate the Canberra S-80. Check energy calibrations on S-80. Log on to the PDP 11/05 computer (via silent 700 terminal) and check operation of ANALYR, NGSD and MPC AIR programs.

3.1.6 Set up an area in the mini-lab vent hood to check in and hold samples for MCA analysis. Set up an area on the opposite side of the vent hood for temporary storage of samples (after MCA analysis and before more permanent

  • storage in the designated shielded storage area in the Unit 1 turbine hall El. 8').

3.1.7 Set up a trash bag in the mini-lab to contain contami-nated sample bags, gloves, towels, etc.

{

3.1.8 Activate the mini-lab vent hood by placing the switch (behind the door) in the auto position.

NOTE: BE SURE TO TURN OFF AFTER DRILLS.

3.2 Notification When Chemistry and Health Physics Personnel are Off-Site (EPIP 7.1.2) t

3. 2.1 ' Upon receipt of instruction to activate the TSC/OSC, the TSC rad support team will set up and place into operation

, the VAMP area moniter and the low volume air sampler at the south gate.

3.2.2 Proceed to the TSC/OSC and move the AMS-2 continuous air sampler (cart-mounted) into the TSC/OSC hallway; set up and place the Aris-2 into operation.

3.2.3 Begin preparation to provide health physics coverage as described under ISC HP equipment activation, Section 3.3 of this procedure.

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EPIP 7.2.2

. Page 3 -

3.3 TSC HP Equipment Activation 3.3.1 Prepare the health physics equipment from the emergency locker for use.

3.3.2 Prepare Th (red) radio for communications check.

3.3.3 Prepare the Nuclear Chicago counter-scaler for use.

! 3.3.4 Activate the Canberra S-80. Check energy calibrations i on S-80. Log on to the PDP 11/05 computer (via silent 700 terminal) and check operation of ANALYR, NGSD and MPC AIR programs.

! 3.3.5 Set up an area in the mini-lab vent hood to check in and

! hold samples for MCA analysis. Set up an area on the opposite side of the vent hood for temporary storage of samples (af ter MCA analysis and before more permanent storage in the designated shielded sorage area in the

  • Unit 1 turbine hall El. 8').

3.3.6 Set up a trash bag in the mini-lab to contain contami-nated sample bags, gloves, towels, etc.

i ( 3.3.7 Activate the mini-lab vent hood by placing the switch

(behind the door) in the auto position.

3.3.8 Provide health physics support as required at the TSC/OSC and in-plant support as requested by the Chemi.stry Director.

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

3.3.10 Coordinate with the Chemistry Director at the TSC/OSC on in-plant personnel exposure and documentation. Ensure i

that all personnel have a TLD; issue from the supply in the locker. Ensure that personnel are issued SRDs as required.

3.3.11 Verify that all personnel who are departing from the TSC are certain as to details of their approved assignments and are complying with all health physics requirements.

Whenever practicable, entries into high radiation or air-borne areas will be made under the radiation work permit

system. '

3.3.12 Determine contaminated area access point and set up $0P and control point at TSC/OSC entrance te Unit 1 turbine hall.

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{ EPIP 7.3.2 MINOR Revision 17 06-27-86 ,

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POST-ACCIDENT SAMPLING AND ANALYSIS  !

! 0F POTENTIALLY HIGH LEVEL REACTOR COOLANT .

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1.0 INTRODUCTION

i 1.1 This procedure outlines the i.,teps necessary to collect, handle and analyze a high level reactor coolant sample which could result from j gross fuel failure.

i j 1.2 Equipment List Set up the following in the primary sample hood prior to collecting

your sample

I i 1.2.1 The equipment detailed in Figures 2A and 25, with.the excep-tion of the sample bomb. -

) 1.2.2 Magnetic stirrers (120 VAC, battery or water / air powered) j and one 50 mi poly beaker and a 50 ml beaker.

1.2.3 pH/mv meters (120 VAC or battery powered) and pH probe.

3

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{ 1.2.4 A piston burette.

1.2.5 A lead brick wall of sufficient sise to store residue from j analysis.

I 1.2.6 Automatic pipets, continuously adjustable through 5 m1, or equivalent.

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1. 2. 7, Remote handling tools located in the cabinet below the 3

hood, t

, 1.2:8 Prepare a 1.0 liter sidearm flask with a correctly s'. zed

{ solid stopper and rubber septum over the sidearm.

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j 1.2.9 Gas syringe i

! The following equipment is also necessary for this procedure

! and need to be made ready.

1.2.10 The gas partitioner for H a analysis.

1.2.11 The special cart used for transport of the sample bomb.

j . 1.2.12 Tools for connecting and disconnecting sample bombs i.e.,

11/16" open end wrench or equivalent.

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EPIP 7.3.2

, Page 2 1.2.13 Remote valve turning tool. This tool as well as those mentioned in Step 1.2.12 are necessary for sampling and should be taken along and placed on the sample bomb transport cart, j 1.3 Reagents

) The following reagents are also necessary and need to be prepared.

1.3.1 0.1N NaOH for boroa. Obtain a supply from normal boron analysis.

l J 1.3.2 Mannitol for boron analysis. '

I 1.4 Preliminary Steps Initials 4

} 1.4.1 Standardize the pH meter.

j NOTE: IN THE EVENT OF LOSS OF AC POWER TO

  • THE LABORATORY, USE OF BATTERY, AIR,  ;

OR WATER-POWERID. MAGNETIC STIRRER i

AND BATTERY-POWERED PH METER MAY BE

, REQUIRED. -

5 ( 1.4.2 Organize as much of the equipment as possible behind lead brick walls in an arrangement j

that allows for unobstructed view of all operations with the aid of the convex mirror.

(See Figure 2A and 28.)

1.4.3 Put new rubber septum on gas bomb.

1.4.4 check out and prime the piston burette with fresh 0.1N Na0H solution.

1.4.5 Make sure that the vacuum line is attached to

the gas collection bomb at the valve 1 location.

Open valves 1 and 2. Secure valve 3. i 1.4.6 Startup the gas chromatograph for hydrogen analysis.

1.4.7 RINSE THE SAMPLE BOMB DRAIN TURE, RECEIVING BEAKER AND TIPS OF TRANSFER PIPETS WITH DEION-IZED WATER TO REMOVE ANY CHLORIDE CONTAMINATION.

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EPIP 7.3.2 Page 3 2.0 PRELIMINARY EVALUATION Initials l 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.

2.1 Indications of Possible Fuel Damage Some or all of the following would be present if fuel damage had occurred:

2.1.1 The letdown valve gallery monitor (RE-116) would be unusually high or offscale.

2.1.2 The failed fuel monitor 1(2)RE-109 will be unusually high or offscale. .

2.1.3 The containment radiation monitors, 1(2)RE-211 and seal table monitors, 1(2)RE-212, would be -

unusually high or offscale.

2.1.4 The containment low-range monitors, 1(2)RE-102 and 1(2)RE-107, would be reading unusually high or offscale.

2.1.5 The auxiliary building vent stack monitor, RE-214, would show a significant increase due to auxiliary building airborne activity from the letdown and charging pump areas.

2.1.6 Evaluation of Sample Room Conditions *

a. The sample room area monitor, 1(2)RE-106, and

, charging pump area monitor,1(2)RE-104, would give an indication of conditions in the auxiliary building and sample room.

The chem lab area monitor (RE-103) would give 2

an indication of lab conditions prior to

sample analysis,
b. After evaluation of the radiation monitoring system readouts, Health Physics will deter-mine what airborne and radiation surveys would be appropriate before auxiliary building entry.

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Initials ' ' -

c. Verify the requirements for auxiliary building i sample room entry, i.e., (1) RWP requirements, '

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(2) clothing requirements, (3) respiratory

} requirements, and (4) dosimetry requirements j including extremity dose monitoring require- s 1 ments, and (5) health physics coverage

! requirements including timekeeping. '

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2.1.7 The automatic actions of E0P-0 have caused -e containment isolation. 'y q
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! 2.2 Possible Loss of Component Cooling /

r 2.2.1 Verify that component cooling is still in service' ,

j to the affected unit. Sample cannot be obtained

-j without component cooling to sample room heat g

exchangers. .. ,

1 3

3.0 REACTOR COOLANT SAMPLING PROCEDURE 4 .-

l NOTE: THIS PROCEDURE SHALL NOT BE INITIATED UNTIL THE EVALUATIONS DIS-CUSSED IN SECTION 2.0 HAVE BEEN COMPLETED AND REVIEWED BY DUTY &

! CALL SUPERINTENDENT (PLANT OPERATIONS HANAGER), DUTY HEALTH PHYSICS

{ SUPERVISION (HEALTH PHYSICS DIRECTOR) AND THE DUTY SHIFT SUPERINTIN-DENT, AND THEIR APPROVAL HAS BEIN GRANTED. f l

I 3.1 Collecting a Pressurized Sample (Refer to Figure 1)

NOTE: THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE

' DIRECTION OF CHEMISTRY SUPERVISION AND ONLY AFTER COMPLETING SECTION 1.0 0F THIS PROCEDURE.

3.1.1 Contact the control room and verify that the

domineralized water header pressure is maximized (approximately 100 to 120 psi).

NOTE: THIS STEP HAY BE DELETED IF REACTOR j

HAKEUP WATER IS USED FOR THE FLUSH.

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EPIP 7.3.2 Page 5 s

! Initials

! 3.1.2 The following steps (a through 1) must be

accomplished before opening the incontainment sample isolation valve 955 (Step 3.1.3) and the hot leg sample isolation valve 966C (Step 3.1.4).
a. Proceed to the sample room and install the i shielded sample bomb on the outside wall of the sample room using the fittings provided.

If the bomb is already installed, verify

that the fittings are tight.

) CAUTION: BEFORE REMOVING THE SWAGE LOCK CAPS TO INSTALL THE BOMB, OPEN VALVES 939, 940 AND 941 TO RELIEVE SYSTEM

! PRESSURE. CLOSE VALVES 939, 940 i

AND 941. PLACE A WASTE BUCKET

! DIRECTLY UNDE 3 THE BOMB. USE A PAPER -

{ TOWEL SHIELD AND RUBBER GLOVES WHEN REMOVING CAPS.

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b. Verify that the dimineralized water line i

is connected from valve 945 to the de- -

mineralized water manifold. Open j domineralized Hao valves 945, 947, and 948 and check for leaks on the bomb fittings.

l Shut valves 945, 947, and 948.

l c. Enter the sample room and close or verify closed the following valves on the sample panel.

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, 1. 961C - Normal hot leg sample bomb inlet.

2. 964C - normal hot leg sample bomb outlet.
3. 965C - normal hot leg sample bypass.

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4. 968 - normal hot leg return valve.
5. 971 - normal hot leg sink sample valve.

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EPIP 7.3.2

, Page 6 Initials

d. Notify the control room that the failed fuel monitor, 1(2)RE-109 will be taken out-of-service for sampling; then close:

938A - detector RE-109 inlet valve 938B - detector RE-109 outlet valve 933C - detector RE-109 metering valve (Unit 2 only)

NOTE: VERIFY THAT SC-938 IS OPEN.

e. Further verify that there is component cooling flow to the sample room heat exchangers by viewing the local flow indicstor (FI-603) on the sample panel.
f. Open or verify open the following valves on the sample panel.
1. 969A - sample system purge to volume control tank.
2. 956C - normal hot leg sample supply valve.

~

3. 990 - residual heat removal sampli supply valve. (DO NOT USE FOR DRILLS.)
g. Verify DI water system lineup as follows:
1. For Unit 2, check open DI water valve (2-991) located on the east wall of sample room.
2. For Unit 1, check DI flow by momentarily opening the DI water valve in the Unit 1 primary sample hood. Check flow, then shut.

s e

+, - - - . . - - - - -.

. o EPIP 7.3.2 Page 7 Initials

h. Leave the sample room and position the following valves wide open. These valves are located on the sample room wall.
1. 939 - sample bomb inlet.
2. 941 - sample bomb outlet.

NOTE: FOR DRILLS AND TRAINING EXERCISES OPEN VALVES ONLY ONE-QUARTER TURN TO ELIMINATE N-16 GAMMAS.

i. Fully open bomb valves 9B, 9A, 8A & 8B.

3.1.3 open the incontainment hot leg sample isolation valve (valve 955) and the residual heat removal sample isolation valve (valve 959) by means of the switches located outside the sample room. -

NOTE: DO NOT OPEN VALVE 959 FOR DRILLS.

If the valve No. 955 will not open because of

m. containment isolation, perform the following steps (a through c). _
a. Request that the Control Room reset the con-tainment isolation signal,
b. Turn the local control switch positions for valves 951, 953, and 955 to the "close"

, position using switches outside sample rooms.

c. Turn the local control switch for valve 955 to the "open" position.

3.1.4 Request control room to open the hot leg sample isolation valve (966C).

3.1.5 Verify sample flow by an increase in the radiation levels around the sample bomb.

3.1.6 Leave the primary auxiliary building.

~.

EPIP 7.3.2 p . Page 8

- Initials 3.1.7 After 15 minutes, return to collect the semple.

Close valves 9B and 9A and then valves 8B 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.

3.1.8 Close the in containment hot leg sample isolation valve (955) and the RHR sample iso-lation valve (959),1f open, using the switches outside the sample room.

3.1.9 Request control room to inanediately 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 4.1 Leave valve 939 open, and fully open valves 940 and 941.

Open valves 945 and 946. Allow the lines to flush for at least 15 minutes.

NOTE: DO NOT REMAIN IN THE AREA 0F THE SAMPLE STATION DURING THIS FLUSH.

4.2 After about 15 minutes return and measure radiation levels.

If a chemistry or 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.

O

_ . , _ . . _ - _ _ , ~ _ - - - - . . - . = - - +-*---2, - - - - "-**^'e M**-"--

EPIP 7.3.2 Page 9 Initials 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. Attach cart to the sample bomb. Dis-connect 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 OF 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 TRAINING EXERCISES, RETURN ALL EQUIPMENT AND VALVE LINEUPS TO NORMAL. (SEE SECTION 4.4).

4.4 After drills or training exercises, enter the sample room and notify control room that the failed fuel monitor -

(RE-109) is to be returned to service and that the sample room valving is to be returned to normal.

4.4.1 Close or verify closed valves: .

1. 961C - Normal hot leg sample bomb inlet
2. 964C - Normal hot leg sample bomb outlet
3. 965C - Normal hot leg sample bypass
4. 971 - Normal hot leg sink sample valve
5. 938B - Failed fuel monitor RE-109 outlet

. (Unit 2 only)

6. 939 - High level sample bomb inlet ,
7. 940 - High level sample bomb bypass
8. 941 - High level sample bomb outlet
9. 945, 946, 947, 948 - Demineralized water flush valves NOTE: ADVISE CONTROL TO REDUCE DEMINERALIZED WATER HEADER PRESSURE TO NORMAL.

l EPIP 7.3.2

. Page 10 Initials 4.4.2 Open valves:

1. 938A - Failed fuel monitor RE-109 inlet g
2. 938B - Failed fuel monitor RE-109 outlet (Unit 1 only)
3. 938C - Failed fuel monitor RE-109 metering (Unit 2 only)
4. 956C - Normal hot leg sample supply valve i
5. 968 - Normal hot leg return valve
6. 969A - Sample system purge to volume control tank 4.4.3 Open the containment isolation valve (955) using ~

the switch outside the sample room.

4.4.4 Call control and have them open valve 966C, hot leg sample isolation valve.

4.4.5 Establish proper flow through the failed fuel monitor by throttling valve 938B for Unit 1 or 938C for Unit 2.

5.0 SEPARATION OF THE PRESSURIZED SAMPLE AND ANALYSIS OF THE GASEOUS AND LIQUID COMPONENT (Refer to Figures 2A and 2B) 5.1 Collecting the Gaseous Sample From the Pressurized Sample 5.1.1 Place the shielded sample bomb in the sample holder in the primary sample hood.

5.1.2 Connect the cample 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 drain tube to the opposite end of the sample bomb and verify that valve 11 on the drain tube is open.

~ s J

EPIP 7.3.2 Page 11 2

Initials l 5.1.4 Make sure that the vacuum line is attached to '

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.

1 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 valu 8B.

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.

Allow the system to degas for 2-4 minutes.

Check that valves 9A and 9B, 8A and 8B are fully open. Close valve 2.

5.2 Analysis of Gaseous Sample

('

m 5.2.1 Hydrogen Use a syringe to draw a 1 cc sample. Use the injection port on the gas partitiener for this analysis.

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 15 minutes for thermal mixing. Draw a I cc sample of this dilution and proceed as normal.

  • Additional dilution should be performed if i the contact reading is >l ar/ hour. j l

NOTE: SEE SECTIONS 7.0 AND 8.0. j er J

1 EPIP 7.3.2

. Page 12 5.3 Initials Collecting the Liquid Sample From the Pressurized Sample NOTE:

IT IS EXTREMELY IMPORTANT TO VERIFY THAT VALVE 2 HAS BEEN CLOSED BEFORE PROCEEDING.

5.3.1 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.

5.3.2 Clcse 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 an automatic pipetter into a 50 ml poly beaker containing '

, a stir bar.

b. After transfer is complete, record the pH.

9' c. Plug in the magnetic stirrer, add mannitol, -

and proceed with the boron analysis.

NOTE: IF THE PRIMARY SYSTEM HAS BEEN BORATED, 5 ML OR MORE OF TITRANT MAY BE NEEDED TO REACH AN ENDPOINT.

NOTE: AFTER DRILLS AND PRACTICE RUNS, THE BORON TITRATOR MUST BE FINSHED WITH DEIONIZED WATER AND PCT IN DRY LAY-

, UP.

ALL ELECTRODES SHOULD BE PLACED IN LAYUP SO THEY ARE CONDITIONED FOR

( - IMMEDIATE USE. ALSO PURGE ANY WATER THAT MAY BE HELD UP IN THE 280 ML GAS COLLECTION BOMB.

5.4.2 Chloride Analysis Analyze a suitable volum of the remainder of the sample using the PBJP ion chromotography analyzer.

i

._ ....__ , __ - - , ~ . - , -

EPIP 7.3.2 Page 13 Initials NOTE: THE CHLORIDE ANALYSIS MAY NEED TO BE PERFORMED BY WE LAB SERVICES USING THEIR ION CHROMATOGRAPHY ANALYZER IF THE PBNP LAB AND/OR EQUIPMENT IS NOT AVAILABLE.

KEEP THIS SAMPLE FRACTION IN THE LAB VENT HOOD UNTIL ANALYSIS HAS BEEN SATISFAC-TORILY COMPLETED. CONTACT THE TECHNICAL SUPPORT MANAGER TO ARRANGE FOR THE TRANS-PORT OF THE NECESSARY PERSONNEL AND EQUIPMENT TO PBNP.

5.4.3 Iodine Analysis and Gamma Scan Using the specially prepared 2 cc syringe or adjustable automatic pipet, withdraw 0.3 cc (or less) of the cample from the beaker and inject 9.is sample into a 1000 ml poly bottle containing demineralized water. Make additional dilutions in the same msnner.* Count as normal. 1

  • Additional dilution should be perfonned until

( the contact reading is <1 mr/ hour.

\

NOTE: SEE SECTIONS 7.0 AND 8.0.

5.5 Reporting of Results i

Complete and forward Reactor Coolant Post-Accident  !

Sampling Analysis Report (EPIP-30) to the Chemistry 1 Director. '

6.0 SAMPLE STORAGE After analysis, store all samples (liquid and gas) in the desig-nated high-level shielded storage area located in the auxiliary  ;

building area outside of the gas decay tank room. ]

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 ce 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.

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EPIP 7.3.2 l

. Page 14 l

8.0 LABELING OF SAMPLES Label all chloride, noble gas, iodine and ganuna scan. samples with all ,

pertinent information such as: sample ntuaber, name of sample, date and '

time of sampling, sample volume and dilution (s).

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EPIP 7.3.3 l

. MINOR Revision 16 06-27-86 POST-ACCIDENT SAMPLING OF CONTAINMENT ATMOSPHERE l

l

1.0 INTRODUCTION

, l This procedure outlines the steps necessary to collect, handle and analyze a potentially high radioactive containment atmosphere sample resulting from gross fuel failure and loss of reactor coolant system integrity to determine hydrogen and radioactive gas concentrations.

1 2.0 PRELIMINARY EVALUATION I NOTE: THE FOLLOWING EVALUATION SHALL BE COMPLETED PRIOR TO ANY ATTEMPT TO ENTER THE FACADE OR RE-111/RE-212 CUBICLE TO PERFORM A VALVE LINEUP OR COLLECT A CONTAINMENT ATMOSPHERE SAMPLE.

2.1 Indications of Possible Fuel Damage Some or all of the following would be present if fuel damage or loss of reactor coolant ystem integrity had occurred:

2.1.1 The letdown valve gallery monitor RE-116 would be .

, unusually high or offscale.

2.1.2 The containment radiation monitors 1(2)RE-211 and 1(2)2RE-212 would be unusually high or offscale.

2.1.3 The containment low-range monitors 1(2)RE-102 and seal table monitors, 1(2)RE-107 would be unusually high or offscale.

2.1.4 The automatic actions of EOP-1A have caused containment isolation.

2 .1. ,5 The failed fuel monitor 1(2) RE-109 may be unusually high or offscale.

2.1.6 The auxiliary building vent stack monitor, RE-214 could show a significant increase due to auxiliary building airborne activity from the letdown and charging pump areas.

2.2 Evaluation of Radiological Hazards in Access Areas Required for Sampling Initials 2.2.1 After evaluation of the radiation monitoring system readouts, verify with Health Physics that the appropriate airborne and radiation s surveys have been made before entering the facade. .

. .. .-4 _ -_ __. ,-.-- --

._ y -

EPIP 7.3.3

, Page 2 Initials 2.2.2 Verify the requirements for facade and 1(2)RE-211/l(2)RE-212 cubicle entry.

a. Radiation work permit requirements
b. Clothing requirements
c. Respiratory requirements
d. Dosimetry requirements including extremity dose monitoring
e. Health physics coverage requirements ,

including timekeeping.

2.3 Evaluation of Containment Pressure containment pressure must be less than 5 psig in order '

to initiate sampling.

3.0 MISCELLANEOUS CONSIDERATIONS Take along a flashlight in case area lights are not' working and a portable FM radio.

4.0 CC!NTAINMENT ATMOSPHERE SAMPLING PROCEDURE NOTE: THE FOLLOWING PROCEDURE SHALL NOT BE INITIATED UNTIL THE EVALUATION DISCUSSED IN SECTION 2.0 HAS BEEN COMPLETED.

THE DUTY & CALL SUPERINTENDENT (PLANT OPERATION MANAGER),

THE DUTY & CALL HEALTH PHYSICS SUPERVISOR (HEALTH PHYSICS DIRECTOR) AND THE DUTY SHIFT SUPERINTENDENT SHALL APPROVE THE IMPLEMENTATION OF THIS PROCEDURE. THE FOLLOWING STEPS WILL BE ACCOMPLISHED UNDER THE DIRECTION OF CHEMISTRY SUPERVISION.

l l

1 9

b I

EPIP 7.3.3 Page 3 Initials 4.1 Containment Atmosphere Sampling Using the 1(2)RE-211/

1(2)RE-212 Sampling System, After Containment Isolation 4.1.1 Service Air Setup

a. Proceed to the potable water room to sample Unit I containment or to Unit 2 nonnuclear room to sample Unit 2 containment.
b. Enter the facade outside the 1(2)RE-211/1(2)RE-212 cubicle
c. Connect the service air regulator /

tailpiece section to the quick disconnect fitting attached to valve 1(2)3200Y. Verify that valve (1(2)3200Y is closed. -

i d Open the service air supply Whitey valve (upstream of regulator) and verify service air pressure on the regulator inlet gauge.

(~ ~ NOTE: IF NO PRESSURE, VERIFY THAT THE SERVICE AIR GATE VALVE ON THE EL. 66' FACADE IS OPEN

e. Adjust the regulator to 4 psig static head outlet presssure.

NOTE: IF PRESSURE GOES ABOVE 4.5 PSIG, BACK OFF THE REGULATOR, BLEED OFF AIR AT THE DOWNSTREAM QUICK DISCONNECT AND TRY AGAIN 4.1.2 Valve Line-Up NOTE: FOR INTERIM SETUP P707A HAS NO AUTO SECURING. IF CONTAINMENT ISOLATICN HAS OCCURRED, FUSES FOR P707A MAY t

HAVE BLOWN. FUSES ARE LOCATED IN THE DAM IN THE ROD DRIVE ROOM.

l e

i

l EPIP 7.3.3 l

. Page 4  !

I Initials I

a. Secure sample pump, P707A, locally at
pallet.
b. Verify with theicontrol room that the following conditions exist:

(1) Valves 3200A, B & C have closed.

(2) Vent control switch is in off and pullout (P707B secured).

(3) Mode select switch is in septum l position. The switch will accomplish the following valve line-up: (3200E&F closed, 3200D open, 3200G aligned to containment, 3200M aligned to septum).

i -

i NOTE: THE SWITCHES ARE LOCATED ON THE

) APPROPRIATE UNIT'S ASIP PANEL.

c. Enter the cubicle and perform the

( following:

(1) Verify 1(2)A0V-3200A&B are closed by visual observation.

(2) Verify 1(2)3200Z is open.

{

(3) Manually close valves 1(2)3200N, I P, Q, W AND (2)3200EE & FF. '

(4) Manually open Whitey valves 1(2)3200J & L.

d. Request the control room perform the following:

I NOTE: THE SAMPLE PUMP P707A SEALS ARE RATED FOR 5 FCIG. TO PREVENT AN -

INADVERTENT AIRBORNE RELEASE, THE CONTAINMENT PRESSURE MUST BE LESS THAN 5 PSIG BEFORE PRO-CEEDING.

I

EPIP 7.3.3

, Page 5 i

Initia7s (1) Verify containment pressure is less than 5 psig.

(2) Open A0V's 1(2)3200A, B & C (contain_

ment isolation valves).

e. Start sample pump P707A locally at the pallet.
f. Verify sample flow by observing a flow increase on FIT-3288 and return to the potable water /nonnuclear room.
g. Allow 15 minutes for sample recirculation and return to the cubicle with two (2) 2 cc gas-tight syringes in a hollowed-out lead brick. One syringe should have 1 cc of AgZ inside the syringe barrel. ~

4.1.3 Sample collection

a. Obtain two 1 cc gas samples from the sample

.. septum by means of the gas-tight syringes.

Withdraw the syringe plunger only once. Do not purge the syringe as the AgZ will retain I

the iodine from each withdrawal.

NOTE: LOCK THE SYRINGE PLUNGERS PRIOR TO

] WITHDRAWING FROM THE SEPTUM.

b. Place the syringes in tr.e lead bricks for transport.

CAUTION: CLOSE LEAD BRICK COVER SLOWLY TO AVOID BREAKING SYRINGES.

! c. Note the prepurge radiation levels in the l cubicle,

d. Verify a service air pressure of <5 psig on the regulator discharge and open l l valve 1(2)3200Y.  ;

)

l

=

EPIP 7.3.3

, Page 6 Initials 4.1.4 Sample Line Purge

a. Return to the potable water /nonnuclear room and request the control room close valves 1(2)3200B&C.
b. Allow the system to purge forward for 15 minutes.
c. Secure the sample pump P707A locally from the pallet, then request the control room perform the following:

(1) Place mode select switch to containment position and shut 1(2)A0V-3200A. ~

(2) Open 1(2)A0V-3200B&C.

- d. Allow the system to purge backwards 15 minutes and request the control room close valves 1(2)3200B&c.

e. Return to the cubicle and perform the following:

(1) Verify the effectivenss of the purge by measuring the reduction of the radiation levels.

(2) Close the service air Whitey valve.

Close valve 1(2)3200Y and disconnect )

the service air line quick disconnect l at valve 1(2)3200Y. i (3) Enter the cubicle and close Whitey valves 1(2)3200J & L.

e!

- r - - - -- , y ,% r, , - - , - - -

l EPIP 7.3.3

. Page 7 l

1 Initials

f. Notify the control room that sampling has been completed, and that valves 1(2)3200W and 2-3200 EE & FF are closed.

NOTE: AFTER ALL DRILLS AND PRACTICE EXERCISES, ALL EQUIPMENT AND VALVE LINEUPS ARE TO BE RETURNED TO THE AS-FOUND CONDITION. ASK THE ,

CONTROL ROOH TO HAVE AN OPERATOR VERIFY /REALLIGN THE VALVES WITHIN THE 1(2)RE-211/212 CUBICLE.

5.0 CONTAINMENT ATMOSPHERE ANALYSIS 5.1 Volume Adjustments 5.1.1 Before proceeding with the hydrogen, radioactive -

noble gas and radioactive iodine analyses, the sample contents of both syringes must be brought to atmospheric pressure. Use the shielded sacri-ficial glass bomb for this purpose if an operat-ing vent hood is not available.

5.1.2 Insert the syringe through the rubber septum of the glass bomb or place deep inside the vent hood.

Unlock the syringe locking device and let the syringe and bomb equilibrate for approximately 30 seconds. Relock the syringe and withdraw.

, Store the syringe in the lead brick.

) 5.1.3 Repeat Step 5.1.2 for the other syringe.

5.2 Hydrog'en Assuming normal equipment setup and preparations are complete, use the sample injection port on the gas partitioner, inject a 1 cc gas sample from the syringe without the AgZ, and proceed using normal hydrogen analysis procedures.

5.3 Radioactive Noble Gases & Iodines Noble Gases 5.3.1 Use the 2 ce syringe with the 1 cc of AgZ for the noble gas and iodine separation / analysis.

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EPIP 7.3.3

, Page 8 5.3.2 Inject the 1 cc containment atmosphere sample into a one liter poly bottle. Purge the syringe once or twice while in the poly bottle in order to recover all of the noble gases. Remove the syringe and store in the lead brick. Tape over the syringe hole in the poly bottle. Let the gas come to equilibrium for a minimum of 15 minutes while proceeding with the iodine analy-sis section.

5.3.3 Withdraw a 1 ce gas sample from the poly bottle in Step 5.3.2. If the contact reading on the syringe is less than 1 mR/hr, inject the sample into a 5 cc vial and count as normal. If the contact reading is greater than 1 mR/hr, further dilutions are necessary.

Dilution procedure: Inject the 1 cc sample into a one liter poly bottle and allow to equilibrate.

  • Withdraw 1 cc from the poly bottle. If the con-tact reading is less than one mR/hr, inject into a 5 cc vial and count as normal. If the contact reading is greater than 1 mR/hr, dilute further.

k NOTE: FOR EACH DILUTION, USE A NEW SYRINGE OR MAKE CERTAIN THE OLD SYRINGE IS COMPLETELY PURGED. LABEL NOBLE GAS SAMPLES AND IODINE SAMPLES WITH ALL PERTINENT INFORMATION SUCH AS: SAMPLE NUMBER, NAME OF SAMPLE, DATE AND TIME OF SAMPLE, SAMPLE VOLUME AND DILUTION (S).

Iodines 5.3.4 Unscrew the syringe top and remove the internal plunger.

, Pour the silver zeolite into a counting test tube and cap.

5:3.5 If the silver zeolite / iodine sample is less than one mR/hr contact, count the sample directly on the MCA using the test tube geometry.

l l

t ,

i EPIP 7.3.3 i , Page 9 1

~

i 5.3.6 If the iodine activity is too high to count directly, determine the radiation level in mR/hr at one foot.

Also, determine the percent isotopic composition using -

j the MCA and attenuating the sample if necessary.

Determine the total iodine activity using the following equation; R/hr 9 l' C(CI) = 6E T

l The following table can be used as an aid in determining i the " Total Gamma Energy / Disintegration" (E ) f r the T

above equation.

) (1) (2) (1) x (2)

Total y  % Composition Weighted y i Isotope Energy / Dis (Fraction) Energy I-130 2.130 I-131 0.380 i

I-132 2.260 3 I-133 0.608 I-134

(-.

I-135 2.600 1.56C Total Weighted y Energy: (ET )

Each individual iodine isotopic concentrtion (pC1/cc) is calculated as follows:

pCi/cc Igg) = C(Ci) x 1 x 10+6 x (Fractional % Composition) j 4

i 1

EPIP 7.3.3

, Page 10 6.0 CALCULATIONS Initials 6.1 Pressure & Temperature Correction Ask control room supervision for the temperature and pressure in containment (psig and *F). Determine atmos-heric pressure (mm Hg) and temperature (*F) from the barometer in the laboratory. Convert this to psia.

Apply the following correction factor to all results:

Concentration (pCi/cc) x (Pc + 14.7) x ( lab + 459)

(T + 459)

P lab P ("" U}

3ab (psia) = 14.7 psi x 760 mm Hg Pc = containment pressure, psig Tc = containment temperature, 'F 6.2 Complete and forward Containment Atmospheric Post-Accident Sampling Analysis Report (EPIP-31).

7.0 Sample Storage '

i After analysis, store all samples (AgZ and gases) in the designated high-level shielded storage area located in the auxiliary building outside of the gas decay tank room. '

I l

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g mwv i II I V

32OOJ W 32OOL CV Stock l gy 32OOR Samn e Septum 3200 y N.E. M Il 3406 32OOW iT

! FI VG P IT 34 h 9 b 340 3403 y1 3288 g [O .

CV M . P707A N. D.

{ 32 O H 34O' RE 2ll/ 212 RED 2 11 Il h b) Q Sample Pump N.D.

Focade Q. ,,

- Filter B 32 0 32OOFF ( 3200 PP l l 3200 E C. N CV N. E . L. C.

F N.D. Forced Vent Pump g 3h00  ; .'orge Exh. Filler llB Sak L.$ 32OOT

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E F7 l 32OOP 32OOS 2

3200 ~

3405 j E o FOR INFORMATION ONLY

l EPIP 7.3.4

, MINOR Revision 4 06-27-86 MOVEMENT OF REQUIRED CHEMISTRY EQUIPMENT & MATERIALS TO THE TECHNICAL SUPPORT CENTER COUNTING ROOM & MINI-LABORATORY 1.0 GENERAL The purpose of this procedure is to provide a series of actions on the part of chemistry personnel for the movement of required chemistry equipment and materials to the technical support center (TSC) counting room and mini-lab in the event this becomes necessary.

This procedure may be implemented in the event that the controlled side chemistry lab is declared radiologically uninhabitable or unfit for MCA analyses.

2.0 ATTACHMENTS 2.1 Appendix "A": Gas Chromatograph Transport Procedure 2.2 Appendix "B": TSC, Minilab & Counting Room Chemistry-Related Equipment & Reference Material Inventory List 4

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EPIP 7.3.4

, Page 2 APPENDIX "A" GAS CHROMATOGRAPH TRANSPORT PROCEDURE 1.0 PURPOSE To provide a readily available reference for the timely removal and transport of the Fisher Model 29 or 1200 Gas Chromatograph (GC) to the TSC mini-lab.

2.0 REFERENCES

2.1 Fisher Model 29 Instruction Manual, Fisher Scientific Co., April, 1974 2.2 Fisher Model 1200 Instruction Manual. Fisher Scientific Co., May, 1979 3.0 PROCEDURE 3.1 Turn off the " CELL POWER" and " HEATER" on the GC Model 29 or the

" BRIDGE POWER" and " MAIN POWER" on the GC Model 1200. Unplug the AC line cord.

3.2 Secure the Helium and/or Argon carrier gas at the cylinder and disconnect the carrier gas line at the GC inlet.

3.3 Disconnect the tygon vent tubing from the "T" fitting that connects to the " CARRIER GAS OUTLET" and " SAMPLE OUTLET."

3.4

Disconnect the VARIAN AEROGRAPH recorder cable from the + and -

jacks on the RECORDER TRANSFER SWITCH box. Unplug the AC line  !

cord on the VARIAN AEROGRAPH recorder.

3.5 Disconnect the +, - and ground wires on the back of the GC that lead to the RECORDER TRANSFER SWITCH.

3.6 Carefully transport the GC and recorder units to the TSC l mini-lab.

NOTE: 1 TAKE ALONG ANY OTHER NECESSARY ITEMS SUCH AS CALIBRATION 1 CURVES, CALIBRATION GASES, SILICON RUBBER INJECTION STOPPERS, DRIRITE, ETC. j'

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EPIP 7.3.4

. Page 3 3.7 Setup the GC close to the VENT HOOD and connect a tygon line from the SAMPLE and CARRIER OUT to the VENT HOOD.

3.8 Plug in the AC line cord and turn on the " HEATER" on the -

GC Model 29 or the " MAIN POWER" on the GC Model 1200.

l 3.9 Connect the appropriate carrier gas line to the GC and establish the correct pressure and flow rate.

3.10 Turn on the " CELL POWER" on the GC Model 29 or the " BRIDGE POWER" on the GC Model 1200 after allowing sufficient carrier gas purge time.

3.11 Connect the Varian Aerograph recorder cable directly to the jacks on the back of the appropriate GC. Plug in the recorder AC line cord.

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. Page 4 APPENDIX "B" TECHNICAL SUPPORT CENTER, MINI-LAB & COUNTING ROOM CHEMISTRY-RELATED EQUIPMENT & REFERENCE MATERIAL INVENTORY LIST 1.0 GAS CHROMATOGRADH RELATED 1.1 Tygon vent line to vent hood 1.2 Burret stand and clamps, 250 ml separatory funnel, latex tubing

  • 1.3 Carrier gas (Ar), regulator, hose, cylinder bracket or stand 1.4 Glass sample bombs 1.5 Syringes (gas tight and liquid) 1.6 Leak detector -

1.7 Dririte i

1.8 Silicon rubber injection stoppers 1.9 Hose pinch clamps ~

1.10 Varian recorder paper

  • 1.11 Calibration curve book
  • 1.12 Calibration gas cylinders for hydrogen s
  • May not be stocked in TSC, mini-lab or counting room; bring from chemistry lab.

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2.0 MCA RELATED 2.1 Calibration curve book (s) l 2.2 Geli detector (s) l l

1 2.3 LN2 dewar and fill system 2.4 Detector pig (s) and geometry positioner / holder (s) 2.5 Canberra S-80 MCA, PBP 11/05 computer and Silent 700 terminal 2.6 Sample bottles, vials and septums

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EPIP 7.3.4 4

- Page 5

  • 2.7 Calculators (2); also chargers if applicable.

2.8 Charcoal filter blowout apparatus

  • 2.9 Eff checking standard (such as Q CY.44 liter liquid) 3.0 MISCELLANEOUS 3.1 Poly bottles (assorted) i 3.2 Pipettes (assorted) and rack 3.3 Bunsen burners, tripods, screens, torch lighter 3.4 condenser columns, drilled corks, glass tubing 3.5 VoJar etric flasks, beakers, volumetric cylinders 3.6 Decon soap and Sparkleen : ~

3.7 Tygon, latex tubing and cutter 3.8 Vacuum hose

't 3.9 Tuck tape 3.10 Tools (assorted) 3.11 Eye droppers 3.12 Tweezers & planchetts (1" and 2")

3.13 CAMP procedure book 3.14 Respirator inserts (eyeglasses)

  • 3.15 Gas " syringes and lead brick for containment atmospheric sampling 4.0 POST-ACCIDENT SAMPLING SYSTEM RELATED 1

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  • 4.1 Ramp / Gas expansion chamber (gas collection bomb) l
  • 4.4 Mirror ._
  • 4.5 Specially prepared 2 c syringes and auto pipeters (0-5 ml) 1

EPIP 7.3.4

, Page 6

  • 4.9 All " Equipment List" items from EPIP 7.3.2, Section 1.2
  • 4 10 EPIP binder (lab copy)

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EPIP 13.1

. MINOR Revision 5 06-27-85 1

CRISIS COMMUNICATIONS 1.0 GENERAL This procedure describes the steps to be taken if crisis communications are deemed necessary.

2.0 PRECAUTIONS & LIMITATIONS 2.1 All actions and notifications should be appropriately logged.

4 2.2 Maintain phone lines.

3.0 INITIAL CONDITIONS 3.1 Site emergency or general emergency has been declared or Company ~

Management has decided that JPIC activation is necessary.

3.2 Notification has been received from the Emergency Director, Duty &

Call Superintendent, or the Emergency Support Manager that crisis

('. communications are necessary.

4.0 PROCEDURE 4.1 Designee (Public information representative) i 4.1.1 Contact Vice President Communications, Manager of Communica-tions, Joint Public Information Center Director or their designates to alert them of events and possible implementa-tion of the Crisis Communications Plan.

4.1.2 Contact Coordinator of Point Beach Energy Information Center or

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designee with instructions to open the Joint Public l

Information Center (JPIC). I 4.1.3 Report to the communications center in the Public Service Building (PSB) or JPIC as instructed by the Manager of Communications.

i 4.2 Vice President Communications 4.2.1 Contact Emergency support Manager. Together detenmine if it is necessary to open the JPIC.

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l EPIP 13.1

, Page 2

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1 4.2.2 Contact JPIC director to confirm need to open JPIC. I Indicate which JPIC location will be utilized. (Primary - l Two Rivers Community House; Backup - Kewaunee High School.)

4.2.3 1

Contact the Manager of Communicaticas. Advise him to call I appropriate personnel required to staff the comunications center at the PSB and JPIC.

4.2.4 Report to the PSB.

4.3 Manager of Comunications 4.3.1 Contact personnel necessary to staff the communications center in the Public Service Building.

4.3.2 contact personnel necessary to staff the JPIC.

4.3.3 Report to the communications center in the PSB.

4.3.4 Coordinate communications between the JPIC and the communications center in the PSB.

4.3.5 Assist JPIC Director in coordination of all ccamunications with media and offsite agencies. Releases should be identical and may be released simultaneously from the JPIC, the communications centers in the PSB, and the Madison office of the State Division of Emergency Government.

4.4 Joint Public Information Center Director 4.4.1 Report to the JPIC.

4.4.2 Contact Emergency Support Manager at the emergency opera-tions facility (EOF) to discuss status of the plant ani information to be released to the media.

4.4.3 Contact communications center in the PSB to confirm the operation of the JPIC and coordinate any media release.

4.4.4 Oversee and direct operation of the JPIC.  :

4.5 Coordinator - Point Beach Energy Information Center l 4.5.1 Contact the Director - Two Rivers Community House (or director of designated alternate) and request that the facility be made available to Wisconsin Electric Power Company as the Joint Public Information Center.

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EPIP 13.1 l

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4.5.2 If the Two Rivers Community House is to be used as the JPIC, i contact General Telephone and request that they implement their Radiological Emergency Response Plan for that facility.

4.5.3 Contact other Energy Infr:mation Center sisff and request that they report to the JPIC bringing with them listed emergency supplies.

4.5.4 Report to the JPIC.

4.5.5 Contact emergency operations facility (EOF) to confirm tele-phone communications capability. Request that a technical advisor be dispatched to the JPIC.

4.5.6 Contact the communications center at the PSB to confirm telephone communications.

4.5.7 Contact the Two Rivers Police Department and request that -

security officers be dispatched to the JPIC.

4.5.8 Under the direction of the JPIC director, perform administrative duties as required. .

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l EPIP 14.2

. MINOR Revision 7 06-27-86 PAGING SYSTEM OPERATION 1.0 GENERAL The purpose of this procedure is to list the steps necessary for proper communication over the paging system.

2.0 PRECAUTIONS & LIMITATIONS

$ 2.1 This procedure applies to pushbutton telephones only. If you have a j rotary dial telephone, have the control room make the page.

2.2 Maximum message length is 30 seconds when using the telephone.

3.0 PROCEDURE NOTE: INDIVIDUAL AND GROUP PAGER NUMBERS ARE FOUND ON FORM EPIP-22, " PLANT PERSONNEL EMERGENCY CALL LIST," IN THE CALL LIST TAB 0F THIS MANUAL.

< 3.1 Paging From the Site

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3.1.1 Dial on a PBX telephone.

3.1.2 Listen for a relatively loud beep.

3.1.3 Dial the desired group or individual number (See form EPIP-22, " Plant Personnel Emergency Call List").

3.1.4 Listen for the beeping tone.

3.1.5- Wait approximately 3 seconds after the tone then state your message and hang up.

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3.1.6 Personnel directed to come to the site should be told to place their paging unit in the monitor (thunderbolt) position.

NOTE: THIS WILL ALLOW LONG MESSAGES TO BE TRANSMITTED BY USING FM RADIOS WHICH THE PAGING UNIT SHOULD RECEIVE.

-. ~ - - - - _

EPIP 14.2 Page 2 3.2 Paging from Offsite 3.2.1 Call the plant.

3.2.2 Ask for Ext.

3.2.3 Repeat Steps 3.1.2 through 3.1.6.

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EPIP 16.1 1 ,_ . MINOR Revision 9 06-27-86 HEADQUARTERS SUPPORT NOTIFICATION AND RESPONSE 1.0 GENERAL 1.1 Establish notification responsibilities and sequence for designated Corporate Nuclear Power Department personnel.

1.2 Provide notification to specific corporate offices and corporate personnel.

1.3 Augment the emergency organization human resources as necessary 4

during a Point Beach Nuclear Plant condition classified as an alert, site emergency, or general emergency in accordance with the Emergency Plan Implementing Procedures.

NOTE: NECESSARY PHONE NUMBERS ARE FOUND ON FORM EPIP-25, "WE HEADQUARTERS SUPPORT PERSONNEL EMERGENCY CALL LIST."

2.0 PRECAUTIONS AND LIMITATIONS

k. 2.1 If unable to contact an individual, continue with the notification of the other individuals and then attempt to contact the persons who have not been notified.

2.2 All notifications should be appropriately logged on Attachment 16.1-1.

3.0 INITIAL CONDITIONS Alert, site emergency or general emergency conditions exist.

i 4.0 PROCEDURE j

4.1 Eme'rgency Support Manager 4.1.1 Contact the Emergency Director listed on EPIP-25 and discuss the emergency classification.

4.1.2 Contact the Communications Department. Telephone numbers are found in Section 2 of EPIP-25. Assure that the Comrunica-tions Department representative is aware of whether .the 3 occurrence is an emergency, or a nonemergency event. If it '

is an emergency event, provide the correct classification of the event and a determination as to whether the JPIC should be activated.

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EPIP 16.1

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I 4.1.3 Contact as appropriate other designated Nuclear Engineering personnel listed on EPIP-25.

4.1.4 Report to the emergency operations facility and assume responsibility for its operation.

l 4.1.5 Establish a communications link with the technical support center and joint public information center as soon as practicable. {

4.2 Emergency Director

, 4.2.1 Report to WE corporate headquarters and coordinate as appro-priate WE general office emergency response and recovery i

operations in support of the plant's emergency and recovery effort.

4.2.2 Establish a communications link with the emergency opera- ~

tions facility as soon as practicable.

4.3 Designated Nuclear Engineering Personnel (Technical Support Centerl

( (See Emergency Plan Figures 5-4, 5-5, and 5-6 for individuals

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reporting to the technical support center.) l Report to the technical support center.

4.4 Designated Nuclear Engineering Personnel (Emergency Operations Facility)

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(See Emergency Plan Figures 5-5 and 5-6 for individuals reporting to the emergency operations facility. This would include the RadCon/ l Waste Manager.)

4 Report to the emergency operations facility.

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---.-- --- - - - - - - - - - - - - - - - - ~ ~ " " ~ ~ ~ ~ " ~ ~ ~ ~ ~ ~

POINT BEACH NUCLEAR PLANT TECHNICAL SUPPORT CENTER ACTIVATION CHECKLIST This checklist should be completed by the Technical Support Manager or designee prior to fonmal activation of the technical support center.

Physical setup complete. (Tables, chairs, etc.)

Telephones installed and operability verified.

Emergency Plan Implcmenting Procedures (EPIP's) in place near dose plotting map.

Operating Procedures (OP's) and Emergency Operating Procedures t (EOP's) have been obtained from front office.

Status boards initialized.

Ventilation system in emergency mode.

Date and time indicated on TSC chart recorders -

l Positions identified in EPIP 6.5, Section 3.1 have been filled.

Persons filling the positions have reported to the TSC.

Technical support center staff h'as been briefed by the Technical Support Manager regarding TSC staff assignments and plant status.

[

i Activation of iodine and noble gas monitors is complete.

(EPIP 6.5S9.0)

Following satisfaction of the items listed above, contact the control room to formally assume responsibility for each of the following items as appropriate:

Area of Responsibility Time Transferred to TSC

1. Offsite communication / notification (2400 Clock)
2. Offsite radiological assessment (2400 Clock)
3. Offsite protective action recommendations (2400 Clock)
4. Other(s) l (2400 Clock) 1 Form Completed by:

(EPIP-20)

(06-86)

i ,

P0ZNT BEACH NUCLEAR PLANT EMERGENCY OPERATIONS FACILITY ACTIVATION CHECKLIST

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This checklist should be completed by the Emergency Support Manager, Site Manager or designee prior to formal activation of the Emergency Operations i

Facility (EOF), '

Setup of tables, chairs, etc. complete. (EPIP 6.752.1).

2 Telephone installed and operability verified. (EPIP 6.7, Sections 2.2 and 2.3) l One copy each of the Emergency Plan and Emergency Plan Implementing

, Procedures (EPIP's) distributed to the table in front of the chalk t

board and the table near the dose plotting map. (EPIP 6.7S2.5) j Status boards initialized.

1 Access to TSO and MAD (mainframe computer dose projection program complete).

l j Ventilation system i1 emergency mode. (EPIP 6.754.0)

'I Persons filling the following positions have reported to the EOF:

Site Manager Emergency Support Manager Two Duty Technical Advisors Rad / Con Waste Manager l

S.. Emergency operations center staff has been briefed by the Site Manager or Emergency Support Manager regarding EOF staff assignments, plant status and offsite status.

4 Activation of iodine and nobel gas radiation monitors complete.

(EPIP 6.758.0)

Following satisfaction of the items listed above, contact the technical support center to formally assume responsibility for each of the following items as appropriate:

Area of Responsibility Time Transferred to EOF

1. Offsite conuiunication/ notification (2400 Clock)
2. Offsite radiological assessment (2400 Clock)
3. Offsite protective action j recommendations (2400 Clock) i
4. Other(s)

i j (2400 Clock)

Form Completed By:

l EPIP-21 (06-86)

PLANT PERSONNEL EMERGENCY CALL LIST f

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1. Duty & Call Superintendents (Pager Group No. )

Name Pager No.

l Plant Ext. Home Phone Time Notified

2. Shift Superintendents Name Plant Ext. Home Phone Time Notified I

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EPIP-22 (06-86) Page 1 of 4 i

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3. Chemistry (Pager Group Nos. )

Name Pager No. Plant Ext. Home Phone Time Notified I

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4. Health Physics (Pager Group Nos. )

Name Pager No. Plant Ext. Home Phone Time Notified k.

5. Instrumentation & control (Pager Group Nos )

Name Pacer No. Plant Ext. Home Phone Time Notified i

EPIP-22 (06-86) Page 2 of 4

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6. Maintenance (Pager Group No. )

i i Name Pager No. Plant Ext. Home Phone Time Notified i

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j ( 7. Reactor Engineering l Name Plant Ext.

.i Home Phone Time Notified 4

. 8. Plant Administration & Security i

Name Pager No. Plant Ext.

.i IfomePhone Time Notified l

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_-. _ -- .. . . . . _ . = . - . . . . - . - . _ - - - . - . . . - . -- . -. . - - _ .

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9. Emergency Planning i

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10. Duty Technical Advisors (Group Nos. )

Name Pacer No. Plant Ext. Home Phone Time Notified 1

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1 NOTE: REFER TO PBNP FIRE PROTECTION MANUAL CALL LIST, i SECTION FEP 2.0. l j

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EPIP-22 (06-86) Page 4 of 4 l

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s OFFSITE AGENCY EMERGENCY CALL LIST 1

i FEDERAL AGENCIES:

1. United States Nuclear Regulatory Commission Telephone Person Time Name Frequency Number Notified Notified Initials NRC Operations All hours Red Phone Center i NRC Office of All hours Inspection and (Ask for Enforcement, Duty Officer)

Region III NRC Resident Inspectors: Pager Plant Ext. Home l

2. United States Department of Energy
Telephone Person Time Name Frequency Number Notified Notified Initials

( Chicago Operations Weekdays Center, Region V (8AM-SPM)

(Radiological Assistance Team) All other i hours -

3. United States Coast Guard Telephone Person Time Name Frequency Number Notified Notified Initials MSO, Milwaukee Day Night USCG, Sturgeon All hours Bay __

I USCG, Two All hours ,

Rivers ~~

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EPIP-23 Page 1 of 5 I

(06-86) l I_ _ _ _ _ . . _ . _ - - --_ _ _ - - - - - - - - - - - - - - - - - - - -~-~-- - -

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{ 4. United States National Weather Service j Telephone Person Time Name Frequency Number Notified Notified Initials i -

NWS, Green Bay All hours l,

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l STATE OF WISCONSIN AGENCIES 1

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i Name Telephone Person Time {

Frequency Number Notified Notified Initials ,

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l l Wisconsin Dept. of Weekdays Health and Social {

] (9AM-5PM) i Services, Section of Radiation Pro-tection i

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Wisconsin Division All hours I i

of Emergency l

1 Government Wisconsin State All hours

Patrol - Madison 1

l COUNTY AGENCIES r

1. Manitowoc County Telephone Person Time j Name Frequency Number Notified Notified Initials Manitowoc Ccanty All hours

! Sheriff l

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EPIP-23 Page 2 of 5 (06-86) l l

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2. Kewaunee County Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee County All Hours Dispatcher 0FF-3ITE AGENCIES SUPPORTING JPIC ACTIVATION Telephone Person Time Name Frequency Number Notified Notified Initials Phone Service at Community House All Hours All Hours Superintendent of Office Schools , Kewaunee City of Two Rivers All Hours Police Dept All Hours PRIVATE AGENCIES Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee Nuclear All hours Power Plant Institute of All hours Nuclear Power Operations i
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1

o PRIVATE AGENCIES (Cont'd.)

Telephone Person Time Name Frequency Number Notified Notified Initials American Nuclear Insurers All hours Westinghouse Electric Corp.

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Milwaukee seismic Center Wisconsin Public Service Corp.

(EOF Power)

EPIP-23 Page 4 of 5 (06-86)

s FIRE AND MEDICAL AGENCIES

1. Fire Emergency Telephone Person Time Name Frequency Number Notified Notified Initials Two Creeks Fire All hours Department
2. Medical Assistance ~

Telephone Person Time Name Frequency Number Notified Notified Initials Emergency All hours Vehicle Ambulance Community Hos- All hours pital, Two Rivers Doctors Clinic. Ltd.

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University Hos-pital, Madison Emergency Room All hours EPIP-23 Page 5 of 5 (06-86)

POINT BEACH NUCLEAR PLANT EMERGENCY RESPONSE FACILITY TELEPHONE DIRECTORY l

Extension Phone

, Technical Support Center

Site Manager i

Plant Operations Manager

! Health Physics Supervisor & Chemists Core Physics coordinator Systems Analysis & Procedural Support Coordinator i

Operations Support Center i

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Health Physics counting Area 4

5 Emergency Operation Facility

! Emergency Support Manager

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Offsite Communicator j Rad / Con Waste Manager

{ Radiation Dose Projection 1

i j Site Boundary Control Center Offsite Health Physics Director i  !

I EPIP-24 Page 1 of 2

(06-86)

. . - . . _- .= . . - - .

Joint Public Information Center JPIC Director Corporate Emergency Response Center i

Emergency Director i

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  1. 4 POINT BEACH NUCLEAR PLANT WISCONSIN ELECTRIC

, HEADQUARTERS SUPPORT PERSONNEL EMERGENCY CALL LIST NOTE: ALL TELEPHONE NUMBERS WITH A PREFIX MAY BE DIALED FROM POINT BEACH ON THE PBX SYSTEM NOTE: ALL TELEPHONE NUMBERS ARE IN THE "414" AREA, UNLESS OTHERWISE INDICATED.

1. NUCLEAR POWER DEPARTMENT Time Name Pager No. Company Ext. Home Phone Notified i

G EPIP-25 Page 1 of 3 (06-86)

+ 9 7- 1. NUCLEAR POWER DEPARTMENT (Cont'd.)

Time Name Company Ext. Home Phone Notified l

i j 2. COMMUNICATIONS DEPARTMENT NOTIFICATION (A) Media Line (0700 - 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> Monday - Friday )

(B) After Hours Listing:

Call the following list of Communications Department Personnel, in order, until one is reached:

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3. COMPANY ADMINISTRATION & DEPARTMENTS Time Name Company Ext.

, Home Phone Notified i

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- 4. OTHERS .

Time Name Company Ext. Home Phone Notified a

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POINT BEACH NUCLEAR PLANT REACTOR COOLANT POST ACCIDENT SAMPLING ANALYSIS REPORT 1.0 ANALYSIS OF GASEOUS SAMPLE 1.1 Hydrogen Analysis 1.1.1 Scale used on gas partitioner 1.1.2 Millivolt reading on chart recorder 1.1.3  % hydrogen from calibration curve 1.1.4 Volume of sample bomb in ml 1.1.5 Atmospheric pressure (mm/Hg) 1.1.6 cc/Kg hydrogen in coolant * (STP)

  • cc/Kg H 2{8TI)"(kb}*(1 4)
  • hb x 1000

( = 3.68 (1.1.3 x (1.1.5)

(1.1.4) 1.2 Radioactive Noble Gases 1.2.1 Decay time in minutes 1.2.2 Sample count time in seconds 1.2.3 Detector 1.2.4 Geometry 1.2 t5 Common multiplier

  • 1.2.6 Volume of sidearm flask 280
  • CM = _(1.1.4)0.5 x (1.2.6)

= 560 x (1.2.6) .

(1.1.4)

(1) See Section 5.2.2 of EPIP 7.3.2.

EPIP-30 (06-86)

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1.2.7 MCA Results

Isotope Concentration (pci/cc)

Xe-133 Kr-85m Kr-88 Xe-133m Xe-135 Xe-138 4 Kr-87 Xe-135m Ar-41 Kr-85 Xe-131m NOTE: THE FOLLOWING ARE NOT REQUIRED. HOWEVER, IF TIME

, PERMITS, ANALYSIS OF AS MANY AS POSSIBLE WILL HELP IN THE COMPLETION OF EPIP 1.7, " CORE DAMAGE ESTIMA- ~

TION PROCEDURE."

Rb-88 Cs-134

' .' Cs-137 -

Te-132 Ba-140 l La-140 La-142 2.0 ANALYSIS OF LIQUID SAMPLE t

2.1 Boron and pH 2.1.1 Volume of sample ml 2.1. '2 pH of sample i

2.1.3 Normality of NaOH ,l 1

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l EPIP-30 (06-86)

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'x Page 3 2.1.4 Volume of NaOH used al 2.1.5 Concentration of boron

  • ppm
  • ppe Boron = ,'y,'fx(2.1.4)x10810 2.2 Chloride 2.2.1 Chloride concentration ppm 2.3 Iodine Analysis 2.3.1 Decay time min 2.3.2 Sample count time sec 2.3.3 Detector 2.3.4 Geometry 2.3.5 Common multiplier *
  • CM = xF S

V, = Volume of sample (first dilution)

F = Any additional dilution factors (2 or more dilutions)

(1) See Section 5.4.3 of EPIP 7.3.2.

2.3.6 MCA Results Isotope Concentration (WCi/cc)

I-130 I-131 I-132 I-133 I-134 I-135

. Total EPIP-30 (06-86)

4 Page 4 3.0 ROUTING AND APPROVAL Date Initials

.j 3.1 Calculations completed by 3.2 Analysis completed by 3.3 Chemistry Director

{ 3.4 Health Physics Director 3.5 Technical Support Manager l

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POINT BEACH NUCLEAR PLANT CONTAINMENT ATMOSPHERE POST-ACCIDENT SAMPLING ANALYSIS REPORT 1.0 HYDROGEN ANALYSIS 1.1 Scale used on gas partitioner 1.2 Millivolt reading on chart recorder 1.3  % hydrogen from calibration curve 2.0 RADI0 ACTIVE NOBLE GAS ANALYSIS 2.1 Decay time in minutes 2.2 Sample count time in seconds

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2.3 Detector 2.4 Geometry 2.5 Number of dilutions : (D) 2.6 Common multiplier *

  • CM = (D)1 x 0 x (Pressure-Temperature Correction)

(1) See Section 5.3.3 of EPIP 7.3.3. One or more dilutions may be necessary.

2.7 Pressure-Temperature Correction

, (Pc + 14.7)(Tg + 459)

Pg (Tc + 459)

Where Pc = Pressure in Containment (psig)

Tc = Temperature in Containment (*F) '

P = Pressure in Lab (psi) where P = 14.7 x "" "

l L 760 (mm Hg) I 1

T = Temperature in Laboratory (*F)

I EPIP-31 (06-86)

)

. Page 2 2.8 Results of MCA Isotope Concentration (pci/ce)

Xe-133 Kr-85m Kr-88 Xe-133m Xe-135 Xe-138 Kr-87 Xe-135m Ar-41 Kr-85 Xe-131m _

NOTE: THE FOLLOWING ARE NOT REQUIRED. HOWEVER, IF TIME .

PERMITS, ANALYSIS OF AS MANY AS POSSIBLE WILL HELP IN THE COMPLETION OF EPIP 1.7, " CORE DAMAGE ESTIMA-TION PROCEDURE."

Rb-88 Cs-134 Cs-137 Te-132

Ba-140 La-140 La-142 3.0 RADIOACTIVE IODINE ANALYSIS 3.1 Decay time in minutes 3.2 Sample count time in seconds 3.3 Detector 3.4 Geomitry 3.5 Pressure-Temperature Correction (Same as >

Section 2.7)

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EPIP-31 l (06-86)

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Page 3 3.6 Rcsults of MCA Isotope Concentration (pCi/cc)

I-130 I-131 I-132 I-133 I-134 I-135 4.0 ROUTING & APPROVAL Date Initials 4.1 Calculations completed by 4.2 Analysis completed by 4.3 Chemistry Director 4.4 Health Physics Director

. 4.5 Technical Support Manager e

I e

EPIP-31 (06-86)

POINT BEACH NUCLEAR PLANT SEARCH & RESCUE AND EMERGENCY OPERATIONS CHECKLIST Consider the following items during final briefing of search and rescue team in the operations support center:

1. Dosimeters (TLDs and SRDs)
2. Protective clothing.
3. Respiratory protection and projected time to depletion.
4. Thyroid blocking agent.
5. Radio communications include spare batteries.
6. Keys
7. Information as to intent of team, suggested routes, dose rates, and precautions.

(

8. Backout areas.
9. Portable survey instruments.
10. Exposure limits.
11. Existing personnel exposure balance.
12. First aid qualification.
13. Answer any questions.

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14. Procedural checkoff.
15. Trauma kit or first aid kit
16. Air sampler and filters
17. Portable lighting EPIP-32 l

(06-86)  ;

EPIP 6.7 MINOR f- Revision 4 1

06-27-86 EMERGENCY OPERATIONS FACILITY ACTIVATION 1.0 PURPOSE 1.1 To provide instructions for the activation of the emergency operations facility after the declaration of an alert, site emergency or general emergency.

1.2 To outline the emergency operations facility ventilation system operation in the event of high airborne activity.

2.0 ACTIVATION OF EMERGENCY OPERATIONS FACILITY 2.1 Set up tables as shown on Attachment 6.7-1. They may be obtained from rooms adjacent to the operations area.

2.2 Install phones, which may be found in the NRC office, in the appropriate areas as shown on Attachment 6.7-1.

_ 2.3 Confirm that all phones operate by noting if dial tone is present when l l

(< the receiver is lifted. Confirm that the numbers listed on the face l of the phone matches the number on the wall jacks. '

2.4 Install telecopier (obtain from HP office in the extension building).

2.5 Distribute paper and pencils to each table.

2.6 Distribute one copy each of the Emergency Plan and EPIP's to the table in front of the chalk board and the table near the dose plotting map (see Attachment 6.7-1).

2.7 Shift the ventilation system from normal to the emergency operating mode per Section 4.2.

2.8 Turn on the sample pump for the iodine and noble gas monitors per l Section 8.0.

3.0 ACTIVATION OF EOF PERSONNEL 3.1 Health Physics Personnel See EPIP 7.2.1, " Activation of Health Physics Facilities at Emergency Operations Facility," for activation of health physics personnel.

EPIP 6.7

. Page 2 3.2 Site Manager 3.2.1 Personnel to fill the following positions have not been contacted, proceed to do so.

Emergency Support Manager Rad / Con Waste Manager 2-Duty Technical Advisors 3.2.2 If any followup data is available which may be of help to offsite agencies, have that information relayed to those agencies.

3.3 Emergency Support Manager 3.3.1 Assume responsibility for offsite radiological assessment, dose projection and offsite protective action recommendations as soo'n as the EOF is staffed sufficiently to take that responsibility. Fonnalize the transfer of respor.sibilities by using Form EPIP-21, " EOF Activation Checklist." -

(Attached) 3.3.2 Assume responsibility from the TSC, for status update com-munications with offsite agencies as soon as able.

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\- 3.4 Rad / Con Waste Manager Provide dose projections, offsite survey direction, and offsite protective action recommendations to the appropriate emergency organization personnel.

4.0 EMERGENCY VENTILATION SYSTEM 4.1 The EOF heating and ventilation system has a normal and emergency ,

operation mode. Under all modes of operation any fresh air is taken  ;

in from a vent on the south end of the west wall of the building. l The . intake air under normal operation is coarsely and electrostatically filtered.

i In the emergency mode, a minimum of outside air is taken in and a high efficiency particulate air filter is added to the filter media.

4.2 To shift the heating, ventilating and air conditioning system from normal to emergency mode, manually select the emergency position of switch S3 on control panel M1 located on the south wall of the mechanical equipment room. Access to this room is obtained from the men's locker room.

O EPIP 6.7

, Page 3

/

5.0 EOF POWER SUPPLY Power supply to the EOF is obtained from Wisconsin Public Service Corporation distribation feeder. In case of total power failure, call Wisconsin Public Servici Corporation. See form EPIP-23, 'Offsite Agency Emergency Call List."

6.0 EOF ANLUNCIATOR PANEL 6.1 The annunciator par.1 monitors 8 parameters in the building. The control room will re eive an alarm upon annunciation of any of the 8 alarms.

6.2 Alarms " holding tank high level" and " dosing tank high level" will announce upon tank high level. The holding tank must be pumped by a contractor. The dosing tank has an internal pump which pumps the contents to the mound septic system.

6.3 The " fire detector" annunciates upon the detection of a fire.

6.4 The " emergency mode" window annunciates upon switchover to the emergency mode of the HVAC system.

6.5 The " building temperature low" window lights upon exceeding the ks setpoint for the building temperature. This usually indicates a heating system failure.

l 6.6 If a pump has not started after a 30-second delay upon demand from control panel M-1, the " pump failure" window will light.

6.7 The " air filter plugged" window will light when the electrostatic air filter is plugged and the differential pressure across the filter exceeds the setpoint.

6.8 The " compressed air low pressure" window will light when the air pressure in the supply header to the Johnson Control control system falls below the setpoint.

7.0 ACCESS OF TSO AND MAD 7.1 Power up the terminal and modem and set the modum (right-most switch) to "MA."

7.2 Call our switchboard operator (Dial "0") or the control room (after hours) and ell him/her to transfer and the next "FX" call to extensio 7.3 Place the phone call to the WE computer by dialin

p ._

4 EPIP 6.7 Page 4

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7.4 Following an answer by the security equipment at the Pewaukee Data Center, wait about 10 seconds then enter on the phone touchtone key pad the appropriate predefined 6-digit location identifier number (LIN) which relates- r calling location. The LIN for this terminal location 1 NOTE: IF THE PROPER CODE IS NOT ENTERED OR NOT RECOGNIZED, THE SECURITY EQUIPMENT SIMPLY TERMINATES THE CALL. IT WILL THEN GE NECESSARY TO RETURN TO STEP 7.2.

7.5 A proper code is acknowledged with a tone. Once this tone is heard, the phone which originated the call should be hung up. The security hardware will automatically disconnect the call.

7.6 Within 15 to 30 seconds, the security equipment will place a call back to the number that relates to the LIN which was entered.

7.7 In a correct sequence of events, the user's phone will ring. After picking up the receiver, enter the "*" key on the touchtone key pad. -

This lets the security equipment know that its call was received and a data carrier is to be provided.

7.8 Once the carrier signal is heard, change the setting on the modem (right-most switch) to the "DA" position.

7.9 The terminal will respond with:

ACF82003 ACF2, ENTER LOGON ID-7.10 Using the deckwriter keyboard, enter the letters "PB" followed by your 4-number, TSO user ID and account number

<PB#### A(0479)>

To ENT'ER, press " Return."

7.11 The terminal will respond with:

ACF82004 ACF2, ENTER PASSWORD -

7.12 Using the deckvriter keyboard, enter your password.

(Up to 8 alphanumeric characters)

To ENTER, press " Return."

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A EPIP 6.7

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Page 5 e 7.13 A correct ID and password results in access to TSO. After: a l

successful LOGON, TSO will respond - l READY <

7.14 To gain access to MAD, enter - - l MEX 'PBNP. MAD.CLIST'>

7.15 HELP -

2 ems executing Steps 17.1/- 7.13, contacttthe HELP desk

- If you experiene fficulty in gainisg access to MAD, . contact Jim Knorr at Ext 8.0 ACTIVATION OF IODINE 7 NOBLE GAS RADIATION 10NITORS

~ 1.^f ,

8.1 1

Coordinate with tberoff-site Health Physics Director to:have the iodine and noble gas sample pump star.ted..mThe pump is.in .the heating

- and ventilation room adjacent to the inents lavoratory. Ensure that a new charcoal cannis:ter is installed and that2 the initial sample flow rate and start time are recorded.

g 8.2 Interpretation of RMS readouts .!

8.2.1 The concentration of noble gas is7 determined by, multiplying the observed concentrate onethe" readout labeled."RE-242" by the calibration constant posted adjacent to the uieter. The units are\pci/cc Xe-133 dose' equivalents. .-i q 8.2.2

- The iodincactivity on the charcoal cartridge ~. is robtained by multiplying the observed countrate on the readout labeled "RE-241" by the calibration: constant posted adjacent to the meter. The units are pCi - !I-131 dose equivalents.

8.2.3 To convert:the iodine activityiinto a concentration, calculate the volume of air that . passed through the filter.

The concentration of iodine is approximately the. activity on the filter (pci) divided by th6. total volume (cm3) for sampling periods less than .12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, assuming no short-lived isotopes are present.

J

a e EPIP 6.7

. Page 6 f

NOTE: FOR LONGER SAMPLING PERIODS AND WHEN SHORT-LIVED IODINE ISOTOPES ARE EXPECTED TO BE PRESENT, THE FOLLOWING FORMULA MAY BE USED TO CALCULATE THE IODINE CONCENTRATION:

e s C=

~

F p(1-e s)

Where: Units C = concentration in air pCi/cc F = sample volume A = decay cons. ant, 0.693T\ cc ,1 min A = total activity on filter pCi t = elapsed time from sample stop to count start min t = total sample time min p' = filter collection efficiency 8.2.4 Any changes to the alarm setpoints shall be made in accordance with the Radiation Monitoring System Alarm Setpoint Response Book (RMSASRB) kept in the control room.

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.6c use Dy computer terminal I 1 I l i

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PAGING SYSTEM OPERATION 1.0 GENERAL The purpose of this procedure is to list the steps necessary for proper communication over the paging system.

2.0 PRECAUTIONS & LIMITATIONS 2.1 This procedure applies to pushbutton telephones only. If you have a rotary dial telephone, have the control room make the page.

2.2 Maximum message length is 30 seconds when using the telephone.

3.0 PROCEDURE NOTE:

INDIVIDUAL AND GROUP PAGER NUMBERS ARE FOUND ON FORM EPIP-22, " PLANT PERSONNEL EMERGENCY CALL LIST," IN THE CALL LIST TAB OF THIS MANUAL.

, 3.1 Paging From the site .

3.1.1 Dia n a PBX telephone.

3.1.2 Listen for a relatively loud beep.

3.1.3 Dial the desired group or individual number (See form EPIP-22, " Plant Personnel Emergency Call List").

3.1.4 Listen for the beeping tone.

3.1.5 Wait approximately 3 seconds after the tone then state your message and hang up.

3.1.6 Personnel directed to come to the site should be told to place their paging unit in the monitor (thunderbolt) position.

' NOTE: THIS WILL ALLOW LONG MESSAGES TO BE TRANSMITTED BY USING CHANNEL 3 ON THE RED FM RADIOS WHICH THE PAGING UNIT SHOULD RECEIVE.

w

\

EPIP 14.2

. Page 2 I

3.2 Paging from Offsite 3.2.1 Call the plant.

3.2.2 Ask for Ext. 334 or 335, 3.2.3 Repeat Steps 3.1.2 through 3.1.6.

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1 PLANT PERSONNEL EMERGENCY CALL LIST

1. Duty & Call Superintendents (Pager Group No. S501) l Name Pager No. Plant Ext. Home Phone Time Notified
2. Shift Superintendents l l'

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i EPIP-22 (06-86) Page 1 of 4

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3. Chemistry (Pager Group No -

Name Pager No. Plant Ext. Home Phone Time Notified l

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4. Health Physics (Pager Group Nos. S540 & S530)

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5. Instrumentation & Control (Pager Group Nos. S520)

Name Pager No. Plant Ext. Home Phone Time Notified EPIP-22 (06-86) Page 2 of 4

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6. Maintenance (Pager Group No l

Name Pager No. Plant Ext. Home Phone Time Notified I

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8. Plant Administration & Security Name Pager No. Plant Ext. Home Phone Time Notified I

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9. Emergency Planning -

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11. Fire Brigade Members NOTE: REFER TO PBNP FIRE PROTECTION MANUAL CALL LIST, SECTION FEP 2.0.

EPIP-22 (06-86) Page 4 of 4 i

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0FFSITE AGENCY EMERGENCY CALL LIST r~

i' l FEDERAL AGENCIES:

1. United States Nuclear Regulatory Commission Telephone Person Time Name Frequency Number Notified Notified Initials NRC Operations All hours Red Phone Center or NRC Office of All hours Inspection and (Ask for Enforcement, Duty Officer),

Region III NRC Resident Inspectors: Pager Plant Ext. Home R. L. Hague

2. United States Department of Energy Telephone Person Time Name Frequency Number Notified Notified Initials Chicago Operations Weekdays '

l N. Center, Region V (8AM-5PM)

(Radiological Assistance Team) All other hours I

l 3. United States Coast Guard Telephone Person Time Name Frequency Number Notified Notified Initials MSO, Milwaukee Day Night USCG, Sturgeon All hours Bay USCG, Two All hours Rivers EPIP-23 Page 1 of 5 (06-86)

2 l

4. United States National Weather Service Telephone Person Time Name Frequency Number Notified Notified Initials NWS, Green Bay All hours STATE OF WISCONSIN AGENCIES Telephone Person Time Name Frequency Number {

Notified Notified Initials Wisconsin Dept. of Weekdays ,-

Health and Social (9AM-SPM)

Services, Section of Radiation Pro-tection Lawrence J. McDonnell, Chief, Radiation Protection Section Wisconsin Division All hours of Emergency Government Wisconsin State All hours

Patrol - Madison I

J COUNTY AGENCIES:

1. Manitowoc County Telephone Person Time Name Frequency Number Notified Notified Initials Manitowoc County All hours Sheriff r EPIP-23 Page 2 of 5 (06-86)

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! 2. Kewaunee County Telephone Person Time l Name Frequency Number Notified Notified Initials Kewaunee County All Hours Dispatcher -

0FF-SITE AGENCIES SUPPORTING JPIC ACTIVATION Telephone Person Time Name Frequency Number Notified Notified Initials 1 Howard Perry - Home Director, Two Rivers Office l Community House l

l Steve Nenonen - Home Manager, City office of Two Rivers Phone Service at Communit s GTE % y House xchange) All Hours j AT&T (Ringdown &

j PBX) All Hours R. F. Plantico - Home Superintendent of Office Schools , Kewaunee

! City of Two Rivers All Hours

Police Dept All Hours 4

Chief Thome l

PRIVATE AGENCIES Telephone Person Time Name Frequency Number Notified Notified Initials Kewaunee Nuclear All hours Power Plant Institute of All hours Nuclear Power Operations l

EPIP-23 Page 3 of 5 (06-86)

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PRIVATE AGENCIES (Cont'd.)

Telephone Person Time Name Frequency Number Notified Notified Initials All hours office Home Office Home Office Horne Office Home Office Office Home

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Office Office Home Office ffice EPIP-23 Page 4 of 5 (06-86)

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FIRE AND MEDICAL AGENCIES

1. Fire Emergency Telephone Person Time Name Frequency Number Notified Notified Initials Two Creeks Fire All hours Department
2. Medical Assistance Telephone Person Time 1 Name Frequency Number Notified Notified Initials l Emergency All hours ~~ l Vehicle l Ambulance l

Community Hos- All baurs pital, Two Rivers Doctors Clinic, Ltd.  !

S. Lawrence Kaner, M.D.  !

\m Gerry R. Geroso, M. D. i

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University Hos-pital, Madison Emergency Room All hours Frank C. Larson, M.D.

Michael Garvin Robert R. Radtke, Ph.D.

(Health Physicist)

EPIP-23 Page 5 of 5 (06-86)

iM-4 POINT BEACH NUCLEAR PLANT EMERGENCY RESPONSE FACILITY TELEPHONE DT'lECTORY Extension Phone Technical Support Center M. . ( .'. / Q.'" " I ' 2;JC '.t. ,'-f. .%.

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HEADQUARTERS SUPPORT PERSONNE5 E ,g EMERGENCY CALL LIST

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NOTE: ALL TELEPHONE NUMBERS WITH REFIX MAY BE DIALED FROM POINT BEACH ON THE PBX SYSTEM WITH AN OWED BY THE LAST 4 DIGITS OF THE NUMBER.

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EPIP-25 Page 2 of 3 (06-86)

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4. OTHERS Name Time Company Ext. Home Phone Notified ll I

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l l l l l EPIP-25 Page 3 of 3 (06-86) l i l l i

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR: O' C70201 '7 DOC.DATE: 86/06/27 NOTARIZED: NO DOCKET # FACIL: 50-266 Point Beach Nuclear Plant, Unit 1. Wisconsin Electric 05000266 50-301 Point Beach Nuclear Plant, Unit 2, Wisconsin Electric 05000301 AUTH.NAME AUTHOR AFFILIATION - FAY,C.W. Wisconsin Electric Pouer Co. RECIP.NAME RECIPIENT AFFILIATION DENTON,H.R. Office of Nuclear Reactor Regulation, Direc tor (p ost 851125 LEAR,0. PWR Project Directorate 1 SUB JECT: Forwa*:s Central Files version of revised emergency plan implemening procedures including Rev 3 to EPIP 2.2, " Unusual Event-Plant & Company Personnel Notification." Withheld. DISTRIBUTION CODE: XOO5D COPIES RECEIVED: LTR Jb ENCL _SI ZE: f d" l J TITLE: Emerg Plan (CF Avail) NOTES: RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME LTTR ENCL ID CODE /NAME LTTR ENCL PWR-A PD1 LA 1 0 PWR-A PD1 PD 1 0 COLBURN,T 1 1 E$ )f INTERNAL: D  %$ 1 1 IE/DEPER/EPB 4Q 2_ 2 IE/DEPER/IRB 4pg, 1 1 REG FILES / i 1 4 TOTAL NUMBER OF COPIES REGUIRED: LTTR 8 ENCL 6 \ J

        #         o s                       UNITED STATES 8          ~%              NUCLEAR REGULATORY COMMISSION
      ;               y                    WASHINGTON, D. C. 20555 July 15',1986
       %, . . . . . ,o/

50-266/301 Point Beach MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Division of Rules and Records, ADM

SUBJECT:

REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has detennined that it may now be made publicly available.

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Donnie H. Grimsley, Director Division of Rules and Records Office of Administration - p

Attachment:

As stated t B 4 A}}