Text

Emergency Plan Implementing Procedures - F3
	ML021440429
Person / Time
Site:	Prairie Island
Issue date:	05/06/2002
From:	Nazar M; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Security and Incident Response
References
	Download: ML021440429 (81)
	v • d • e

NMC E Mano K. Nazar Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Dr. East e Welch MN 55089 May 6, 2002 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 Docket Nos. 50-306 License Nos. DPR-60 Prairie Island Emergency Plan Implementing Procedures - F3 Emergency Response Plan Implementing Procedures Furnished with this letter are the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures F3. This revision includes the following procedures:

INDEXES: Emergency Plan Implementing Procedures TOC REVISIONS F3-9 Emergency Evacuation Rev 17 F3-10 Personnel Accountability Rev 19 F3-11 Search & Rescue Rev 8 F3-16 Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release Rev 17 F3-13.4 Midas Meteorological Data Display Rev 7 F3-13 Offsite Dose Calculations Rev 15 F3-13.3 Manual Dose Calculations Rev 11 DELETIONS INSTRUCTIONS:

Please post changes in your copy of the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures. Procedures, which have been superseded or deleted, should be destroyed.

,W4ý5

Please sign and return the acknowledgment of this update to Bruce Loesch, Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089.

If you have any questions, please contact Mel Agen at 651-388-1121 Extension 4240.

Mano K. Nazar Site Vice Presi t Prairie Island /clear Generating Plant c: USNRC - Steve Orth, Region IIm (2 copies)

NRC Resident Inspector (w/o attachment)

M Agen (w/o attachment)

Records Management (Doc Control Copy) (w/o attachment)

NL File (w/o attachment)

Mfst Num: 2002 - 0336 Date : 05/02/02 FROM Bruce Loesch/Mary Gadient Loc : Prairie Island TO UNDERWOOD, BETTY J Copy Num: 515 Holder : US NRC DOC CONTROL DESK SUBJECT : Revisions to CONTROLLED DOCUMENTS Procedure # Rev Title Revisions:

F3-9 17 EMERGENCY EVACUATION F3-10 19 PERSONNEL ACCOUNTABILITY F3-11 8 SEARCH & RESCUE F3-16 17 RESPONSIBILITIES OF THE RADIATION SURVEY T DURING A RADIOACTIVE LIQUID RELEASE F3-13.4 7 MIDAS METEOROLOGICAL DATA DISPLAY F3-13 15 OFFSITE DOSE CALCULATION F3-13 .3 11 MANUAL DOSE CALCULATIONS UPDATING INSTRUCTIONS Place this material in your Prairie Island Controlled Manual or File. Remove revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Loesch or Mary Gadient, Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,

Welch, MN 55089.

Contact Bruce Loesch (ext 4664) or Mary Gadient (ext 4478) if you have any questions.

Received the material stated above and complied with the updating instructions Date

I ~iI PRAIRIE ISLAND NUCLEAR

Title:

GENERATING PLANT j Emergency Plan Implementing Procedures TOC I Effective Date : 05/02/02 Approved By.:K7&icc 6Z14 BPS Supt I Document # Title Rev F3-1 ONSITE EMERGENCY ORGANIZATION 19 F3-2 CLASSIFICATIONS OF EMERGENCIES 29 F3-3 RESPONSIBILITIES DURING A NOTIFICATION OF UNUSUAL 18 EVENT F3-4 RESPONSIBILITIES DURING AN ALERT, SITE AREA, 28 OR GENERAL EMERGENCY F3-5 EMERGENCY NOTIFICATIONS 20 F3-5.1 SWITCHBOARD OPERATOR DUTIES 8 F3-5.2 RESPONSE TO FALSE SIREN ACTIVATION 9 F3-5.3 RESPONSE TO RAILROAD GRADE CROSSING BLOCKAGE 8 F3-6 ACTIVATION & OPERATION OF TECHNICAL SUPPORT CENTER 16 F3-7 ACTIVATION & OPERATION OF OPERATIONAL SUPPORT 15 CENTER (OSC)

F3-8 RECOMMENDATIONS FOR OFFSITE PROTECTIVE ACTIONS 19 F3-8.1 RECOMMENDATIONS FOR OFFSITE PROTECTIVE ACTIONS FOR 12 THE ON SHIFT EMERGENCY DIRECTOR /SHIFT MANAGER F3-9 EMERGENCY EVACUATION 17 F3-10 PERSONNEL ACCOUNTABILITY 19 F3-11 SEARCH & RESCUE 8 F3-12 EMERGENCY EXPOSURE CONTROL 14 F3-13 OFFSITE DOSE CALCULATION 15 F3-13.3 MANUAL DOSE CALCULATIONS 11 F3-13.4 MIDAS METEOROLOGICAL DATA DISPLAY 7 F3-13.5 ALTERNATE METEOROLOGICAL DATA 4 Page 1 of 3

PRAIRIE ISLAND NUCLEAR Title : Emergency Plan Implementing Procedures TOO GENERATING PLANT Effective Date : 05/02/02 Document # Title Rev F3-13.6 WEATHER FORECASTING INFORMATION 11 F3-14.1 ONSITE RADIOLOGICAL MONITORING 11 F3-14.2 OPERATIONS EMERGENCY SURVEYS 9 F3-15 RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS 22 DURING A RADIOACTIVE AIRBORNE RELEASE F3-16 RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS 17 DURING A RADIOACTIVE LIQUID RELEASE F3-17 CORE DAMAGE ASSESSMENT 9

F3-18 THYROID IODINE BLOCKING AGENT (POTASSIUM IODIDE) 9 F3-19 PERSONNEL & EQUIPMENT MONITORING & DECONTAMINATION 6

F3-20 DETERMINATION OF RADIOACTIVE RELEASE 17 CONCENTRATIONS F3-20.1 DETERMINATION OF STEAM LINE DOSE RATES 9

F3-20.2 DETERMINATION OF SHIELD BUILDING VENT STACK 9

DOSE RATES F3-21 ESTABLISHMENT OF A SECONDARY ACCESS CONTROL POINT 10 F3-22 PRAIRIE ISLAND RADIATION PROTECTION GROUP RESPONSE 16 TO A MONTICELLO EMERGENCY F3-23 EMERGENCY SAMPLING 18 F3-23.1 EMERGENCY HOTCELL PROCEDURE 11 F3-24 RECORD KEEPING DURING AN EMERGENCY 7

F3-25 REENTRY 8 F3-26.1 OPERATION OF THE ERCS DISPLAY 7

F3-26.2 RADIATION MONITOR DATA ON ERCS 6

F3-26.3 ERDS - NRC DATA LINK 1

F3-29 EMERGENCY SECURITY PROCEDURES 18 F3-30 TRANSITION TO RECOVERY 6

Page 2 of 3

PRAIRIE ISLAND NUCLEAR Title : Emergency Plan Implementing Procedures TOC GENERATING PLANT Effective Date : 05/02/02 Document # Title Rev F3-31 RESPONSE TO SECURITY RELATED THREATS 5 REVIEW OF EMERGENCY PREPAREDNESS DURING OR AFTER 2 F3-32 NATURAL DISASTER EVENTS Page 3 of 3

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENJCE~.V USE,'S

Proceduresegments may be performed from memory.

Use the procedure to verify segments are complete.

Mark off steps within segment before continuing.

Procedureshould be availableat the work location.

"O.C.REVIEW DATE: OWNER: EFFECTIVE DATE Z5.,M. Werner 012-O Page 1 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT PISDRINUMBER EMERGENCY PLAN IMPLEMENTIN

G. PROCEDURE

~S C

I' F3 SREV:

EMERGENCY EVACUATION F3-9 17 1.0 PURPOSE This procedure provides instructions for implementing 4n emergency evacuation of affected areas within the plant buildings or areas within'the site boundaries.

2.0 APPLICABILITY This instruction SHALL apply to all plant personnel who are involved withl evacuations caused by radiological hazards, fire, toxic gas, security threat, etc. This procedure does riot apply to the evacuation of the general public located in affected areas beyond the site boundary.

3.0 PRECAUTIONS 3.1 The Emergency Director (ED) should consider radiation shine from the containments as well as other hazards when determining the habitability requirements of the assembly areas and evacuation routes.

3.2 When the evacuation alarm is heard, evacuate your work area while listening to specific evacuation instructions on the plant's Public Address (PA) system. If you cannot hear or understand the instructions, continue to leave the immediate area until you learn of the evacuation instructions.

3.3 When personnel are working inside Containment or the Shield Bldg, the Access Lead Radiation Protection Specialist (RPS) should establish communications with Containment Lead RPS and keep them informed of PA announcements (cannot understand PA due to echo).

Page 2 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 4.0 RESPONSIBILITIES 4.1 The Emergency Director/Shift Manager (ED/SM) is responsible for ensuring that an appropriate evacuation (local, plant, or site) or an Early Dismissai is implemented when radiological or other conditions warrant such action.

4.2 The Radiological Emergency Coordinator (REC) is responsible to advise the ED/SM on choosing an appropriate Assembly Point and need for evacuation.

4.3 The Control Room is responsib!e to sound the evacuation alarm and make the appropriate announcement over the plant's public address system.

4.4 The Assembly Point Coordinator is responsible to coordinate the activities at the designated assembly area.

4.5 All plant personnel are responsible tofollow the directions given over the plant's public address system and by the Assembly Point Coordinator.

4.6 The Security Team is responsible to assist in the personnel accountability process and plant access control.

4.7 The Technical Support Center (TSC) Coordinator is responsible for assisting work group leaders in determining nonessential personnel and reporting to ED when determination essential personnel is complete.

4.8 TSC work group leaders are responsible in determining essential and nonessential personnei.

5.0 DISCUSSION - See Attachment 1 6.0 PREREQUISITES 6.1 It has been determined that a personnel hazard exists or may exist; such as; radiological contamination, high radiological dose rates, fire, toxic gas, security threat, etc.,

OR 6.2 A Site Area or General Emergency has been declared.

Page 3 of 22

PRAIRIE ISLAND NUCLEAR GENERAT!NG PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 EMERGENCY EVACUATION REV REV:

F3-9 17 I 7.0 PROCEDURE 7.1 Early Dismissal An Early Dismissal may be warranted during an Alert classification if it is determined that the emergency may escalate to a higher !evel or may involve a hazardous Dismissal.

An Early Dismissa; of personnel should proceed as follows:

SNo Early Dismissal of personnel is nece$sary if it is known that the Alert classification will be closeo out in a short time.

7.1 1 The REC should r-cornrnend .o the ED the need for Early Dismissal of nonessential personnel based on whethrer the event has or may involve a hazardous dismissal or escalate to a higher cleassification.

7.1.2 The ED should direct the TSC Coordinator to assist work group leaders in dismissing nonessential personnei.

7.1.3 The TSC group leaders are to determine which personnel are NOT needed for short term emergency support.

7.1.4 TSC Coordinator reports to ED with the TSC Group Leaders recommendation.

NOTE: Personnel accountability is NOT necessary for Early Dismissal of nonessential personnel.

7.1.5 Once the Early Dismissal personnel have been identified, the TSC Group Leaders should direct the selected work group supervisors to instruct their selected individuals to leave the plant site and go home.

Page 4 of 22

I PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 7.2 Local Evacuation NOTE:" A Plant Evacuation should be conducted if a large NOE employee/worker population is affected.

7.2.1 IF during normal work hours OR an Outage AND the hazard is NOT in the RCA, THEN initiate plant evacuation (Step 7.3).

7.2.2 A Local Evacuation of a specific area of the plant may be necessary because of local hazards. A Local Evacuation may proceed as follows:

A. DETERMINE assembly points using the table below as general quidance. "

uontainment 735' Basketball Court Spent Fuel Pool 4 Aux Bldg Access Control HP Office 4

Operational Old Admin Support Turb Bldg Center (OSC)

New Admin NPD or SBO Initiate Plant Office Trailers Evacuation Security Building Contractor Fab Shop Warehouse #1 (Guardhouse)

Contractor Trailers B. SOUND the EVACUATION ALARM.

C. ANNOUNCE the following over the plant page.

"ATTENTION ALL PLANT PERSONNEL. THERE IS A (hazard)

OCCURING IN

ALL PERSONNEL SHOULD EVACUATE (specify affected area)

THE AND ASSEMBLE AT THE "

(specify affected area) (assembly area)

Page 5 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTR!G PROCEDURES *r NUMBER:

F3 EMERGENCY EVACUATION F3-9 1 REV: 17, D. REPEAT the announcement.

E. DIRECT security (4318) to condupt Personnel Accountability using F3-10 as guidance.

7.2.3 Employees evacuating a particular area should exit via nearest "safe" exit and proceed to (designated area), as announced by PA, to aid in determining accountability.

7.2.4 The Radiation Protection Group (RPG) should:

A. Assume control of entry into the area for exposure control purposes.

B. Complete suiveys in the area and when conditions are returned to normal.

C. Recommend to th-e ED/SM that the area be returned to normal use or relax access control to that area.

7.2.5 Work Group Leaders or Supervisors should complete Accountability for their personnel.

7.2.6 Security or Senior Work Group Leader should contact CAS when Accountability has been completed, 7.2.7 When Accountabi!ity is satisfied, security should inform ED/SM.

7.2.8 When the affected area has been released for normal use, the ED/SM should announce over the P.A., that the affected area is now returned to normal use.

)

Page 6 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES I FN N GIEN IMLBENR U I F3 EMERGENCY EVACUATION REV:

F3-9 17 7.3 Plant Evacuation A Plant Evacuation may occur anytime and SHALL occur whenever a Site Area, or General Emergency is declared unless other constraints or circumstances make it impractical.

"* IF the emergency is already being closed out AND there is no threat to personnel safety, THEN a Plant Evacuation is NOT necessary.

"* IF both onsite Assembly Points are uninhabitable, THEN a Site Evacuation should be initiated.

"I !F there are high winds OR tornado, THEN an evacuation may NOT be feasible or may need to be delayed until it is safe to be outside.

All nonessential plant personnel SHALL evacuate.to a designated onsite assembly area for accountability and monitoring, while emergency response personnel proceed to their respective emergency operating centers.

7.3.1 The Emergency Director should ensure the following is performed during a Plant Evacuation:

During off-normal working hours when few non-shift NOTE: personnel are present, the Shift Manager/Emergency Director may choose the Operations Lounge as an assembly area, if appropriate.

CONSIDER RADIATION SHINE FROM THE CONTAINMENTS CAUTION:I AS WELL AS NATURAL HAZARDS WHEN DETERMINING CATOHABITABILITY REQUIREMENTS OF THE ASSEMBLY AREAS AND EVACUATION ROUTES.

A. Determine the wind direction and possible habitability problems at the onsite assembly areas. Choose either the North Warehouse or the Receiving Warehouse.

"* May use North Warehouse if wind is from:

2360 to 3600 or 00 to 1230

"* May use Receiving Warehouse if wind is from:

1230 to 3600 or 00 to 340 Page 7 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMIPLEME!I.NG PROCEDURES

'I NUMBER:

F3 S:*REV: EMERGENCY EVACUATION F3-9 i 17 B. IF conditions are acceptable, THqN inform the Control Room Operator of the designated Assembly Point and direct the Operator to sound the plant evacuation alarm per Step 7.3.2.

C. Implement F3-1 0, "Personnel Ac(ountability." Personnel evacuation accountability SHALL be completed within 30 minutes after the evacuation alarm is sounded, D. Evacuate the Auxiliary Building Operators to the OSO if:

1. General area radiation levels exceed 100 mR/hr, OR

2. Recommended by tne Rad Protection Group or the REC.

E. Direct security to verify personnelithat normally work outside the plant's Protected Area evacuate to the designated assembly area.

F. IF the completion of the accountability check results in missing persons, THEN direct a search of, the plant buildings in accordance with F3-11, "Search and Rescue" and F3-12, "Emergency Exposure Control."

G. WHEN piant conditions have stabilized, THEN direct reentry into selected areas of the piant in accordance with F3-25, "Reentry."

H. Consider dismissing personnei from the assembly area when:

, Accountability has been compieted.

It has been determined which work groups or individuals may be dismissed from the site.

0 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months staffing plans have been determined.

0 Employee Hot Line has been established and the employee's have been notified of the phone number.

Page 8 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3-9 F3 EMERGENCY EVACUATION SREV: 17 7.3.2 The Control Room Operator should perform the following during a Plant Evacuation:

A. Sound the evacuation alarm.

NOTE., During drills, the message should begin and end with "THIS B. Announce the following over the plant page:

"ATTENTION ALL PLANT PERSONNEL. A PLANT EVACUATION HAS BEEN DECLARED. ALL EMERGENCY ORGANIZATION PERSONNEL REPORT TO AND REMAIN AT YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL SHALL EVACUATE TO THE (specify assembly point)."

C. Repeat announcementt 7.3.3 The REC should perform the following during a Plant Evacuation:

A. Designate an Assembly Point Coordinator to control operations at the designated assembly area.

B. Assist the ED/SM in selecting an Assembly Point.

"* May use North Warehouse if wind if from:

2360 to 3600 or 00 to 1230

"* May use Receiving Warehouse if wind is from:

1230 to 3600 or 00 to 340 C. Monitor the habitability of the Auxiliary Building and recommend to the ED/SM an evacuation of the Auxiliary Building Operators to the OSC if the general area radiation levels exceed 100 mR/hr.

D. Periodically update Assembly Point Coordinator with status of emergency.

Page 9 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTU*G PROCEDURESI PR II D N C E R ISA G N R TN L N M RG N Y P A M L M N I GP O E U E F3 EMERGENCY EVACUATION REV:

F3-9NB:

17 7.3.4 The Assembly Point Coordinator should perform the following during a Plant Evacuation (may initiate at time of Emergency Center staffing):

A. Contact the REC and request the location of the designated Assembly Point.

B. WHEN directed by the REC, THE proceed to the designated onsite assembly area with the appropriate keys (keys are in Security Building) and set up the Assembiy Point as shown in the Assembly Point floor plans, Figure 2 or Figure 3.

C. Supervise any required monitoring or decontamination at the Assembly Point in accordance with F3-14.1, "Onsite Radiological Monitoring," and F3-19, "Perscnnrl and Equipment Monitoring and Decontamination." Give priority to personnel who evacuated directly out of the Radiological Controlled Area.

D. IF contamination is highly likely .A personnel have been dismissed from the Assembly Point, THEN mconitor all vehicles departing the site in accordance with F3-19. Monitoring and/or decontamination should be performed onsits, or at the Training Center, whichever is most practical.

E. Assist in identifying personnel missed during accountability.

F. WHEN directed by ED or REC to dismiss personnel, THEN notify personnel:

"* Who is to return to OSC or TSC.

"* What the Employee Hot Line number is.

7.3.5 OSC Coordinator should:

A. Direct OSC supervisory staff to account for assigned essential personnel NOT evacuating.

B. Comply with EPIP F3-10, Personnel Accountability when the accountability report is delivered by security.

Page 10 of 22

SPRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 SREV:EMERGENCY EVACUATION F3-9 17 7.3.6 Emergency Organization Supervisors should:

A. Verify the physical location and status of their essential personnel NOT evacuating plant.

B. Comply with EPIP F3-1 0, Personnel Accountability when the OSC Coordinator commences the accountability process.

7.3.7 Emergency Organization Support Personnel should contact your emergency organization supervisor and provide your location and physical status.

7.3.8 Personnel evacuating the plant should perform the following during a Rant Evacuation.

A. WHEN the evacuation alarm is heard, THEN evacuate your work area while listening to specific evacuation instructions on the plant's public- address system.

B. IF you cannot hear OR understand the instructions, THEN continue to leave the immediate area until you learn of the evacuation instructions.

C. IF working in a contaminated area, THEN remove as much protective clothing as time permits, especially gloves, booties or rubbers.

D. IF wearing a double suit, THEN removal of outside clothing would only be necessary.

E. IF unable to remove all protective clothing, THEN inform personnel in charge at the assembly area of your condition.

NOTE: During a DRILL, evacuating.

remove ALL protective clothing prior to 1 F. Evacuate via Security Building or as designated by the Security Team.

G. Give your badge to the Security Team member as you exit the Protected Area.

Page 11 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN iMPLEMENTINIG PROCEDURES SEMERGENCY EVACUATION F3-9 J REV: 17 H. WHEN the North Warehouse is thp designated assembly area, THEN all personnel enter the East Door or as directed by the Assembly Point Coordinator.

1. WHEN the Receiving Warehouse is the designated assembly area, THEN all personnel enter the North Door or as directed by the Assembly Point Coordinator.

7.3.9 Security Officers should perform the following during a plant evacuation:

A. Assist in personnel traffic control and perform accountability activities according to F3-10, "Personnel Accountability."

B. Verify personnel have evacuated all of the buildings outside the plant's Protected Area.

7.3.10 The TSC Coordinator should perform the following:

A. Establsh the Employee Hot Line.

B. Coordinate with Group Leaders in establishing 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage.

C. Coordinate when personne! should return to the relieve shift.

Page 12 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES

__F3 F3EMERGENCY EVACUATION NUMBER:

F3-9 REV: 17 7.4 Site Evacuation A Site Evacuation of nonessential personnel should be required when a Plant Evacuation is justified, but the onsite assembly areas are NOT habitable.

Personnel should be directed to evacuate to the parking lot and then using personal NOTE:

cars or plant vehicles, proceed to the offsite assembly area.

Monitoring of personnel and equipment prior to departure from plant I

site is NOT necessary because of possible offsite contamination.

7.4.1 The Emergency Director should perform the following during a Site Evacuation:

A. Designate the Prairie Island Training Center as the offsite assembly area, if possible.

1. In the extreme rare case that the Training Center is NOT usable as an offsite assembly area, reassess, with input from the Radiological Emergency Coordinator, and Site Evacuation plans.

2. A caravan could be led to the Red-Wing Service Center or to either the Goodhue or Dakota County Emergency Worker Monitoring & Decon Centers for monitoring and decon.

NOTE: Appropriate notifications to the county sheriffs' departments should be made.

3. The evacuees could be sent directly to their homes without monitoring, if appropriate.

4. If the general public has been evacuated, evacuees may be sent directly to the state's public reception center for monitoring & decon.

B. Notify the Emergency Manager (EM) of the Site Evacuation and request EOF support. The EOF will be responsible for assisting the I

Assembly Point Coordinator.

C. Inform the Control Room Operator of the offsite assembly point and direct the Operator to sound the evacuation alarm.

D. Implement F3-10, "Personnel Accountability." Personnel accountability should be completed within 30 minutes.

Page 13 of 22

PRAIRIE ISL.AND NUCLEAR GENERATING PLA=NT EMERGENCY PLAN IMPLEIMENTC=!N*G PROCEDURES PRI I N U L A IS.E E A TN L N M R E C L NI P E E%~ G P O E U E NUMBER:

FF3EMERGENCY EVACUATION REV:

F3-9 17 E,. Evacuate the Auxiliary Building Operators to the OSC if:

1. General area radiation levels exceed 100 mR/hr, OR 2, Recommended by the Rad Protection Group or the REC.

F. Ensure that the Security Force has warned all personnel within the Owner Controlled Area, including all trailers, warehouse and construction sites.

G. IF the completion of the accountability check results in missing persons, THEN direct a search of the plant buildings in accordance with F3-1 1, "Search and Rescue" and F3-12, "Emergency Exposure Control."

H. WHEN plant conditions have stabilized, THEN direct a reentry into selected areas of the plant in accdrdance with F3-25, "Reentry."

1. Consider dismissing personnel at the assembly area when accountability has been completed.

"* Key personnel may be requested to return into the plant to augment the TSC or OSC staff,

"* Return of personnel to the plant wili have to be coordinated with Security and Rad Protection Group.

7.4.2 The Control Room Operator should perform the following during a site evacuation:

A. Sound the evacuation alarm.

NOTE: During drils, the message slhould begin and end with "THIS IS A DRILL."

B. Announce the foliowing over the plant page.

"ATTENTION ALL PLANT PERS NNEL. PERSONNEL WITHOUT EMERGENCY ASSIGNMENTS SHALL EVACUATE THE PLANT SITE IMMEDIATELY. GET YOUR CAR KEYS AND EVACUATE TO THE PARKING LOT. USE YOUR CAR OR PLANT VEHICLE AND PROCEED TO THE (specify assembly point). ALL EMERGENCY PERSONNEL SHOULD REMAIN AT YOUR EMERGENCY OPERATING CENTERS" C. Repeat the announcement.

Page 14 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 SREV:EMERGENCY EVACUATION RE:F3-9 17 7.4.3 The Radiological Emergency Coordinator should perform the following during a Site Evacuation:

A. Assist the ED in selecting an offsite assembly area. In most cases the Prairie. Island Training Center should be used.

See the note after 7.4.1 .A for possible alternatives.

B. Direct an Assembly Point Coordinator to report to the offsite assembly area.

C. Monitor the habitability of the Auxiliary Building.

D. IF Auxiliary Building general average dose rates exceed 100 mrem/hr, THEN recommend to ED. and evacuation of the Auxiliary Building Operators to OSC.

E. Consider estabtishing a secondary access control point in accordance with F3-21, "Establishment of a Secondary Access Control Point."

7.4.4 The Assembly Point Coordinator should perform the following during a Site Evacuation:

A. WHEN directed by the REC, THEN proceed to the offsite assembly point (Training Center) and set up the assembly area.

B. Supervise any required monitoring or decontamination at the Assembly Point in accordance with F3-14.1, "Onsite Radiological Monitoring," and F3-19, "Personnel and Equipment Monitoring and Decontamination." Give priority to personnel who evacuated directly out of the Radiological Controlled Area.

C. -IF contamination is highly likely AND personnel have been released, T'HEN monitor all vehicles departing from the site in accordance with I F3-19 or perform monitoring and decontamination at a location further from the Training Center.

Page 15 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 EMERGENCY EVACUATION REV

.REV:

F3-9 17 I 7.4.5 Personnel evacuating the plant site should perform the following during a Site Evacuation:

A. WHEN the evacuation alarm is heard, THEN evacuate your work area while listening to specific evacuation instructions on the plant's public address system.

B. IF you cannot hear or understand the instructions, THEN continue to leave the immediate area until you learn of the evacuation instructions.

C. IF working in a contaminated area; THEN remove as much protective clothing as time permits, especially gloves, booties or rubbers.

D. IF wearing a double suit, THEN removal of outside clothing would only be necessary.

E. IF unable to remove all protective clothing, THEN inform personnel in charge at the assembly area of your condition.

NOTE: W hen an evacuation alarm sounds dunn a DRILL, remove ALL protective clothing prior to evacuating.

I F. Retrieve your personal car keys, if appropriate.

G. Evacuate via Security Building (Guardhouse) or as designated by the Security Force.

H. Give your badge to the Security Force member as you exit the Protected Area.

I. Proceed to your car or to the Assembly Point via other means.

J. IF the Prairie Island Training Centgr is the offsite assembly area, THEN all personnel proceed to the Training Center's parking lot and enter the Southwest Door or as directed by the Assembly Point Coordinator.

K. IF the Training Center cannot be used, THEN assemble in an evacuation caravan on the plant access road and follow the Assembly Point Coordinator to an Qffsite assembly area.

7.4.6 Security Officers should perform the following during a Site Evacuation:

A. Assist in personnel traffic control and perform accountability activities according to F3-10, "Personnel Accountability."

B. Direct all personnel within owner controlled area to proceed to offsite assembly area.

Page 16 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

FR3 EMERGENCY EVACUATION V F39 Figure 1 Site Evacuation Instructions I

i Ill EXAMPLE ONLY USE CURRENT REVISION PINGP 602, Ruv. 4 Page 1 oi 1 SITE EVACUATION INSTRUCTIONS EVACUATION ROUTES To Near-site EOF

1. Exit Piarit Parking Lot

2. Turn left on County 18 INSTRIIC77ONS

3. Proceed to P1 Training Center

4. Use West Entrance 1. Proceed to offsite Assembly Point along designated route.

To Red Wing Service Center

2. Keep windows rolled up; turn heaters

1. Exit Plant via County 18 to Hwy. 61 and air conditioners off.

2. Turn Left on Hwy. 61

3. Proceed to Red Wing 3. Do not smoke, eat or drink.

4. Turn left on Cannon R;ver Roed

5. Turn left on Pepin Street to 4. Do not leave Assembly Point until Red Wing Service Center released.

J:\TEMPLATE\0602 Site Evacuation Instructions.dot Page 17 of 22

PRAIMRE !SLAND NUCLEAR GENERATING PLANT EMýERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 EMERGENCY EVACUATION SREV:

F3-9 17 jv Figure 2 Receiving Warehouse N

Page 18 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 SREV:EMERGENCY EVACUATION F3-9 17 Figure 3 North Warehouse 0

(1) 0 a:

w w

Ill 0

z 0

w w

(r w

Page 19 of 22

PRAIRIE ISLAND NUCLEAR GENERAT!NG PLANT EMERGENCY PLAN IMPLEMEIN7ING PROCEDURES NUMBER:

F3 EMERGENCY EVACUATION REV:

F3-9 17

_J Attachment 1 Discussion The Emergency Director has four (4) options in removing! personnel from an area or the plant determined by the type of emergency condition and/or magnitude of a release. The options are Early Dismissal, Local Evacuation, Plant Evacuation, or Site Evacuation.

1. Early Dismissal This is directing designated groups of nonessential personnel to leave the plant site and return to their homes. This may be initiated during an Alert classification when it is determined that conditions may escalate such that a Plant Evacuation may occur.

When an Alert is declared, the REC should initiate early dismissal assessment and advise the Emergency Director. No Early Dismissal is necessary if it is known that the Alert will be closed out in a short time. If the Alert termination time is unknown or the plant may escalate to a higher classification, then an Early Dismissal should be considered.

Examples of Early Dismissal personnel are:

Visitors Vendors & Consultants Student Interns Selected Admin Staff, Document Control, Information Systems personnel Selected QC Specialists Selected personnel not necessary for immediate emergency support Page 20 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 EMERGENCY EVACUATIONREV:

REV:

F3-9 17~

Attachment 1 Discussion

2. Local Evacuation This is an evacuation of a specific area of a plant building to a safe area within the plant.

This may be done at any emergency level to protect plant personnel from a localized hazard.

If a large employee/worker population is affected (i.e., Turbine Bldg or New Admin Bldg),

a Plant Evacuation should be considered, to facilitate accountability in a timely manner.

During OFF HOURS with the fewer personnel on site it is better to get everyone in one location that would make accountability easier.

"* The OSC is probably the best location. Personnel will show up on the list as being there and they are available to assist.

" The Security Building (Guardhouse) should be the next choice. Personnel will be log off site and will NOT show up on the list. The drawback is they need to get back on site to assist.

Page 21 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 EMERGENCY EVACUATION REV:

F3-93-9 17 Attachment 1 Discussion

3. Plant Evacuation This is an evacuation of plant buildings inside the Prqtected Area to a designated Assembly Point outside the Protected Area (North Worehouse or Receiving Warehouse).

Personnel already outside the Protected Area should be asked to evacuate to the designated Assembly Point.

A Plant Evacuation MAY be initiated at an Alert class fication and SHALL be initiated at the Site Area or General Emergency classification unless there are other constraints or circumstances that make a Plant Evacuation impractical, such as:

C. If the Site Area or General Emergency is already being closed out, then no Plant Evacuation is necessary.

D. If both onsite assembly points are uninhabitable, then a Site Evacuation should be warranted.

E. If there are high winds or tornado, then an evacuation may not be feasible.

Once plant accountability is completed, personnel at the assembly point should be sorted out according to those who go home, go to the OSC, or go to the TSC.

If the event was a contaminating event, personnel and cars should be monitored and decontaminated onsite or at the Training Center, whichever is most practical. If contamination exists beyond the site boundary or at the Training Center, personnel may use the Xcel Red Wing Service Center or the county's Emergency Worker Monitoring and Decon Centers.

4. Site Evacuation This is an evacuation of all plant buildings onsite (inside & outside the Protected Area) to the Training Center. This should be initiated when a Plant Evacuation is justified, but the onsite assembly areas are not habitable.

Once plant accountability is completed, personnel at the Assembly Point should be sorted out according to those who go home, go to the OSC, or go to the TSC.

If the event was a contaminating event, personnel and cars should be monitored and decontaminated, as necessary and practical. If contamination exists beyond the site boundary and at the Training Center, personnel may Use the Red Wing Service Center or the county's Emergency Worker Monitoring and Decon Centers.

If the emergency resulted in evacuation of the general public, plant evacuees may be directed to the public reception center for monitoring and decontamination, as appropriate.

Page 22 of 22

PRAIR!E ISLAND NUCLEAR POWER PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 PERSONNEL ACCOUNTABILITY R73-10 REV: 19 REFERENCE USE

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be available at the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE 4 OZ- x _ _ M.Werner 2-Page 1 of 9

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTNG PROCEDURES NUMBER:

F3 SREV: PERSONNEL ACCOUNTABILITY F3-1 0 19 1.0 PURPOSE This procedure provides instructions for performing personnel accountability during plant evacuations.

2.0 APPLICABILITY This Instruction SHALL apply to all plant personnel.

3.0 PRECAUTIONS If the Security Computer fails and an accountabi!ity list Cannot be generated, individuals remaining in the protected area should be verified by a Oirect contact (either in person or verbally) and their location, name and badge # recorded on the personnel accountability check sheet, Figure 1 (PINGP 601).

4.0 RESPONSIBILITIES I

4.1 The Emergency Director/Shift Manager (ED/SM) is responsible for the completion of personnel accountability and may delegate this authority to the Security Team and emergency center coordinators.

4.2 All emergency center response personnel are responsible to follow the accountability process as directed by their respective emergency center coordinator.

4.3 The Technical Support Center (TSC) Coordinator is responsible to ensure all persons in the TSC have been accounted for.

4.4 All nonessential personnel are responsible to evacuate according to the directions given over the plant's Public Address (PA) system.

4.5 The Security Group is responsible for performing the accountability reports and maintaining access control to the plant.

Page 2 of 9

PRAIRIE ISLAND3 NUCLEAR GENERATING PLANTr EMERGENCY PLAN IMPLEMENTING PROCEDURES 5.0 DISCUSSION 5.1 In the event of a plant evacuation, the personnel accountability check within the Protected Area SHALL be completed within thirty (30) minutes, following the Page Announcement ordering a plant evacuation. Accountability is accomplished with the use of the Security Computer and accountability card readers in the TSC and other sector card readers. All personnel accountability results are forwarded to the ED/SM.

5.2 Accountability is complete when a list is generated showing the location of plant personnel in the protected area.

5.3 When the initial accountability is completed, access to the Protected Area requires coordination between the Emergency Director, Radiation Protection Group, and the Security Manager, or designee, to ensure an ongoing personnel accountability exists throughout the duration of the emergency situation.

5.4 To ensure a continuous personnel accountability, an accountability check should be completed once per shift (every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) or when requested by the Emergency Director.

6.0 PREREQUISITES A Local, Plant, or Site Evacuation has been initiated or a request for personnel accountability within the protected area has been made.

Page 3 of 9

CKLJL PRAIRIE ISLA*ND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMEITTING PROCEDURES NUMBER:

F3 SREV:

PERSONMEL ACCOUNTAOILITY F3-10 19

)

7.0 PROCEDURE 7.1 Local Evacuation 7.1.1 Security Supervision sends a Security Officer to the Assembly Point to assist in Accountability.

7.1.2 AFTER the Security Officer gets to the Assembly Point, THEN CAS Operator runs report-listing personnel in the affected area.

Accountability is complete when the Fa~t Accountability Report is generated.

7.1.3 Inform the ED/SM that accountability is, complete and the results of those names that need verification of location, 7.1.4 Security Officer at the Assembly Point should assist in verifying personnel on the list.

A. Coordinate with CAS and mark the names or badge numbers of security personnel on the list.

During drill and exercises, accovtabii,y of personnel listed in "Listing of on-site DRILL-EXEMPT users" at the end

[ of the Fast Accountability Report is not r quired. If a real NOTE: event should occur during a drill or exer ise, accountability of personnel in "Listing of on-site DRILL4EXEMPT users" at the end of the Fast Accountability Report SHALL be conducted.

B. Inform the ED/SM when the verification process is complete and provide a list of names of those personnel who are still not accounted for.

7.1.5 IF there are any personnel that cannot be located, THEN advise the ED/SM to initiate a search for missing personnel, in accordance with F3..1 1, "Search and Rescue".

7.1.6 WHEN verification of the accountability list is complete, THEN the Security Supeivision should direct the (AS Operator to terminate the emergency evacuation computer program.

Page 4 of 9

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 PERSONNEL ACCOUNTABILITY SREV:

F3-10 19 7.2 Plant or Site Evacuation 7.2.1 Personnel accountability SHALL be initiated immediately after a plant or site evacuation.

7.2.2 During an evacuation, all nonessential personnel should give their badge to the Security Team as they exit the protected area and proceed to the designated assembly area.

7.2.3 As soon as the evacuation alarm soundrs OR at the direction of the Security Manager or designee, the Central Alarm Station (CAS) operator should activate the TSC accountability card readers.

7.2.4 As soon as the. evacuation alarm sounds, all personnel in the TSC should insert that their badges into one of the two TSC card readers (first or second floor TSC).

7.2.5 IF the Security Computer fails, THEN the ED/SM should direct the affected emergency centers to manually complete the personnel accountability check sheet, FigUre:l (PIDNGP 601).

7.2.6 WHEN it has been verified that all badges in the TSC have been inserted into the card readers,. AND badges of personnel evacuating out of the protected area have been inserted into Security Building exit readers, THEN the Security Manager,' or designee, should cause the Fast Accountability Report to be run.

7.2.7 The Security Team action should be as follows:

A. The Security Team should collect all badges from personnel as they NOE leave the protected area via Security Building.

Evacuating personnel nedntso"t°hotlMnitor in Sthe Security Building or at Access Control.

B. The Security Team should insert all badges into the two (2) Security Building exit card readers as soon as possible.

C. As soon as all badges (evacuated personnel and TSC personnel) have been inserted into the card readers, Security Shift Supervision should obtain a list of unaccounted personnel from the security computer.

Page 5 of 9

PRAIRIE ISLAND NtUCLEAR GENERATING PLANT EMEIRGENCY PLAN IMPLEMENTIN4G PROCEDURES I J!"

NUMBER:

F3 PERSONNEL ACCOUNTABILITY REV:

F3-1i0 19 I " The Fast Accountability Report includes'a list of personnel I NOTE. :. who have not inserted their badges into the accountability card readers and their sector location.

D. Tako one (1) Accountability Report to Operational Support Center (OSC) Coordinator or designee in OSC.

E. Take the other copy of the Accourdtability Report to the Technical Support Center (TSC) Security Manager.

F. As soon as the Fast Accountability Report is reviewed by the OSC Coordinator or designee, the Security Team should take this list to the Security Manager, or designee, in the TSC.

7.2.8 Upon receipt of the Fast Accountability Report, the OSC Coordinator or designee should verify the safety status of personnel listed on the Fast Accountability Report as follows:

A. Request OSC supervisory personnel, OSC Emergency Work Status Board Keeper and a representative from the Control Room to assist in the accountability of personnel as names are called.

B. Using the Fast Accountability Report, call or speak the names of personnel listed only in the in-plant areas and out-piant areas. DO NOT call on names in "sector 10" (Control Room Complex) since these personnel are considered safe.

C. WHEN a person has been verified, THEN mark his/her name or badge number on the Fast Accountability Report.

D. WHEN verification of a person cannot be obtained, THEN go to the next name.

E. WHEN this process is complete, THEN return the Fast Accountability Report to the Security Officer for delivery to the TSC.

F. Instruct supervisors to attempt to contact personnel they are responsible for and could NOT verify.

G. Prepare to implement the provision of F3-1 1, "Search & Rescue" upon direction of the ED/SM.

Page 6 of 9

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 PERSONNEL ACCOUNTABILITY VF3-10 REV: 19 7.3 Upon receipt of the Fast Accountability Report, Security Manager or designee should:

7.3.1 Inform the Emergency Director that Accountability is complete and the results of those names that need verification of location.

7.3.2 Coordinate with CAS and mark the names or badge numbers of security personnel accounted for.

During drills and exercises, accountability of personnel listed in "Listing of on-site DRILL-EXEMPT users" at the end of the Fast Accountability Report is not required. If a real NOTE: event should occur during a drill or exercise, accountability of personnel in "Listing of on-site DRILL-EXEMPT users" at the end of the Fast Accountability Report SHALL be conducted.

7.4 IF there are ahy personnel that cannot be located, THEN advise the ED/SM to initiate a search and rescue for missing personnel, in accordance with F3-1 1, "Search and Rescue".

7.5 WHEN verification of the accountability list is complete, THEN the Security Manager should direct the CAS Operator to terminate the emergency evacuation computer program.

7.6 Once each shift, during an emergency (every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) O.R when requested by the ED/SM, a personnel accountability check onsite should be conducted as follows:

7.6.1 The Security Manager or designee should request the CAS Operator to activate the TSC card readers.

7.6.2 All personnel in the TSC should insert their badges into the TSC readers.

7.6.3 WHEN it has been verified that all badges in the TSC have been inserted into the card readers, the Security Manager, or designee, should THEN I cause the Fast Accountability Report to be run.

7.6.4 One (1) copy of the Fast Accountability Report should be taken to OSC and the other copy to the TSC for review.

7.6.5 As soon as the Fast Accountability Report is reviewed by the OSC, the Security Team should take this list to the Security Manager, or designee, in the TSC.

Page 7 of 9

PRAIRIE :SLAND NUCL.EAR GENERATING PLANT EMERGENCY PLAN IMPLEMEI,4JBNG PROCEDURES I-NUMBER:

F3 PERSONNEL ACCOUNTSABiLITY i F REV:

F3-10 19 7.6.6 The Security Manager or designee, shquld then determine from the Fast Accountability Report if the location of any personnel needs to be verified.

7.6o7 IF there are any personnel that cannot Iýe verified, THEN advise the ED/SM to initiate a search for missing personnel, in accordance with F3-1 1, "Search and Rescue".

7.6.8 WHEN verification of accountability list is complete, THEN the Security Manager or designee should direct the CAS Operator to terminate the emergency evacuation computer program.

I Page 8 of 9

PRAIRIE ISLAND NUCLEAR GE*NERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES F31 F PERSONNEL ACCOUNTABILITY REV:

F3-1N0 19 Figure 1 Emergency Operating Center Personnel Accountability Check PINGP 601, Rev. 3 EXAI* JiPLE ONLY Page 1 of 1 Retention: Life USE CUR RENT REVISION Document Type: 7.37J EMERGENCY OPERATING CENTER PERSONNEL ACCOUNTABILITY CHECK LOCATION: Control Room [p7_ Technical Support Center r---I Operational Support Center LI Radiation Protection Group LIII Date: Time:

NAME BADGE # NAME BADGE #

Deliver to security in the TSC.

Completed By:.

Reviewed ByT. Date:

J:\TEMPLATE\0601 Emergency Operating Center Personnel.dot Page 9 of 9

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE o0 1 -?-%,:::, Z S c- M.Werner - ~- -oz Page 1 of 8

A; PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROGEDURES NUMBER:

F SEARCH AND RESCUE F3-11 8 I 1.0 PURPOSE This procedure provides instructions for search and rescue operations in areas of the plant where radiological conditions are known or unknown.

2.0 APPLICABILITY This instruction SHALL apply to all personnel involved in the activation and termination of search and rescue teams.

3.0 PRECAUTIONS 3.1 if there is a reason to believe that the air within the area is toxic or oxygen deficient, the team members SHALL use self-contained b*eathing apparatus which then limits the time available to the team. In this case, in aOdition to the original team, two or more individuals should be assigned outside of the affected area in standby (fuily clothed and wearing SOBA) ready to enter the area if necessary.

3.2 Lifelines should be used in areas containing heavy smoke or in areas where visual contact between team members is impossibie or` hampered. I 3.3 The Search and Rescue Team SHALL have radiation dose rate indicating equipment when radiological conditions are unknown.

3.4 The Radiological Emergency Coordinator (REC) SHALL control all radiation exposure within the guidelines of F3-12, Emergency Exposure Control.

3.5 The Emergency Director SHALL authorize all exposure in excess of 10CFR20 limits per F3-12. If necessary, the Emergency Director may verbally authorize increased exposure when time is a limiting factor and documentation SHALL be completed as a follow-up.

Page 2 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RRSANUMBER: SEARCHNAND RESCUE R 3-11 REV: 8 3.6 Dose Control 3.6.1 Personnel monitoring devices and portable survey equipment will be used to provide information for limiting working times.

3.6.2 For activities NOT involving lifesaving measures, personnel SHALL be limited to no more than 5 REM TEDE.

3.6.3 Where a life is at stake (i.e., removing a casualty from a high level radiation field or treating a highly contaminated casualty), dose should be limited to 25 REM TEDE, 75 REM LDE or 250 REM for organ or extremity. (F3-12) 3.6.4 Dose limits for lifesaving measures may be exceeded on a volunteer basis.

(F3-1!2).

3.6.5 In each instance,-the- risks and benefits derived from a life saving action or protection of large populations SHALL be evaluated for each individual performing the lifesaving action for doses exceeding 25 REM TEDE.

3.6.6 It has been determined that the probability of radiation sickness increases rapidly at doses above 125 REM and that death may occur at dose levels above 200 REM without medical-treatment.'

3.7 All entries into areas of high radiation (>1 OR/hr general area) should be made with two* dose rate indicating meters.

Page 3 of 8

PRAIRIE?,Si-AND NUCLEAR GENERAM;NG PLANT EMERGE-NCY PLAN IMPLEMENTINCg; PFROC3EDURES NUMBER:

SREV:

SEARCH AND9 RESCUE! F3-11 8 -A 4.0 PREREQUISITES 4.1 One or more individuals are missing following arn evacuation and subsequent accountability check.

OR 4.2 A report has been received indicating that personnel are trapped and/or disabled in a potentially hazardous area of the plant.

5.0 PROCEDURE The primary function of the Search and IRescue Teams NOTE: SHALL be to locate the individual(s), administer First Aid, and transport the victim to a ""a*e area for further medical treatment 5.1 The Emergency Director should direct se-u1ity 1o attempt to determine the location of the missing individual(s) by:

5.1.1 Checking the personnel accou*itability at the assembly area, 5.1.2 Paging the individual, 5.1.3 Conferring with the individual's supervisor and co-workers, 5.1.4 Conducting brief searches (if possible), or 5.1.5 Calling individual's home.

5.2 The Emergency Director should review:

5.2.1 Name(s) of individual(s), missing, 5.2.2 Summary of subsequent efforts taken to locate the individual(s),

5.2.3 Last known or most probable location, 5.2.4 Extent of injuries, if any, 5.2.5 Assistance required (onsite or offsite),

5.2.6 Conditions which complicate the search and rescue attempt (e.g., high radiation levels).

Page 4 of 8

PRAIRIE 1SLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE=S NUMBER:

F SEARCH AND RESCUE..

R REV:

F3-11 8

liOT~" i i;*Dose rates for areas of the plant projected from the worst NOTE:case accident assuming major safety system failure and significant core damage are shown in F3-25 "Re-entry."

5.3 The Emergency Director should utilize all pertinent data available including area and process radiation monitoring channels, survey data, visual observations, observations made by previous teams and any other source of information applicable to determine:

5.3.1 Affected plant areas, 5.3.2 Conditions in affected area (e.g., hazards, radiological, temperature, etc.)

5.3.3 Actions which can ,be taken to reduce the potential hazards to the Search and Rescue Team prior.to or during the entry.

1. In the case where radiation exposures may exceed EPA limits, the teams SHALL be composed of volunteers. (F3-12)

2. It is highly recommended that one team member be a Radiation Protection Group member or an individual with extensive training in radiation protection NOTES: practices.

3. The foliowing criteria should be considered when selecting team members:

-Knowledge of first aid

-Knowledge of radiological control practices

-Knowledge of plant construction 5.4 The Emergency Director SHALL order the formation of a Search and Rescue Team composed of a minimum of two individuals. Maximum number will be determined by the volume of work assigned to the Search and Rescue Team.

Page 5 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

REV: 8 5.5 The Radiological Emergency Coordinator should ensure that the Search and Rescue Team is:

5.5.1 Briefed on the estimated or expected radiological conditions in the plant, 5.5.2 Equipped with the required protective clothing, respiratory equipment, dosimetry and communications equipmbnt, 5,5°3 Briefed on exposure control in accordance with the guidelines of F3-12, Emergency Exposure Control 5.5.4 Aware of actions to be taken if unexpected radiological conditions are encountered.

5.6 The team members should remain in visual or voice contact with each other at all times when in the affected areas of the plant.

5.7 The Search and Rescue Team should carry portp.bie communication equipment allowing contact with the Emergency Director, R.ýdiological Emergency Coordinator or designee.

5.8 One member of the Search and Rescue Team should be designated as the Team Leader.

5.9 The Team Leader should ensure that the search and subsequent rescue is completed in the most expeditious manner possible using all available ALARA concepts.

5.10 IF at any time, the survey instrument(s) appear tO maifunction, THEN immediately retreat to a safe area and contact the REC.

5.11 The Search and Rescue Team should continuously observe the portable dose rate meter(s) while approaching the area.

5.12 The Search and Rescue Team should maintain dialogue with REC concerning observed dose rates and conditions observed.

5.13 IF requested, THEN the Search and Rescue Team should read and report dosimeter readings.

Page 6 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F SEARCH AND RESCUE REV:

F3-11 8

5.14 IF at any time during the Search and Rescue mission, observed dose rates exceed a predetermined level, OR IF the exposure of team members approaches a pre-determined amount, THEN the Team Leader SHALL direct the team to a safe area.

5.15 Upon arriving at the area, the Search and Rescue Team Leader should enter the area and assess the situation as conditions permit.

5.16 On the basis of this assessment, the Search and Rescue Team Leader should contact the Emergency Director, determine a course of action, and direct members of the Search and Rescue Team in the completion of the search and/or rescue attempt.

5.17 The Team Leader should request additional support from the Emergency Director when needed.

In the case where the individual(s) cannot be moved NOTE: immediately, First Aid should be applied as necessary, conditions permitting.

5.18 IF the individual(s) are located, THEN they should be moved to the closest safe area and emergency First Aid applied.

5.19 IF the missing or disabled individual is located in a Very High Radiation area, THEN the Team Leader, Radiological Emergency Coordinator, and the Emergency Director SHALL assess the situation pertaining to the following:

5.19.1 Dose Rates in Area 5.19.2 Type of injuries 5.19.3 Estimated Time to Rescue 5.19.4 Projected Exposure to Victim 5.19.5 Projected Exposure to team if rescue is continued 5.20 The Emergency Director SHALL direct the completion or termination of the Search and Rescue mission.

Page 7 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES C I

5.21 IF the individual(s) are in a safe area, THEN the Search and Rescue Team or other qualified EMTs SHALL evaluate the condition of individual(s):

5.21.1 IF the individual is injured and requires further medical treatment, THEN refer to the operations Manual, Section F4, Medical and Casualty Care.

5.21.2 IF the individual has or may have received an overexposure, THEN refer to F3-12.

5.22 The members of the Search and Rescue Team $HALL report to the Radiation Protection Group for determination of exposure they may have received, per F3-12.

Page 8 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE

Proceduresegments may be performed from memory.

Use the procedure to verify segments are complete.

Mark off steps within segment before continuing.

Procedureshould be available at the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE

,4 Z4 -o-< 5c"M. Werner _-2 ,-02 Page 1 of 4

PRAIRIE :SLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES I

1.0 PURPOSE The F3-13 series of procedures and MIDAS User's Manual (RPIPs) satisfy the dose projection commitments made in the Prairie Island NGP Emergency Plan.

2.0 APPLICABILITY This Instruction SHALL apply to Radiological EmergenCy Coordinators, Radiological Protection Support Supervisor, MIDAS Operators, and Shift Chemist.

3.0 REQUIRED EQUIPMENT 3.1 Radiation Monitoring System 3.2 Meteorological Equipment 3.3 Radiation Dose Assessment Computer Syste, (R.DACS) 4.0 PRECAUTIONS I

Use care when reading log scales on the radiation monitors and their calibration curves.

5.0 PREREQUISITES An Alert, Site Area Emergency or General Emergency has been declared and there is actual or potential for a radioactive airborne release.

6.0 PROCEDURE 6.1 IF the Emergency Director has directed offsite dose calculations OR a release to the atmosphere has occurred OR there is an immediate potential for a release to the atmosphere, THEN perform offsite dose calculations in accordance with the MIDAS User's Manual (RPIPs).

I Page 2 of 4

'** PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.2 The conduct of Manual Dose Calculations, F3-13.3, may be performed by the MIDAS Operator in the rare case that neither Radiation Dose Assessment Computer is operating.

6.3 Potential Airborne Release From Containment The REC/RPSS/MIDAS Operator may conduct offsite dose calculations for those cases of a potential release of airborne activity in containment from a LOCA type accident. The MIDAS isotopic release rate run should be used based on the following:

6.3.1 Convert the R48/R49 Containment Radiation Monitor reading (R/Hr) to Containment Activity Concentration ([tCi/cc Xel 33 Equivalent) using the Containment Dose Rate Versus Time Figure in F3-8.

6.3.2 The estimated release rate may be based on releasing 100% of the containment activity in one hour. Estimate the Release Rate (jt Ci/sec Xel 33 Equivalent) by:

Release Containment Rate = Activity X 3.7E10 (cc) X 1 (l.Ci/sec) (p.Ci/cc) 3600 (sec) 6.3.3 Release duration is assumed to be one hour.

6.4 Estimating An Unmonitored Release Rate Based On Field Data The REC/RPSS/MIDAS Operator may perform offsite dose projections based on an unmonitored release by comparing actual measured field survey data with a MIDAS isotopic release rate run as follows:

6.4.1 Perform a MIDAS isotopic release rate run based on actual meteorological data and fictitious release rates of 1E6 [tCi/sec Xe1 33 Equivalent and, 1 E2 0Ci/sec 1131 Equivalent 6.4.2 Compare the actual measured field survey data with the MIDAS dose projection data to establish an estimated actual release rate.

6.4.3 Subsequent offsite dose projections may be performed using MIDAS isotopic release rate run and the estimated actual release rate based on field measurements.

Page 3 of 4

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 oFFSITE DOSE CALCULATION REV:

F3-13 15 6.5 Report results to the Emergency Director or Emr rgency Manager on a periodic basis. Inform the Emergency Director or Emerqgncy Manager immediately of any significant projected offsite dose calculations.

6.6 Continue to calculate the projected offsite dose rIates at approximately 15 to 30 minute intervals, until the emergency situatioris terminated or until such time as determined by the REC/RPSS.

6.7 Ensure that the offsite officials are notified of relevant projected offsite dose calculations on a periodic basis or when requestbd via the transmittal of PINGP 582, "Emergency Notification Followup Message."

i Page 4 of 4

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 MANUAL DOSE CALCULATIONS REV:

F3-13.3 11 REFERENCE USE

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE Ot,%-k o "2.CS M. Werner .-- 2 - Page 1 of 8

El A -LL PRAPIRIE ISLAND NUCLEAR GENERATING PLANT EMIRGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 MANUAL DOSE CALCULATIONS F3-13.3 REV: 11 1.0 PURPOSE This procedure provides instructions to perform manual dose calculations.

2.0 APPLICABILITY This procedure SHALL apply to the Radiological Emergency Coordinators (REC),

Radiation Protection Support Supervisor (RPSS), and MIDAS Operators.

3.0 PRECAUTIONS NONE 4.0 PROCEDURE NOTE: Manual dose calculations may be done using the "Windose" program or using PINGP W-6 and a caliuiator.

4.1 Proceed to Section 4.2 te use the PC olrogram "Windose" or Section 4.3 to use worksheets and a calculator.

4.2 PC Computer Method for Manual Dose Calculations "Windose" is installed on the TSC and EOF MIDAS dose NOTE: projection PCs. There should be a "Windose" icon. A PC diskette should also exist in a 3 ring binder label "Windose".

4.2.1 IF the "Winrdose" icon is to be used, THEN:

A. Run "Windose" by using the "Windose" icon.

B. Continue with Step 4.2.3.

Page 2 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3 F3 MANUAL DOSE CALCULATIONS F3-13.3 REV: 11 4.2.2 IF the '"Windose" diskettes are to be used, THEN:

A. Insert the first diskette into the appropriate disk drive.

B. Choose "RUN" on "START" menu for applicable disk drive.

C. Run the setup program.

D. After "Windose" is installed, execute the program.

E. Continue with Step 4.2.3.

4.2.3 Complete the program's data inputs as necessary.

A. Obtain or determine meteorological information using F3-13.5.

B. Determine the radioactive release path, flows, concentrations or release rates using F3-20, PINGP 783 or PINGP 784.

4.3 Manual Calculator Method for Dose Calculations:.

NOTE:. Use PINGP 946 (Figure 1) to log data and perform calculations.

4.3.1 Obtainldetermine the following meteorological parameters, as per F3-13.5:

A. Wind Speed (ground elevation, mph)

B. Wind Direction (ground elevation, degrees from)

C. Affected Sectors (letter designation)

D. Stability Class (letter designation) 4.3.2 Determine the radioactive effluent release path.

Page 3 of 3

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES

-1 S* .If radioactive effluents are being released from more than one release point, then a total releas* flow rate, F, and an average XE133 eq. concentration willtihave to be calculated:

(1) The total release flow rate, F, (cfni).

F = F1 + F2+

and NOTE:.- (2) Yhe AVERAGE CONCENTRATION XE133 (jiCVcc)

AVE. CONC. XE133 = F1 x XE133(1) + F2,x XE133(2) +

F I F where: F1 = release point 1 flow rate (cim)

F2 = release point 2 flow rate {cft)

XE133(1) = release path 1 concentration (jiCi/cc)

XE133(2) = release path 2 concentratlo, (pCilcc) 4.3.3 Estimate the release flow rate of the radioactive effluent release path, F, in cfm.

Aux Building Special 8,000 cfm per stack Containment Purge 32,250 cfm Containment In-Service Purge 4,000 cfm SFP Special 5,000 cfm per train Shield Building Vent 200 cfm per train (400 cfm/stack)

Steam Dump 6,400 cfm per valve PORV's 3,500 cfm per valve SG Safeties 6,000 cfm per valve SDAFW Pump Turbine Exhaust 150 cfm 4.3.4 Estimate the expected duration of the release, T, in hours (use 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months if release duration is not known).

4.3.5 Determine the release concentration of XE1 33 Equivalent being released from the plant, by either of the following methods:

Page 4 of 8

PRAIRIE ISLAND* NUSLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTrING PROCEDURES IR ISNF EEAINPANTEMEE LNUMBERC F3 MANUAL DOSE CALCULATIONS REV:

F3-13.3 11 A. Obtain the count rate or dose rate from the applicable radiation monitor. Refer to the calibration curves in F3-20 for the applicable radiation monitor to obtain'the release concentration in RCi/cc.

Utilize PINGP 783 for Steam Release or PINGP 784 for Shield Building Stack Release.

B. If the applicable radiation monitor is out of service, determine the release concentration in accordance with F3-20, "Manual Determination of Radioactive Release Concentrations." Utilize PINGP 783 for Steam -Release or. PINGP 784 for Shield Building Stack Release.

4.3.6 Determine the release concentration of 1131 equivalent being released from the plant. .

A. Use the 1131 equivalent activity, pCi/cc, from the sample analysis, if known.

NOE:if more than 1 release point is involved, then calculate an AVG.7 CONC. 1131 as was done for XE1 33.

B. If the 1131 equivalent activity is not known, use the iodine/noble gas ratio of 1E-04 to determine the 1131 equivalent activity being released, as follows:

(XE133) x (1E-04) = (1131) ptCi/cc CONC.

NOTE: Ifmore than 1release point is involved, then use the AVG.

XE133 to determine an AVG. CONC. 1131.

4.3.7 Using the stability class and the downwind distance, determine the value for XU/Q (PINGP 946) for that stability class and downwind distance.

4.3.8 Calculate the TEDE rate as follows:

TEDE Rate (mRem/hr) = (43) (XU/Q) (F) (XE133)

(U)

Page 5 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENT1ING PROCEDURES IF NUMBER:

F3 MANUAL DOSE CALCULATIONS REV:

F3-13.3 11 4.3.9 Calculate the Thyroid CDE rate as fqllows:

Thyroid CDE Rate (mRem/hr) = (2.OE6) (XU/Q) (F._(131.

(u) 4.3.10 Calculate the TEDE and Thyroid CDI by multiplying the applicable dose rates by the expected release cquration, T, in hours:

TEDE (mRem) = TEDE rate (rnRern/hr) x T (hrs)

Thyroid CDE (mRem) = Thyroid CDE rate (mRem/hr) x T (hrs) 5.0 ATTACHMENTS Figure 1 - Dose Calculation Worksheet I

Page 6 of 8

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 1 Dose Calculation Worksheet EXAMPLE ONLY USE CURRENT REVISION PINGP 946, Rev. 4 (Front)

Retention: Ufe Document Type: 7.371 DOSE CALCULATiON WORKSHEET DATE TIME WIND SPEED = U = MPH WIND DIRECTION = DEG SECTO)RS STABILITY CLASS =

RELEASE PATH = FLOW RATE - F = CFM EXPECTED RELEASE DURATION = T = Hrs.

Xe-133 EQ. CONCENTRATION = XE133 = iCi/cc 1-131 EQ. CONCENTRATION = 1131 = pjCi/cc DOWNWIND XU/Q (M- 2 )

DISTANCE As per Stability Class (mi) A B C D E F 0.5 3.1 E-6 1.8E-5 4.7E-5 1.2E-4 2.0E-4 3.3E-4 2.0 5.2E-7 8.3E-7 5.0E-6 1.8E-5 3.6E-5 8.7E-5 5.0 2.4E-7 3.2E-7 1.2E-6 5.0E-6 1.1 E-5 3.0E-5 10.0 1.4E-7 1.8E-7 4.OE-7 2.0E-6 5.2E-6 1.4E-5 (43) (XUIQ) (F) (XE133)

TEDE RATE (mRem/hr) = (U)

(2.026) (XU/Q) (F) (1131)

THYROID CDE RATE(mRem/hr) = (U) 2.0 5.0 10.0 CALCULATED BY:

I Page 7 of 8

- U-uJLiU PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTiNG PROCEDURES NUMBER:

F3 F3-1.

MANUAL DOSE CALCULATIONS 13-13.3 j REV: 11 Figure 1 Dose Calculation Worksheet I EXAMPLE ONLY USE CURRENT REVISION US URN RE ISIN PINGP 946, Rev. 4 (Back)

STABILITY CLASS DETERMINATION DELTA T (-F)/50M STABILITY CLASS WDS1 SIGMA THETA

< -1.71 A > 23

-1.71 to -1.53 B 18- 23

-1.52 to -1.35 C 13 - 18

-1.34 to -0.45 D 8- 13

-044to+1.35 E 4- 8

+1.36 to +3.60 F < 4

> 3.60 G A: Extremely unstable conditions D: Neutral conditions 8: Moderately unstable conditions E: Slightly stable conditions C: Slightly unstabla conditions F: Moderately stable conditions G: Extremely stable conditions NOTE: AT(*F) = (1.8) AT(°C)

WIND DIRECTION

1. If the 10 meter wind speed < 5 mph designates all sectors.

2. If the 10 meter wind speed > 5 mph, use the 10 meter and 60 meter sensors to best describe wind direction and speed for the river N valley and bluffs, respectively.

3. If the 22 meter met tower is used for wind direction, designate all sectors.

Page 8 of 8

' ""- PRAIRIE ISLAND NUCLEA*R GENERATING PLANT EMERGENCY PLAN IMPLEMEN'rING PROCEDURES NUMBER:

MIDAS METEOROLOGICAL DATA F3-13.4 FREV:DISPLAY

~ REF'ERENCEUS

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE

"-4-t? -0 z M.Werner S -'2O2 Page 1 of 5

L11l PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES IL 1.0 PURPOSE This procedure provides instructions for the display of meteorological data from MIDAS or enable the user to turn selected MIDAS DEVICES to the ON status.

2.0 APPLICABILITY This procedure SHALL apply to the Radiation Protection Group, Shift Ernergency Communicators, Shift Supervisors, and Shift Managers.

3.0 PRECAUTIONS Prior to turning any MIDAS DEVICE to the ON status, ensure the problem that turned it OFF has been corrected. If not, MIDAS will turn that data collection device to the OFF status and possibly lose additional data. Data Collection Devices can ONLY be turned to the ON status, by the procedure, and never OFF.

4.0 INITIAL CONDITIONS NONE Page 2 of 5

PRAIRIE ISLA.ND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 5.0 PROCEDURE 5.1 Log onto the MIDAS Metrological Data display by performing the following:

5.1.1 Access a LAN terminal.

5.1.2 Activate the "Midas Meteorological Data F3-13.4" icon found on the

"* "Start" menu

"APPS"

"* "Kea 5.0" menu.

5.2 Once the log-on messages are complete, a standard prompt should appear:

MIDAS-MET -MIDAS TEXT MENU DS = DEVSUM (Device Summary of Met & Rad Data Collection)

MS = METSUM (Summary of Latest 15 minute Met Average)

DM = METDIS (Display of 5 second Met Data - MET EALs)

EX= EXIT Option:

5.2.1 To change the DEVSUM (Device Summary), go to Step 5.5.

5.2.2 To display METSUM (15 minute Met Average), go to Step 5.3.

5.2.3 To display METDIS (5 second Met Data), go to Step 5.4.

5.2.4 To log out, enter "EX."

Page 3 of 5

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENISCY PLAN IMPLEMENTING PROCEDURES I

5.3 To display the Meteorological 15 Minute Summary Table, enter "MS."

5.3.1 A display of the meteorological informalion should now appear.

I i (1) The 10 meter wind direction and spIed is most representative of the meteorological data in the river valley, whereas, the 60 meter wind directior* and speed is slightly more representative of the meteorological data above the river bluffs. For initial dose projection the 10 meter wind speed and direction should be used, if available.

(2) Further analysis of the 10 meter and *60 meter wind direction NOTE: differences should be done by the RgC to determine if any changes in designating downwind sectors is warranted.

(3) The 22 meter met tower does not airways characterize the actual wind direction. If the 22 meter met tower must be used, the REC should consult alternate met data to assess wind direction differences.

(4) Wind direction (degreas) is the direction the wind is coming I

FROM.

5.3.2 Press <ENTER> when completed viewing to return to the selection menu.

5.4 To display the 5 Second Met Data - MET EALs, enter "DM."

5.4.1 A display of the current meteorological information should appear.

5.4.2 The met information will be updated on the screen at five (5) second intervals.

5.4.3 The "EAL Exceeded?" section will indicate if sustained wind speeds (minimum wind speed sustained for at least two (2) minutes) exceed an F3-2 wind speed emergency action level (EAL) of 90 mph or 100 mph.

5.4.4 Enter <CONTROL> "Y" to exit program.

Page 4 of 5

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 5.5 To turn a DEVICE to the ON status:

5.5.1 Enter "DS" for display of Device Status.

5.5.2 Press <ENTER>.

Prior to turning any device to the ON status, ensure the problem NOTE:- that caused data collecti'on to stop has been resolved. If not, MIDAS will return the'device status to OFF and possibly lose additional data.

5.5.3 The following Device Status display should now appear:

DEVICE STATUS ON - PRIMARY METEOROLOGICAL TOWER ON - BACKUP"METEOROLOGICAL TOWER ON - VENT AND FLOW MONITORS What would you like to turn on?

ENTER: [PR] PRIMARY MET TOWER

[BA] BACKUP MET TOWER

[VE] VENT and FLOW MONITORS

[EX] EXIT 5.5.4 If the status of all devices is shown as ON, go to Step 5.5.7 to exit. Ifone or more devices are shown as OFF, continue with 5.5.5.

5.5.5 To turn a device ON, enter the two letter code for that device, either "PR",

"BA", or "VE".

5.5.6 Repeat Step 5.5.5 for each device that is to be turned to the ON status.

5.5.7 When all devices [lave been turned to the ON status, and/or if it is desired to exit the device status program, enter "EX."

Page 5 of 5

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

RADIATION SURVEY TEAMS F3- 16 F3

__________LIQUID

.0,.., ODURING A RADIOACTIVE RELEASE REV:

F3- 17 17 REFERENCE USE

"* Proceduresegments may be performed from memory.

"* Use the procedure to verify segments are complete.

"* Mark off steps within segment before continuing.

"* Procedureshould be availableat the work location.

O.C. REVIEW DATE: OWNER: EFFECTIVE DATE

ýZ4---40* -7.. M.Werner -2 2-Page 1 of 22

- Dial PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES i' I RESPONSIBILITIES OF T-01E NUMBER:

RADIATION SURVEY TEAMS F3 DURING A RADMOACTiVE F3- 16 LIQUID RELEASE REV: 17 1.0 PURPOSE This procedure describes the responsibilities of the Radiation Survey Teams during a

liquid radioactive release to the environment.

2.0 APPLICABILITY This Instruction SHALL apply to all members of the Prairie Island Radiation Protection Group.

3.0 PRECAUTIONS AND SPECIAL CONSIDERATIONS 3.1 Each team SHALL obtain information pertaining to the magnitude of the liquid release, either from the Control Room Operator, the Radiological Emergency Coordinator (REC), or the Radiation Protection Support Supervisor (RPSS).

3.2 Depending on magnitude of the Radioactive Liquid Release, the spray/mist from the cooling towers could be radioactively contaminatpd. Radiation Survey team members should take approphate precautions and monitor themselves for possible J

contamination.

3.3 Report all liquid sample results to the REC or RPSS, in whole numbers, (i.e., with no decimal places) microcunes per milliliter.

3.4 Preface each communication with time title or name of the receiving party and then your title or name. For example: "Prairie Island TSC; Survey Team No. 1 ....

After the communication is cornplete, request the receiving party to repeat the message, if numerical data was relayed.

End message transmission with an appropriate termination phrase. For example:

"Survey Team No. 1, out."

During drills, always include the words, "THIS IS A DRILL," with each transmission.

Page 2 of 22

PRAIRIE ISLAND NUCLEAR GENERATI NG PLANT EMERGENCY PLAN IMPLEMENTiNG-PROCEDURES RESPONSIBILITIES OF THE NUMBER:

F3 RADIATION SURVEY TEAMS DURING A RADIOACTIVE LIQUID RELEASE REV:

F,3- 16 17 3.5 The normal means of transportation for survey teams during any emergency is plant vehicles. Extreme environmental conditions (blocked roads, snow, bridges out,etc.)

may preclude the use of these vehicles. The following alternate transportation is available.

This does not prohibit the use of personal vehicles in cases NOTE: where plant vehicles are not available in sufficient numbers.

3.5.1 Power Boats - Sheriff's Department, plant environmental monitoring

.team,.Red Wing Police..

3.5.2 Four Wheel Drive Vehicle - at Prairie Island 3.5,3 Helicopter - Available during suitable weather conditions from charter services in Minneapolis and St. Paul. Arrangements to be made via the Emergency organization at the EOF.

3,6 The normal means of communication for survey teams is the portable radios. The normal telephone system serves as a backup communication system. Telephone numbers in the TSC for the Radiological Emergency Coordinator (REC) are:

(651) 388-1121 Local Plant (800) 216-1986 Long Distance Plant x4350 REC x4334 F.T. Comi.

(715) 839-0382 REC (Wisconsin)

(612) 330-7690 REC (Twin Cities)

Telephone numbers at the EOF are:

Prairie Island EOF Contact Monticello EOF (651) 388-1121, Ext. 4502 Field Team Comm (763) 295-1504 (651) 388-1165, Ext. 5244 RPSS (763) 295-1503 (651) 388-1121, Ext. 4500 EOF Coordinator (763) 295-1502 (651) 388-1121, Ext. 4505 EOF Count Room (763) 295-1435 (651) 388-1165, Ext. 5236 EOF Count Room (763) 295-1583 3.7 The REC, or RPSS, may determine that samples should be obtained at the Eisenhower Bridge and the Wisconsin channel. The REC, or RPSS, SHALL assign available individuals to obtain these samples.

Page 3 of 22

-A III PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERG 'NCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF T/E NUMBER:

RADIATiON IBTRVEY TEAMS F3-16 DURING A RADIOACTIVE R-: 1 LIQUID RELEASE REV__17

1. If river sampling is hindered due to ice, contact the REC, or RPSS, for further instructions.

NOTE:

2. Traffic control assistance on the Eiso nhower Bridge should be obtained from the Red Wi g Police.

3.8 The estimated main channel average river velocity is 0.75 mph, therefore:

A. time to reach Lock & Dam. No. 3 is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

B. time to reach Eisenhower Bridge is 9 hourS.

3.9 Check meter batteries by switching to BATTERY CHECK position. Replace if necessary.

3.10 Meters checks SHALL be completed prior to use.

3.11 Observe the cold weather operation restrictions (Attachment C).

3.12 All samples SHALL be labeled properly with the required information and saved for further analysis.

4.0 RESPONSIBILITIES 4.1 The REC and the RPSS have the responsibility to determine sample priorities and to direct the Radiation Survey teams sampling.

4.2 The Radiation Survey teams have the responsibility to conduct sampling during a radioactive liquid release in accordance with this procedure.

4.3 The Radiation Team communicator has the responsibility to maintain communications between the Radiation Survey Teams and the REC in the TSC or the RPSS in the EOF.

Page 4 of 22

PRAIRIE *ISLAND NI~r;LEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE'S RESPONSIBILITIES OF-THE NUMBER:

RADIATION SURVEY TEAMS F3- 16 F3 DURING A RADIOACTIVE REV: 17 LIQUID RELEASE REV:_ 17 5.0 DISCUSSION There are three radiation survey teams. Two (2) teams perform offsite surveys and another team provides onsite coverage. Each offsite Survey Team as a minimum requires one (1) Survey Team Member. A second Survey Team Member is desirable. Another person maybe assigned as a driver. All team members report to the Operation Support Center (OSC) for assignment by the Radiological Emergency Coordinator (REC). Other personnel can be used to assist Survey Team Members. The Survey Team Member has the responsibility to ensure proper survey and sampling technique and to perform field calculations.

In the event of an offsite liquid release, the Radiological Emergency Coordinator (REC) may request support for offsite surveys from Monticello. When the Monticello Field Teams arrive at the Prairie Island Near-Site EOF, they will be provided Prairie Island radios if necessary and they will accept the responsibility for offsite surveys and sampling. This allows the Prairie Island personnel to augment the Onsite Radiological Survey Team. All offsite surveys will continue under the direction of the EM at the Prairie Island Near-Site EOF, with the Offsite Survey Teams reporting their activities to the RPSS.

Page 5 of 22

}

PRAIRIE ISLAND NUCLEAR GENERATING PLANT RESPONSIBILITIES OF TýE RADIATION SURVEY TEAMS EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:

F3- 16 I

DURING A RADIOACTIVE LIQUID RELEASE REV: 17 J) 6.0 EQUIPMENT AND PERSONNEL REQUIRED

1. Personnel listed as Team I or Team I may respond as either tearn to ensure staffing of the Field Survey Teams is satisfied expeditiously.

NOTE:

2. Red Protection Supervisors SHALL r~port to the OSC and assume on-site responsibilities s directed by the Radiological Emergency Coordinator (REC).

6.1 Team Members Personnel trained in performing surveys.

6.2 Team Equipment Required 6.2.1 Field Teams 1 & 2 (Offsite Survey Teams)

A. Vehicle (plant or personal),

I B. Offsite sampfe kit (Attachment A) 6.2.2 Onsite Radiological Monitoring Team A. Normal counting room equipment, if available B. E.O.F. counting room equipment C. All available onsite radiation protection equipment 7.0 PREREQUISITES An NUE, Alert, Site Area, or General Emergency has been declared for Prairie Island Nuclear Plant, or anytime Radiation Protection Group deems necessary.

Page 6 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

RADIATION SURVEY TEAMS F3- 16 Fr' -

DURING A RADIOACTIVE REV: 17

__________LIQUID RELEASE REV:_ 17 8.0 PROCEDURE 8.1 All members of Radiation Survey Teams should assemble in the Operational Support Center, unless directed by the Emergency Director or the Radiological Emergency Coordinator (REC):

8.2 Field Teams 1 & 2 (Offsite Survey Teams) 8.2.1 Obtain the necessary information from the the Control Room Operator or TSC personnel regarding the type and amount of release, etc.

8.2.2 Designate two (2) members for Team 1 and two (2) members for Team 2 (if available) to perform, offsite surveys.

Any available plant personnel may be designated as the NOTE: driver for a single team member.

I I 8.2.3 Obtain a plant vehicle-or personal vehicle.

8.2.4 Obtain the necessary equipment (Attachment A), from the NPD Office Building equipment locker or EOF.

8.2.5 Obtain TLD's and dosimeters for each Team member.

NOTE:Survey T departingTeam Members should keep their personal TLD's if from the plant site.

8.2.6 Ensure dosimeter is < 25% of scale and record readings on the dosimeter signout sheet.

8.2.7 IF vehicle with installed radio is NOT available, THEN obtain a portable radio, and magnetic antenna from EOF Receiving Area.

8.2.8 Test the operation of the radios (on channel 13, Rad Team 1) and meter check all meters prior to departing. Refer to Attachment C, if cold weather is a consideration.

Page 7 of 22

III I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMEROENCY PLAN IMPLEMENTING PROCEDURES F3 F RESPONSIBIUTIES OF T$1 E RADIATION SURVEY TEAMS

~~DURING A RADIOACTIVý NUMBER:

F3-16_

LIQUID RELEASE E: 1 REV: 17 8.2.9 Perform offsite surveys as directed by REC or RPSS.

A. Team 1 will proceed to the Lock Dam No. 3 and obtain a one liter sample every 15 minutes from tho downstream side of roller gate area or as directed by the REC or RPSS. Refer to Attachment B for sampling instructions.

B. Team 2 will proceed to the Discharge Canal, at the Cooling Tower Discharge gates and Recycie gates, and obtain one liter samples from the Discharge Canal and Repycle Canal every 15 minutes or as directed by the REC, or RPSS. Liquid samples may be requested near the Discharge Canal outlet to the river at the Cooling Tower Sluice gates. Refer to Attachment B for sampling instructions.

If river sampling is hindered due to ice, Oontact the NOTE: Radiological Emergency Coordinator, or' RPSS, for further instructions.

II NOTNN/A, I On PINGP 647 (Figure 4) columns that do NOT apply may be a down arrow (1) may be used to repeat data.

8.2.10 Document all surfay data on P!NGP 1225, Emergency Sample Label, (Figure 1), and on PINGP 647, Field Team Communicator Emergency Sample Results Log, (Figure 4) or PINGP 598, Emergency Center Narrative Log, (Figure 5).

8.2.11 Report results to the REC or the RPSS, via the portable radio or telephone.

8.2.12 Label bottles correctly for further analysis and storage at the plant site.

8.2.13 One team member SHALL continue the' sampling schedule while the other member transports the samples to the location designated by REC or RPSS for pickup by Sample Courier. Additional bottles may also be obtained at this location.

8.2.14 Continue sampling as directed by the REC or RPSS.

Page 8 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

F-3 RADIATION SURVEY TEAMS DURING A RADIOACTIVE LIQUID RELEASE REV:

F3- 16 17 NOTE:

asnplantl tapersonnelme

- - dieAny availablefo i:!iii~~* b rmay be designated as the 8.3 Onsite Radiological Monitoring Team 8.3.1 Perform all operations requested by the Emergency Director (ED) or REC.

8&3.2 Control radiation exposure onsite (internal and external).

8.3.3 Analyze samples obtained by the onsite and offsite survey teams, using the Count Room facilities and/or the E.O.F. count room facilities.

8.3.4 Store all samples for future analysis.

8.3.5 Perform onsite surveys as requested by the Emergency Director and/or REC per F3-14.1, Onsite Radiological Monitoring.

8.3.6 Perform required personnel monitoring at the emergency operating centers and supervise any necessary personnel decontamination per F3-19, Personnel'and Equipment Monitoring and Decontamination.

8.3.7 One member may be designated as a runner to pickup all samples at the designated locations from Team No. 1 and Team No. 2. Nuclear Plant Service Attendants may be used as sample couriers.

8.3.8 Assist plant operations in minimizing and controlling the release.

8.3.9 All results SHALL be reported to the REC or ED via the available communication system.

Page 9 of 22

PRAIRIE ISLAND NUCLEAR GENERAT:NG PLANT RESPONSIBILPTIES OF EMERGgNCY T E PLAN IMPLEME~rnNCG NUMBER: PROCEOURE RADIATION SURVEY TEA S F3- 16 1)

LIQUID RELEASE REV: 17 8.4 Radiation Field Team Communicator 8.4.1 Report to the Technical Support Center when the emergency is declared, and utilize PINGP 1156, TSC Field Team Communicator Checklist.

8.4.2 Obtain current plant status, release information and meteorological data.

8.4.3 Establish communications with the Survey Teams, using the TSC Console in the REC area.

A. Identify team as PI Team No. 1, etc.

B. Obtain team member names.

C. IF radio communication NOT possible, THEN survey teams will utilize telephone system.

D. Update teams with present plant status, release information, met data, etc.

1. When communicating with the survey teams, preface each communication with the title or name of the NOTE: receiving party.

2. During drills, always include the words, "THIS IS A DRILL", with each transmission.

8.4.4 Dispatch Survey Team No. 1 to Lock ar.d Dam No. 3 and Survey Team No. 2 to the Discharge Canal or as directed by the REC or ED. (See Step 8.2.9.A and Step 8.2.9.B). Refer to PI Survey Team Liquid Sample map for assistance.

8.4.5 Log pertinent information and Survey Team Results on the REC Log, PINGP 598 (Figure 5) or PINGP 647 (Figure 4).

NOTE: If numerical results are communicated, repeat results for verification from survey teams.

8.4.6 Instruct the Survey Teams to return samples to the Plant or EOF Count Room for analysis, or dispatch a sample courier.

Page 10 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMFLEMEN"T'iNG PROCEDURES RESPONSIBILITIES OF THE NUMBER:

RADIATION SURVEY TEAMS F3- 16 F3 .

_________LIQUID DURING A RADIOACTIVE RELEASE REV: 17 8.4.7 Compare offsite monitoring results for consistency. Re-monitor areas of concern, as required.

8.4.8 Update the Field Survey Teams periodically with:

A. Emergency Classification B. Plant status C. Release information D. Meteorological data 8.4.9 IF radiation exposure to personnel exists, THEN direct the Survey Teams periodically to read their dosimeters, and log results.

8.4.10 Instruct the Prairie Island Survey Teams to report to the OSC for onsite assignments, when the RPSS and the Monticello Survey Teams assume responsibility for offsite surveys.

Page 11 of 22

El - JUL PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBiLiTIES OF THE F3 .0RADIATION SURVEY TEAMS NUMBER:

F3- 16 1)

DURING A RADIOACTIV LIQUID RELEASE REV: 17 Attachment A Offsite Survey Team Equipment Package 1.0 Each offsite survey team should be equipped with a kit of the following:

0 Dose rate instrument RO-2 or equivalent

Count rate instrument RM-14 or equivalent 0 2" GM pancake probe

Battery powered air sampler 0 Personnel self-reading dosimeters (Low Range)

Personnel self-reading dosimeters (High Range) 0 TLD's (if individuals have a normally assigned TLD, they should wear those assigned)

Plastic Sample Bags

Garbage bags

Paper towels

Masking tape

Silver zeolite adsorbers

GMR-l canisters

Full Face respirators

Gas Sample Chambers 0 Filter assembly (gas sampler) 0 Suction bulb (gas sampler) 0 Filter paper (gas sampler)

One liter poly bottles

Four inch air sampler filter papers Page 12 of 22

PRAIRIE ISLAND NUJCLEA&R GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

RADIATION SURVEY TEAMS F3- 16 DURING A RADIOACTIVE

___....____ LIQUID RELEASE REV: 17 Attachment A Offsite Survey Team Equipment Package

"* Survey sample labels

"* IF NOT using vehicles with a radio installed, THEN pick up spare radio in EOF or get radio from Monti.

"* Portable Radio Antenna Adapter (Connects antenna directly to hand held portable radio in event of radio booster unit failure)

"* Flashlight

"* D-Cell batteries

"* Potassium Iodine tablets (Thyroid Blocking Agent)

"* Orange Safety Vests

"* Tweezers

"* Anti-C Clothing

"* Life Jackets

"* Compass

"* Clipboard

"* Pens

"* Pad of paper (8-1/2" X 11" minimum size)

"* Road map of State of Minnesota

"* Road map of State of Wisconsin

"* Umbrella

"* Watch or clock

"* Calculator

"* Foul weather (rain) gear Page 13 of 22

PHAIHIE FIL.AND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTIN

G. PROCEDURE

S i RESPO"NSIBILITIES OF T"IE NUMBER:

F3 RADFAT.ON SURVEY TEAMS DURING A RADMOACTIVE F3- 16 4 LIQUID RELEASE REV. 17 Attachment A Offsite Survey Team Equipment Package

"* Line (100 feet)

"* Weighted poly bottle holder

"* Snow Scoop

"* Surgeon gioves 2.0 The Procedures Binder contains:

"* Ground Deposition Sample Results Log Fornms

"* Plume Search Survey Log Forms

"* Copy of F3-15, "Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release"

" Copy of F3--16, "Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release"

"* Copy of F3-22, "Prairie Island Radiation Protection Group Response to a Monticello Emergency"

"* Narrative Log 3.0 Prairie Island and Monticello Emergency Piar, Map Sets 4.0 Aluminum Form clipboard/holder:

Field Team Air Sampie Results Forms Page 14 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

F3 RADIATION SURVEY, TEAMS*

DURING A RADIOACTIVE.

LIQUID RELEASER F3- 16 Attachment B Liquid Sampling 1.0 Precautions 1.1. Always collect full one liter bottles.

1.2. For samples at the outfall or point of discharge, assume that the bottle, weighted sampler and rope could possibly be slightly contaminated.

Surgeons gloves should be worn at this sample point and bottles be placed in a plastic bag.

1.3. Observe cold weather operation instructions (Attachment C).

1.4. Estimation of gross liquid activity SHALL be made with probe in position shown on applicable activity curve table.

1.5. All meter readings SHALL be corrected count rates (subtract background).

2.0 Procedure 2.1. Obtain a one liter poly sample bottle of liquid from the desired sample location.

noPlace poly bottle in sample rig in such a position that it will INOTE: not float out.

2.2. Throw the weighted sampler into an area of water which will supply a representative sample.

2.3. Collect a FULL one liter sample of liquid.

2.4. Withdraw the weighted sampler and cap the sample bottle.

NOTE: I Observe precautions as sampler may be contaminated.

2.5. Label bottle properly.

2.6. Place labeled bottle in plastic bag.

Page 15 of 22

Jill

'U PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING, PROCEDURES RESPONSIBILITIES OF T14E NUMBER:

RADIATFON SURVEY TEAMS F3- 16 F3 DURING A RADIOACTIVE i LIQUID RELEASE REV: 17 Attachment B Liquid Sampling 2.7. Estimate the gross liquid activity by the following methods:

2.7.1 Using RM-14 or equivalent with 2"( M Pancake Probe position the probe at midpoint on the one liter sample bottle as shown on Figure 2 or Figure 3.

2.7.2 Using the corrected count rate obtqined on the instrument, estimate gross activity in liCi/mi Figure 2 or Figure 3.

2.8. Record results on PINGP 1225, (Figure 1), and on PINGP 647, (Figure 4) or PINGP 598, (Figure 5).

2.9. Report the results to the REC or the RPS$.

2.10. Save all samples for further analysis.

Page 16 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES I RESPONSIBILITIES OF THE NUMBER:

RADIATION SURVEY TEAMS F3- 16 DURING A RADIOACTIVE LIQUID RELEASE REV: 17 Attachment C Cold Weather Operation

1. IF outside temperature is greater than 32 0 F (00C), THEN instrument use is unlimited.

2. IF outside temperature is between 32 0 F (00)) AND 0°F (-18°C), THEN no instrument should be used for more than 5 minutes.

3. IF outside temperature is between 0°F (-180.C) AND -20°F (-280C), THEN no instrument should be used for more than 2 minutes.

4. IF the outside temperature is below -20°F (-280C), THEN no instrument should be used unless special batteries (alkaline or Ni-CD) are in instrument and this would increase the temperature range to -40°F(-400 C). The instrument should only be used for very short times (less than 30 seconds).

5. The instrument should completely warm up between periods of cold weather use.

Instrument warm-up may be indoors or in a heated vehicle and should take 2 - 5 minutes.

Page 17 of 22

11 111 I

I I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT RESPONSIBILITIES OF TI -IE EMERC ENCY PLAN IMPLEMENTING PROCEDURES I

NUMBER:

F3 RADIATION SURVEY TEA MS DURING A RADIOACTIV E LIQUID RELEASE REV:

F3- 16 17 J

Figure 1 PINGP 1225 Emergency Sample Label EM PINGP 1225, Rev. 0

'1 L EXAMPLE ONLY USE CURRENT REVISION Page 1 of 1 Retention: N/A EMERGENCY SAMPLE LA*BEL I NOTE: I Consider all samples as possibly, ontaminated.

SAMPLE LOCATION: SAMPLE ID #:

SAMPLE DATE: SAMPLE TIME:

SAMPLE CONTACT READING: _CP_ o___emhr (CPM or moem/hr)

LIQUID SAMPLE: ( ) - ( __ ) = ( ) CPM)

GROSS CPM BKGD CPM CORRECTED COUNTRATE LIQUID SAMPLE ACTIVITY (Figure 2 or 3, F3-16) = uCi/ml MISC. SAMPLE TYPES: SNOW DIRT FOOD OTHER:

COMMENTS:

I FIELD TEAM RPS: COUNTROOM: (circle) PLANT EOF Page 18 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

RADIATION SURVEY TEAMS, F3- 16 DURING A RADIOACTIVE REV: 17

[__________LIQUID RELEASE REV:_ 17 Figure 2 Gross Liquid Activity Curve Using Rm-14 Or Equivalent With HP-210 Probe 10 ----------

-I- - - -- - - - - ....

..... *-aa..... J.-a

, .-------- Saa.

,. . ,.a;a... .' ' .. ... .. . * . . . .. . . . .. . . , . , .., ,. ,.

. . . . . *.. a... S *a ' a 10 * '

a .- . "

.. ° * - a * -* ------ a a a a1*

LA-------- --------------------------------- A--

at a )*

, .-. . ,- , - ,- , a a , , , .

S,---------- . ..

C<

. . ._ a. . : . _. ' . .. . . r.. . . . . - . ., - . . . .. ;

... . :. " .. . ., of 22...

a a . . . . *' a ' a L

.a a..a--- .. 1 a aa ------------- a a, a a,- a: a j, ala-----

a

- a,

*:a... .: ! / / a.

a-. .. , .aa.

,I'a - .

L *:. ... ...- ,-,;* ,':[*:/2 --::;":.---;-;--;-. -.- .. .. ..---. -' 1 ;

.... ,!f a:*:::::: a .i... -::.:: .a......

L .aDi 0'31 0" . ...

10 10a

. * . : a.ri:*.

.. . . . . . .,- --- ' ', r o- . .. .. ."/..a." .a , , , , a. ,- ' ,

" a a ' :: 4a,*- - . ,

, , , ,a

.a ...,a.a. .. . . a.. a- a a a

. T------- ..--- ..-- .- .,.,;., . .... ... a a..;..a : ,a a 1

-"a a10aa 10 " -a aLLaDaa1a0 ACTaVITa- aCa/a aPage 1a ofa22

J1L-A - 11 I

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGr-NCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF TI IE NUMBER:

F3 RADIATION SURVEY TEA1AS DURING A RADIOACTIVI LIQUID RELEASE REV:

F3- 16 17 I

Figure 3 Gross Liquid Activity Table Using RM-14 or Equivalent With HP-210 Probe

\ ._

Detector Position CCPM 4 uCi/m!

CCPM I uCi/ml 10 1 E-04, 30006- 3.E-03 120 ,2.E-04 S2.E-04 3500 3.E-03 140 __2.E-04 4000 3. E-03 160 1 2.E-04 4500 4.E-03 180 2.E-04_ 5000 4. E-03 200 3.E-04 6000 -5.E-03 220 3.E-04 7000 5.E-03 240 3.E-04 8000 6.E-03 260 3.E-04 9000 7.E-03 280 f 3.E-04 10000 7. E-03 300 4.E-04 350 4.E-04 400 5.E-04 450 "5.E-04 . . . . .. . . . ._ . __..

500 6.E-04 Page 20 of 22

PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE NUMBER:

F RADIATION SURVEY TEAMS F3- 16 F3iDURING A RADIOACTIVE LIQUID RELEASE REV: 17 Figure 4 PINGP 647, Field Team Communicator Emergency Sample Results Log PINGP 647, Rev. 12 Page 1 of 1 Document Type: 7.37D Retention: Life of Plant FIELD TEAM COMMUNICATOR I EXAMPLE ONLY USE CURRENT REVISION I

EMERGENCY SAMPLE RESULTS LOG DATE:

DOSE RATE RESULTS SAMPLE RESULTS !*1/2 mREM/hr 1 TEAM SURVEY SAMPLE SAMPLE GROSS GAMMA BETA NUMBER POINT TIME TYPE*. , Ci/cc CPM

Sample type includes: Particulate, Gaseous. Iodine, Liquid, Area Dose Rate COMMUNICATOR SIGNATURE Authenticated & Accepted Date Page 21 of 22

11I PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES RESPONSIBILITIES OF THE F3 RADIATION SURVEY TEAKS DURING A RADIOACTIV =

NUMBER:

F3- 16 LIQUID RELEASE REV: 17 Figure 5 PINGP 598, Emergency Center Narrative Log PINGP 598, Rev. 2 Retention:,

Page 1 of 1Lifetime I EXAMPLE ONLY CURRENT REVISION SECRRN USE EMERGENCY CENTER NARRATIVE LOG PAGZ:

LOCATION: DAT__:

DESCRIPTION I

I I I

I I

,I I I ,

I I I I I T.M Completed by:

Page 22 of 22

ML021440429

Contents

Text

Title:

G. PROCEDURE

G. PROCEDURE

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