Text

Rev 35 to HP-90, Emergency Equipment.
	ML17309A996
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1999
From:	Harris K, West R; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17309A992	List: ML17309A991; ML17309A994; ML17309A995; ML17309A996;
References
	HP-90, NUDOCS 9907300161
	Download: ML17309A996 (507)
	v • d • e

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Procedure No.

ST. LUCIE PLANT HP-90 y)

HEALTH PHYSICS Current Rev. No.

PL

'5 PROCEDURE SAFETY RELATED Effective Date:

07/06/99

Title:

EMERGENCY EQUIPMENT Responsible Depa ent: HEALTH PHYSICS Revision Summary Revision 35 - Revised r erences to delete C-111 and a ded COP-06.11. Revised text and checklists to delete C- 11 and added COP-06.11.y6pdated EP Supervisor information.

Made administrative change . (Rick Walker, 06/30/99)

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aoceouaE wooucrloN Revision FRG eview Date Approved By Approval D te S OPS DATE 06/24/75 K. N. Harris 09/1 1/75 DOCT PROCEDURE Plant General Manager DOCN HP-90 Ys Revision FRG Review Date Approved By Approval Date C 'P COMPLETED 35 06/30/99 R. G. West 06/30/99 IT 35 Plant General Manager 73001.b1. 99072b 05000335 PDR gDOCK PDR)

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Page 2 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

1.0 TITLE

EMERGENCY EQUIPMENT 2.0 REVIEW AND APPROVAL:

See cover sheet.

3.0 PURPOSE

This procedure gives the instructions to be used when conducting inventories and maintenance of HP Emergency Kits.

4.0 PRECAUTIONS AND LIMITATIONS:

4.1 Item substitution is authorized only if the substituted item is comparable/equivalent to the original equipment.

4.2 All emergency equipment shall be checked and inventoried once each month and within five (5) working days following each use.

4.3 Items found in Emergency Kits which do not appear on the inventory sheets shall be removed and relocated in accordance with the instructions of a Health Physics Supervisor. This does not apply at hospitals, where FPL and non-FPL supplies may be collocated in accordance with hospital staff preferences.

4 (

Page 3 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQ UIPMENT 4.0 PRECAUTIONS AND LIMITS: (continued) 4.4 In years ending in zero (0) or five (5), all inventoried equipment should be evaluated with respect to age, wear and need for replacement or upgrade.

4.5 Kit check sources used to test instrument operability should NOT be stored near the kit TLDs.

4.6 Silver impregnated zeolite cartridges may be properly stored for a period of five years from the date of manufacture.

4.7 Electronic Personnel Dosimeters (EPD) stored in the Control Rooms and offsite monitoring team kits shall be programmed to:

1. Display both Dose and Dose Rate.

2. Activate by pushing the pushbutton.

3. Alarm on a dose of 4.5R and a Dose Rate of 10R/hr.

4.8 When notified by Emergency Planning that a revision to a procedure contained

'in the HP Emergency Kits has been issued, HP should update the procedure with the new revision within five (5) working days.

4.9 Full face respirators in the Emergency Kits shall be visually inspected in accordance with the requirements of HPP-62, Inspection and Maintenance of Respiratory Protection Equipment.

5.0 RELATED SYSTEM STATUS:

NONE

Page 4 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan) 6.2 E-Plan Implementing Procedures (EPIP 00-13) 6.3 St. Lucie Plant Emergency Response Directory (ERD) 6.4 Florida Power 8 Light Company, St. Lucie Plant Recovery Plan 6.5 HPP-62, "Inspection and Maintenance of Respiratory Protection Equipment."

6.6 HPP-70, "Personnel Contamination Monitoring and Decontamination Procedure."

6.7 HPP-101, "Identification and Reporting of Radiological Events."

6.8 Health Physics Procedures, HP-200 Series 6.9 COP-06.06, "Guidelines for Collecting Post Accident Samples."

6.10 COP-06.11, "Establishing Remote Laboratory for Analyses of Accident Samples." /R35 6.11 OP 1-0010125, "Schedule of Periodic Tests, Checks and Calibrations."

6.12 OP 2-0010125, "Schedule of Periodic Tests, Checks and Calibrations."

6.13 ADM-17.01, "Duties and Responsibilities of the Shift Technical Advisor."

6.14 NRC Generic Letter 91-14, Emergency Telecommunications.

6.15 NRC Administrative Letter 94-04, Change of the NRC Operations Center Commercial Telephone and Facsimile Numbers.

6.16 OSHA 1926.404(b)(iii), Assured Equipment Grounding Conductor Program.

0 Page 5 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

6.0 REFERENCES

6.17 PMAI number PM 97-04-006, EPIP Updates in HP EKits 6.18 PMAI number PM 97-04-147, Shaving Supplies in HP EKits

$3 6. 1 9 PMAI number PM 97-07-1 42, First-aid Kit in Site Assembly Station 7.0 RECORDS REQUIRED:

7.1 Inventory sheets for each of the locations listed in 8.2 below (HP-90)-

Attachments 01-7 shall be maintained in the plant files in accordance with Ql-17-PSL-1 "Quality Assurance Records." /R35

Page 6 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT 8.0 INSTRUCTIONS'.1 Prior to conducting inventories of the kits:

1 ~ Ascertain the current revision number of Emergency Planning documents.

A. Contact the Nuclear Records Vault for 1, 2 and 3 below.

B. Access the Controlled Electronic Procedure Index (in Lotus Notes) for all other documents (4-10 below).

NOTE Kits designating that full sets of EPIPs and/or HP-200 series procedures are available, shall contain all the procedures in Table 1 and/or Table 2, as applicable.

1 ~ St. Lucie Plant Radiological Emergency Plan (EPlan)

2. St. Lucie Plant Emergency Response Directory (ERD)

3. Florida Power 8 Light Company, St. Lucie Plant Recovery Plan

4. EPIPs (see Table 1)

5. HP-200 Series (see Table 2)

6. HPP-70, "Personnel Contamination Monitoring," (Form HPP-70.1, Personnel Skin and Clothing Contamination Report)

7. HP-90, "Emergency Equipment"

8. HPP-101, "Identification and Reporting of Radiological Events,"

(Form HPP-1 01.1, Radiological Event Report)

Page 7 of 55 l 8.0 INSTRUCTIONS; (continued) 8.1 (continued)

ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

1. (continued)

B. (continued)

9. COP-06.06, "Guidelines for Collecting Post Accident Samples"

10. COP-06.11, "Establishing Remote Laboratory for Analyses of Accident Samples." /R35 The procedure distribution is listed on the inventory sheet.

2. Contact Emergency Planning to determine if any procedure revisions are available to be added to the emergency kits.

3. Contact Land Utilization to arrange for access to the Emergency Operations Facility (EOF), if necessary (i.e., not on the access list).

8.2 Inventory all items, verifying that the proper supplies are present. Use the appropriate inventory list.

1. Attachment 1 - Unit 1 Control Room/Technical Support Center Emergency Kit

2. Attachment 2 - Unit 2 Control Room Emergency Kit

3. Attachment 3 - Operational Support Center Emergency Kit

4. Attachment 4 - Site Assembly Station Emergency Kit

5. Attachment 5 - Site Assembly Station - Field Monitoring Team Emergency Kit (complete 1 attachment for each kit)

6. Attachment 6- Emergency Operations Facility Emergency Kit

7. Attachment 7 - Hospital Emergency Kit (complete one attachment for each hospital)

Page 8 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

8.0 INSTRUCTIONS

(continued) 8.3 Any equipment which is out of calibration, fails the operability check, or appears to be unusable shall be replaced.

1. An asterisk designates a major piece of equipment. If a major piece of equipment is found to be deficient, the equipment must be replaced as follows:

A. For Emergency Kits located within the Owner Controlled Area - the same day B. For Emergency Kits located outside the Owner Controlled Area-within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

8.4 Quantities of non-asterisked inventory items may be exceeded, but shall not be less than that indicated on the attachment. An item found to be in a quantity less than that listed on the attachment shall be replenished by the time of the next inventory.

8.5 Perform operability checks of instruments in accordance with Appendix A, Operability Instructions.

8.6 Verify that dosimetry is current.

NOTE Not all dosimetry is required in each Emergency Kit.

1. Direct Reading Dosimeter (DRD). DRDs are calibrated every six (6) months.

A. 0-500 mR B. 0-5 R C. 0-20 R D. 0-100 R

Page 9 of 55 C ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

8.0 INSTRUCTIONS

(continued) 8.6 (continued)

2. Electronic Personal Dosimeter (EPD)

A. Alarm Setpoint, Dose: 4.5 R B. Alarm Setpoint, Dose Rate: 10 R/hr

3. Thermoluminescent Dosimeter (TLD). TLDs are changed out in the kits on a semi-annual basis.

A. Whole Body B. Extremity C. Finger Rings 8.7 Verify that respirators are visually inspected as prescribed in HPP-62, Inspection and Maintenance of Respiratory Protection Equipment.

8.8 Verify that silver zeolite cartridges are current. Inform the Health Physics Technical Supervisor when the posted shelf life of the cartridges is within three (3) months of expiring.

8.9 Extension cords stored in the Emergency Kits shall be tested or replaced with tested extension cords after use.

1. A testing device is available in each kit which has extension cords.

2. Record test results or cord replacement in the "Remarks" section (e.g., all extension cords passed; one extension cord replacement due to test failure).

Page 10 of 55 l 8.0 INSTRUCTIONS: (continued)

ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT NOTE The portable count rate instruments (friskers) and the dual channel analyzers are exempt from this instruction because they require re-chargeable batteries.

Spare instruments are available as backups should one of these instruments (friskers) experience battery failure.

I 8.10 Verify that there is a sufficient supply of spare batteries available for all instruments and equipment requiring batteries.

1. Replace any battery or package of batteries which is approaching (within one (1) month) or exceeds its expiration date or shelf life.

2. Every January and July, inspect batteries in all instruments and equipment for signs of deterioration or leaks and replace, as necessary.

8.11 Verify that the procedures contained in the kit are the current revisions, if not, replace procedure with a controlled copy of the current revision.

8.12 Perform monthly test of communications equipment with state and local governments and the NRC in accordance with Appendix B, Instructions for Testing Emergency Communications Equipment.

8.13 Complete the inventory form as follows:

1. Indicate the results of the operability checks of the kit instruments by marking "Pass" or "Fail" on the appropriate atta'chment. Record any discrepancy in the "Remarks" section.

2. Dosimetry, dress-out supplies, and other equipment should be evaluated against the "Minimum Quantity" requirements as listed on the inventory form. Record the "As Found" condition as either "Pass" or "Fail". Indicate any discrepancy in the "Remarks" section.

3. Review all documents, procedures, and logs and show whether they are "Available" or, "Unavailable". Record any discrepancy in the "Remarks" section.

Page 11 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT

8.0 INSTRUCTIONS

(continued) 8.13 (continued)

4. Indicate the results of the communications tests by marking "Pass" or "Fail" on the appropriate attachment. Record any discrepancy in the "Remarks" section.

5. Upon completion of the inventory, close and lock the kit and sign and date the attachment in the blanks labeled "Inventoried by" and "Date".

8.14 A copy of each completed inventory (attachment) is required.

1. Conspicuously post the copy of the inventory on the front of the Emergency Kit for ready reference by the next user of the kit.

2. Provide the original to an HP Supervisor for review.

8.15 An HP Supervisor shall review all completed inventories.

1. A PMAI is to be issued by the reviewing HP Supervisor for each item which is not addressed in 8.3 or 8A above and can not be resolved within five (5) working days of identification.

The PMAI number is to be recorded in the "Remarks" section of the affected attachment.

2. Sign and date the reviewed inventories in the "Reviewed by" and "Date" blanks on each attachment.

3. A copy of each reviewed attachment is to be forwarded to Emergency Planning.

4. The originals of all reviewed attachments are to be sent to the Nuclear Records Vault.

Page 12 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT TABLE 1 EMERGENCY PLAN IMPLEMENTING PROCEDURES EPIP "Discovery & Identification of an Emergency Condition (Including Chemical, Fire and Natural Emergencies)"

EPIP "Classification of Emergencies" EPIP "Duties and Responsibilities of the Emergency Coordinator" EPIP "Emergency Response Organization Notification/Staff Augmentation" EPIP "Activation and Operation of the Technical Support Center" EPIP "Activation and Operation of the Operational Support Center" EPIP "Activation and Operation of the Emergency Operations Facility" EPIP "Conduct of Evacuations/Assembly" EPIP "Off-site Dose Calculations" EPIP "Off-site Radiological Monitoring" EPIP "Core Damage Assessment" EPIP "Maintaining Emergency Preparedness - Radiological Emergency Plan Training" EPIP "Maintaining Emergency Preparedness - Emergency Exercises, Drills, Tests and Evaluations"

Page 13 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT TABLE 2 HP-200 SERIES PROCEDURES HP-200 - "Health Physics Emergency Organization" HP-201 - "Emergency Personnel Exposure Control" HP-202 - "Environmental Monitoring During Emergencies" HP-203 - "Personnel Access Control During Emergencies" HP-204 - "In-Plant Radiation and Contamination Surveys During Emergencies" HP-205 .- "Emergency In-Plant Air Sampling" HP-206 - "Analysis of Emergency In-Plant Air Samples" HP-207 - "Monitoring Evacuated Personnel During Emergencies" HP-208 - "Personnel Decontamination During Emergencies"

r Page 14 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT1 UNIT 'I CONTROL ROOMITECHNICAL SUPPORT CENTER EMERGENCY KIT (Sheet 1 of 4)

NOTE Inspect all batteries during January and July inventories.

INSTRUMENTS Pass Fail

1. Portable Dose Rate Instrument (> 5R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

3. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

4. Dual Channel Analyzer Model No.: ~ Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A DOSIMETRY Minimum As-Quantity Found

1. TLD, Whole Body Semi-annual: 53

2. TLD, Finger Ring Semi-annual: 16

3. TLD, Multibadge Semi-annual: 50

4. DRD, 0-500 mR Calib. Due Date: 50

5. DRD, 0-5R Calib. Due Date: 10

6. DRD, 0-100R Calib. Due Date:

7. Electronic Dosimeter Calib. Due Date: 10 Major Equipment

- Codes: P=Pass, F=Fail, R=See Remarks

- - Alarm Setpoint: Dose -

4.5R; Dose Rate 10R/hr.

Page 15 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT1 UNIT 1 CONTROL ROOM/TECHNICAL SUPPORT CENTER EMERGENCY KIT (Sheet 2 of 4)

NOTE Inspect all batteries during January and July inventories.

DRESS-OUT SUPPLIES Minimum As*"

Quantity Found

1. Coveralls 20

2. Cloth Hood 20

3. Cotton Liners (pr.) 20

4. Rubber Gloves (pr.) 20

5. Surgical Gloves (pr.) 20

6. Rubber Shoe Covers (pr.) 20

7. Plastic Booties (pr.) 20

8. T-Cuts (pr.) 20

9. Whirl-Pack 50

10. Tape (2" roll)

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

~ 1 Page 16 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT1 UNIT 1 CONTROL ROOM/TECHNICAL SUPPORT CENTER EMERGENCY KIT (Sheet 3 of 4)

NOTE Inspect all batteries during January and July inventories.

Minimum As

OTHER EQUIPMENT Quantity Found

1. SCBA

2. Air Sampler Model No.: Serial No.: Calib. Due Date:

3. Silver Zeolite Cartridges Exp. Date:

4. Particulate Filters

5. Whirl-Packs (labeled Air Sample Data)

6. Full-Face Respirator (perform visual inspection, update card)

7. Charcoal Canister Exp. Date: 16

8. Dosimeter Charger

9. Contamination Smears and Envelopes/Folders 500

10. Radiation Barrier Tape/Rope/Ribbon N/A

11. Radiation Sign and Assorted Inserts

12. Step-off Pads 10

13. Poly Bags (yellow) 10

14. Extension Cord (HD)

15. Extension Cord Adapter - Yellow

16. Extension Cord Adapter - Red

17. Plastic Rainsuits 20

18. Batteries - complete set of replacement batteries, both type and N/A number, available for all equipment requiring batteries; check shelf life.

19. Telephone Headset Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

'a Page 17 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT1 UNIT 1 CONTROL ROOM/TECHNICAL SUPPORT CENTER EMERGENCY KIT (Sheet 4 of 4)

NOTE Inspect all batteries during January and July inventories.

DOCUMENTS, PROCEDURES, LOGS Avail. Un avail.

1 ~ PSL Emergency Plan (check for current revision)

2. EPIPs (full set) (check for current revisions)

3. Emergency Response Directory (check for current revision)

4. HP-90 (check for current revision)

5. HP-200 Series (full set) (check for current revisions)

6. Form HP 206.1 (10 copies) (check for current revision)

7. COP-06,06 (check for current revision)

8. COP-06.11, "Establishing Remote Laboratory for Analyses of Accident Samples" (check for current revision) /R35

9. Radiation Exposure Summary Report

10. Control Room Rad Survey Maps (10 copies)

11. Laminated Floor Plan Maps with Index for Rad Survey (full set)

12. Field Monitoring Maps Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: Date:

Page 18 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT2 UNIT 2 CONTROL ROOM EMERGENCY KIT (Sheet 1 of 4)

NOTE Inspect all batteries during January and July inventories.

INSTRUMENTS Pass Fail

1. Portable Dose Rate Instrument (a5 R/hr)

Model No.:, Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

3. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

4. Dual Channel Analyzer Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A DOSIMETRY Minimum As**

Quantity Found

1. TLD, Whole Body Semi-annual: 10

2. TLD, Finger Ring Semi-annual: 12

3. TLD, Multibadge Semi-annual: 50

4. DRD, 0-500 mR Caiib. Due Date: 10

5. DRD, 0-5R Calib. Due Date: 10

6. DRD, 0-100R Calib. Due Date:

7. Electronic Dosimeter Calib. Due Date: 10 Major Equipment

- Codes: P=Pass, F=Fail, R=See Remarks

- - Alarm Setpoints: Dose - 4.5R; Dose Rate 10R/hr.

Page 19 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT2 UNIT 2 CONTROL ROOM EMERGENCY KIT (Sheet 2 of 4)

NOTE Inspect all batteries during January and July inventories.

DRESS-OUT SUPPLIES Minimum As**

Quantity Found

1. Coveralls 10

2. Cloth Hood 10

3. Cotton Liners (pr.) '10

4. Rubber Gloves (pr.) 10

5. Surgical Gloves (pr.) 10

6. Rubber Shoe Covers (pr.) 10

7. Plastic Booties (pr.) 10

8. T-Cuts (pr.) 10

9. Whirl-Pack 50

10. Tape (2" roll)

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

g ~

4i

Page 20 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT2 UNIT 2 CONTROL ROOM EMERGENCY KIT (Sheet 3 of 4)

NOTE Inspect all batteries during January and July inventories.

Minimum As-OTHER EQUIPMENT Quantity Found

1. SCBA

2. Air Sampler Model No.: Serial No.: Calib. Due Date:

3. Silver Zeolite Cartridges Exp. Date:

4. Particulate Filters

5. Whirl-Packs (labeled Air Sample Data) 6 Full-Face Respirator (perform visual inspection, update card) 7 Charcoal Canister Exp. Date: 16 8 Dosimeter Charger 9 Contamination Smears and Envelopes/Folders 500

10. Radiation Barrier Tape/Rope/Ribbon N/A

11. Radiation Sign and Assorted Inserts

12. Step-off Pads 10

13. Poly Bags (yellow) 10

14. Extension Cord (HD) N/A

15. Extension Cord Adapter - Yellow

16. Extension Cord Adapter - Red

17. Plastic Rainsuits 10

18. Batteries - complete set of replacement batteries, both type and N/A number, available for all equipment requiring batteries; check shelf life Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 21 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT2 UNIT 2 CONTROL ROOM EMERGENCY KIT (Sheet 4 of 4)

NOTE Inspect all batteries during January and July inventories.

DOCUMENTS, PROCEDURES, LOGS Avail. Un avail ~

1 ~ PSL Emergency Plan (check for current revision)

2. EPIPs (full set) (check for current revisions)

3. Emergency Response Directory (check for current revision)

4. HP-200 Series (full set) (check for current revisions)

5. Form HP 206.1 (10 copies) (check for current revision)

6. Radiation Exposure Summary Report

7. Control Room Rad Survey Maps (10 copies)

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: Date:

~ ~

Page 22 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT, ATTACHMENT3 OPERATIONAL SUPPORT CENTER EMERGENCY KIT (Sheet 1 of 4)

NOTE, Inspect all batteries during January and July inventories.

INSTRUMENTS Pass Fail

1. Portable Dose Rate Instrument (M R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Portable Dose Rate Instrument (a5 R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

3. Portable Dose Rate Instrument (a5 R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

4. Portable Count Rate (Fdsker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

5. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

6. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

7. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

8. Dual Channel Analyzer Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

9. Sealer and Detector Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 23 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT3 OPERATIONAL SUPPORT CENTER EMERGENCY KIT (Sheet 2 of 4)

NOTE

, Inspect all batteries during January and July inventories.

DOSIMETRY Minimum As

Quantity Found

1. TLD, Whole Body Semi-annual:

2. TLD, Finger Ring Semi-annual: 22

3. TLD, Multibadge Semi-annual: 50

4. DRD, 0-500 mR Calib. Due Date: 40

5. DRD, 0-5R Calib. Due Date: 20

6. DRD, 0-100R Calib. Due Date: 10 DRESS-OUT SUPPLIES

. Coveralls 50

2. Cloth Hood 50

3. Cotton Liners (pr.) 50

4. Rubber Gloves (pr.) 50

5. Surgical Gloves (pr.) 50

6. Rubber Shoe Covers (pr.) 50

7. Piastic Booties (pr.) 50

8. T-Cuts (pr.) i, 50

9. Whirl-Pack 100

10. Tape (2" roll) 10 Shaving Cream (can)

12. Disposable Razors OTHER EQUIPMENT

1. SCBA

2. Air Sampler Model No.: Serial No.: Calib. Due Date

3. Silver Zeolite Cartridges Exp. Date: 20

4. Particulate Filters 20

5. Whirl-Packs (labeled Air Sample Data) 20

6. Full-Face Respirator (perform visual inspection, update card) 12

7. Charcoal Canister Exp. Date: 24

8. Dosimeter Charger (electric)

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 24 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT3 OPERATIONAL SUPPORT CENTER EMERGENCY KIT (Sheet 3 of 4)

NOTE Inspect all batteries during January and July inventories.

OTHER EQUIPMENT (continued) Minimum As""

Quantity Found

9. Dosimeter Charger (battery)

10. Contamination Smears and Envelopes/Folders 1500

11. Radiation Barrier Tape/Rope/Ribbon N/A

12. Radiation Sign and Assorted Inserts 20

13. Step-off Pads 20

14. Poly Bags (yellow) 50

15. Portable Fluorescent Lights

16. Flashlights 24

17. Rope (manila) N/A

18. Insect Repellent (spray can) 10

19. Decontamination Agent

20. Bull Hom

21. Plastic Rainsuits 50

22. Clipboards (regular)

23. Lined Tablets 10

24. Note Pads 10

25. Felt-Tip Pens (black) 24

26. Ink Pens (black) 24

27. Pencils 24

28. Scissors

29. Calculator

30. Stapler with staples

31. Bolt Cutters

32. Batteries - Complete set of replacement batteries, both type and N/A number, available for all equipment requiring batteries; check shelf life.

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 25 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT3 OPERATIONAL SUPPORT CENTER EMERGENCY KIT (Sheet 4 of 4)

NOTE Inspect all batteries during January and July inventories.

DOCUMENTS, PROCEDURES, LOGS Avail. Unavail.

EPIPs (full set) (check for current revision)

2. Emergency Response Directory (81 A-D, H - 5 copies) (check for current revision)

3. HPP-70 (check for current revision)

4. HP-90 (check for current revision)

5. HP-200 (full set) (check for current revision)

6. COP-06.06 (check for current revision)

7. COP-06.11, "Establishing Remote Laboratory for Analyses of /R35 Accident Samples" (check for current revision)

8. Radiation Exposure Summary Report

9. HP Blank Survey Forms (Unit 1 and Unit 2)

10. Field Monitoring Map

11. Assembly Area Kit Emergency Response Directory (81J - 1 copy) (check for current revision)

HP-207 (check for current revision)

HP-208 (check for current revision)

12. Decon Log Notebook including:

Form HP207.1 (25 copies) (check for current revision)

Form HPP-70.1 (25 copies) (check for current revision)

COMMUNICATIONSTEST Pass Fail

1. Videolink Check Perform check in accordance with Appendix B Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: Date:

4 Page 26 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT4 SITE ASSEMBLY STATION EMERGENCY KIT (Sheet 1 of 3)

NOTE Inspect all batteries during January and July inventories.

INSTRUMENTS Pass . Fail

1. Portable Count Rate (Frisker) Instrument (Decon)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Portable Count Rate (Frisker) Instrument (Field Team)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

3. Portable Count Rate (Frisker) Instrument (Field Team)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

4. Portable Count Rate (Frisker) Instrument (Field Team)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

5. Portable Count Rate (Frisker) Instrument (Field Team)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 27 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT4 SITE ASSEMBLY STATION EMERGENCY KIT (Sheet 2 of 3)

NOTE Inspect all batteries during January and July inventories.

DRESS-OUT SUPPLIES Minimum As**

Quantity Found

1. Coveralls 10

2. Cloth Hood 10

3. Cotton Liners (pr.) 10

4. Rubber Gloves (pr.) 10

5. Surgical Gloves (pr.) 10

6. Rubber Shoe Covers (pr.) 10

7. Plastic Booties (pr.) 10

8. T-Cuts (pr.) 10

9. Whirl-Pack 50

10. Tape (2" roll)

OTHER EQUIPMENT 1, Paper PCs 10

2. Radiation Barrier (Tape/Rope/Ribbon) N/A

3. Radiation Sign and Assorted Inserts

4. Step-off Pads 10

5. Poly Bags (yellow) 50

6. 5 Gallon Jug of Water

7. Waterless Hand Cleaner (can)

8. Hand Rags 50

9. Towels

10. Shaving Cream (can) 11 ~ Disposable Razors

, Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Cl

Page 28 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT4 SITE ASSEMBLY STATION EMERGENCY KIT (Sheet 3 of 3)

NOTE Inspect all batteries during January and July inventories.

DOCUMENTS, PROCEDURES, LOGS Avail. Un avail.

1 ~ Emergency Response Directory (check for current revision)

2. HP-200 Series (full set) (check for current revision)

3. Notebook

4. Decon Log Clipboard with:

Form HP 207.1 (25 copies) (check for current revision

5. Decon Log Clipboard with:

Form HPP-70.1 (25 copies) (check for current revision)

6. First Aid Kit COMMUNICATIONSTEST Pass Fail

1. Wall Phone Perform communications test in accordance with Appendix B Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: Date:

4 Page 29 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT5 SITE ASSEMBLY STATION-FIELD MONITORING TEAM EMERGENCY KIT

'(Sheet 1 of 2)

NOTE Inspect all batteries during January and July inventories.

INSTRUMENTS Pass Fail

1. Portable Dose Rate Instrument (2 5R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Dual Channel Analyzer Model No.: Serial No.: Caiib. Due Date:

Perform operability check in accordance with Appendix A DOSIMETRY Minimum As" Quantity Found

1. TLD, Whole Body Semi-annual:

2. EPD '** Calib. Due Date:

3. DRD, 0-5 R Calib. Due Date:

OTHER EQUIPMENT

1. Air Sampler (auto battery-powered)

Model No.: Serial No.: Calib. Due Date:

2. Silver Zeolite Cartridges Exp. Date:

3. Particulate Filters

4. Whirl-Packs (labeled "Air Sample Data" )

5. Surgical Gloves (pr.)

6. Portable Radio

7. Power Cord with Cigarette-Lighter Plug

8. DC Power Receptacle with Battery Clips

9. Microphone with Cable

10. Magnetic-Mount Antenna

11. Full Face Respirator (perform visual inspection, update card)

12. Charcoal Canister Exp. Date:

Major Equipment

- Codes: P=Pass, F=Fail, R=See Remarks

- - Alarm setpoints: Dose - 4.5R, Dose Rate 10R/hr.

Page 30 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT5 SITE ASSEMBLY STAT(ON-FIELD MONITORING TEAM EMERGENCY KIT (Sheet 2 of 2)

NOTE Inspect all batteries during January and July inventories.

OTHER EQUIPMENT (continued) Minimum As'*

Quantity Found

13. Stopwatch

14. Calculator

15. Dosimeter Charger

16. Tweezers

17. Flashlight

18. Batteries - Complete set of replacement batteries, both type and N/A number, available for all equipment requiring batteries; check shelf life.

DOCUMENTS, PROCEDURES, LOGS Avail. Un avail.

1. Emergency Response Directory (check for current revision) 2 HP-202 (check for current revision) 3 (Form) Table 1 of HP-202 (2 copies) (check for current revision) 4 Form HP-202.1 (6 copies) (check for current revision) 5 Field Monitoring Log

6. Field Monitoring Maps Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: 'ate:

Page 31 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT6 EMERGENCY OPERATIONS FACILITY EMERGENCY KIT (Sheet 1 of 3)

NOTE Inspect all batteries during January and July inventories.

INSTRUMENTS Pass Fail

1. Portable Dose Rate Instrument (2 5R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Caiib. Due Date:

Perform operability check in accordance with Appendix A

3. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A DOSIMETRY Minimum As**

Quantity Found

1. TLD, Whole Body Semi-annual:

2. DRD, 0-500 mR Calib. Due Date: 10

3. DRD, 0-5 R Calib. Due Date:

DRESS-OUT SUPPLIES

1. Coveralls 20

2. Cloth Hood 20

3. Cotton Liners (pr.) 20

4. Rubber Gloves (pr.) 20

5. Surgical Gloves (pr.) 20

6. Rubber Shoe Covers (pr.) 20

7. Plastic Booties (pr.) 20

8. T-Cuts (pr.) 20

9. Whirl-Pack 50

10. Tape (2" roll)

'ajor Equipment Codes: P=Pass, F=Fail, R=See Remarks

~ l e

Page 32 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT6 EMERGENCY OPERATIONS FACILITYEMERGENCY KIT (Sheet 2 of 3)

NOTE Inspect all batteries during January and July inventories.

OTHER EQUIPMENT Minimum As""

Quantity Found

1. Full Face Respirator (perform visual inspection, update card)

2. Charcoal Canister Exp. Date: 12

3. Dosimeter Charger (electric)

4. Dosimeter Charger (battery)

5. Silver Zeolite Cartridges Exp. Date: 50

6. Contamination Smears and Envelopes/Folders 500

7. Radiation Barrier (Tape/Rope/Ribbon) N/A

8. Radiation Sign and Assorted.inserts 10

9. Step-off Pads 10

10. Poly Bags (yellow) 10

11. 'lastic Rainsuits 20

12. Batteries - Complete set of replacement batteries, both type and N/A number, available for all equipment requiring batteries; check shelf life.

DOCUMENTS, PROCEDURES, LOGS Avail. Un avail.

1. PSL Emergency Plan (check for current revision)

2. EPIPs (full set) (check for current revision)

3. Emergency Response Directory (check for current revision)

4. Florida Power & Light Company St. Lucie Plant Recovery Plan

5. HP-90 (check for current revision)

6. HP-200 Series (full set) (check for current revision)

7. COP-06.06 (check for current revision)

8. COP-06.11, 'Establishing Remote Laboratory for Analyses of Accident Samples" (check for current revision) /R35 COMMUNICATIONSTEST Pass Fail

1. NRC Emergency Notification System (ENS)

Perform communications test in accordance with Appendix B

2. NRC Health Physics Network (HPN)

Perform communications test in accordance with Appendix,B

3. NRC Reactor Safety Counterpart Link (RSCL)

Perform communications test in accordance with Appendix B.

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 33 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT6 EMERGENCY OPERATIONS FACILITYEMERGENCY KIT (Sheet 3 of 3)

NOTE Inspect all batteries during January and July inventories.

COMMUNICATIONSTEST - EMERGENCY OPERATIONS Pass Fail FACILITY (EOF) (continued)

4. NRC Protective Measures Counterpart Link (PMCL)

Perform communications test in accordance with Appendix B.

5. NRC Management Counterpart Link (MCL)

Perform communications test in accordance with Appendix B.

6. NRC Local Area Network (LAN)

Perform communications test in accordance with Appendix B

7. Local Government Radio (LGR) Channel 2 (39.18 MHz)

Perform communications test in accordance with Appendix B; 0 Unit1, 0 Unit2, 0 TSC(AII3okto pass)

8. Local Government Radio (LGR) Channel 1 (39.10 MHz)

Perform communications test in accordance with Appendix B; 0 Unit 1, 0 Unit 2, 0 TSC (All 3 ok to pass)

9. Spectra Radio, HP Offsite Channel Perform communications test in accordance with Appendix B

10. State Warning Point (SWP) Hot Ring Down Phone (HRD)

Perform communications test in accordance with Appendix B

11. Videolink check Perform check in accordance with Appendix B Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: Date:

Page 34 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT7 HOSPITAL EMERGENCY KIT (Sheet 1 of 2)

NOTE Inspect all batteries during January and July inventories.

INSTRUMENTS Pass Fail

1. Portable Dose Rate Instrument (t 5R/hr)

Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

2. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A

3. Portable Count Rate (Frisker) Instrument Model No.: Serial No.: Calib. Due Date:

Perform operability check in accordance with Appendix A'OSIMETRY Minimum As**

Quantity Found

1. TLD, Whole Body Semi-annual: 12

2. DRD, 0-20 R Calib. Due Date:

3. DRD, 0-500 mR Calib. Due Date: 12 OTHER EQUIPMENT

1. Dosimeter Charger

2. Contamination Smears and Envelopes/Folders 500

3. Radiation Barrier Tape/Rope/Ribbon N/A

4. Radiation Sign and Assorted Inserts

5. Step-off Pads 10

6. Poly Bags (yellow) 20

7. Herculite (may be precut) N/A

8. Decontamination Table and Accessories

9. Tape (2'oll)

10. Radioactive Material Tags 25 Major Equipment Codes: P=Pass, F=Fail, R=See Remarks

Page 35 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT ATTACHMENT7 HOSPITAL EMERGENCY KIT (Sheet 2 of 2)

NOTE Inspect all batteries during January and July inventories.

OTHER EQUIPMENT (continued) Minimum As**

Quantity Found

11. 'Lined Tablets

12. Note Pads

13. Ink Pens (black) 12

14. Batteries - Complete set of replacement batteries, both N/A type and number, available for all equipment requiring batteries; check shelf life.

DOCUMENTS, PROCEDURES, LOGS Avail. Un avail.

1. Emergency Response Directory (check for current revision)

2. HPP-70 (check for current revision)

3. HPP-101 (check for current revision)

4. HP-207 (check for current revision)

5. HP-208 (check for current revision)

6. Form HPP-101.1 (5 copies) (check for current revision)

7. Form HPP-70.1 (5 copies) (check for current revision)

Major Equipment Codes: P=Pass, F=Fail, R=See Remarks Remarks:

Inventoried by: Reviewed by:

Date: Date:

0

~ ~

Page 36 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIXA OPERABILITY INSTRUCTIONS (Sheet 1 of 5)

1. Portable Dose Rate Instrument - Check calibration sticker, battery test and response to supplied check source.

NOTE Kit check sources should not be stored near the kit TLDs.

2. Portable Count Rate Instrument - Check calibration sticker, battery test (unplug line cord) and response to supplied check source.

3. Battery and Operational Checks of the Ludlum Model 2218.

NOTE

~ Should it be necessary to use Channel 2, items contained within parentheses are settings to be used for Channel 2.

~ A layout of the Ludlum Model 2218 is provided in Figure 1 to this Appendix.

Verify that the RECYCLE knob is OFF. The knob is labeled and located on the rear panel of the instrument.

3.1 Check the battery as follows:

NOTE If an instrument fails the battery check, it can be used only if it is connected to AC power and therefore should be replaced with an instrument capable of passing this operability check.

1. Tum the POWER knob to "BAT".

2. Unplug the AC line cord.

3. Depress the BAT testbutton.

Page 37 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX A OPERABILITY INSTRUCTIONS (Sheet 2 of 5)

3. (continued) 3.1 (continued)

4. Observe the condition below the RATE SCALE.

5. If battery condition is not within the acceptable BAT TEST range, plug in the AC line cord and turn the POWER knob to CHARGE. Attach a label to the instrument stating "Instrument is charging, started charge at AM/PM on 19

6. If the battery condition is acceptable, then continue with the steps below.

3.2 Set the STABILIZER toggle switch to OFF, NOTE Steps 3.3 through 3.15.4 are initially performed on Channel 1.

3.3 Ch1 (Ch2), set the ADD-OFF-SUBTRACT knob to ADD.

3.4 Ch2 (Ch1), set the ADD-OFF-SUBTRACT knob to OFF 3.5 Ch1 and Ch2, set the ON-BYPASS toggle switch to BYPASS.

3.6 Ch1 (Ch2), set the WINDOW and the THRESHOLD dials IAW (in accordance with) settings on the side of the 2218 cabinet.

3.7 Set the unused Channel's WINDOW and THRESHOLD dials to 10.0.

3.8 Ch1 (Ch2), set the IN-OUT toggle switch to IN.

3.9 Ch2 (Ch1), set the IN-OUT toggle switch to OUT.

3.10 Set the MINUTES knob to X1.

3.11 Set the LIVE-CLOCK toggle switch to LIVE.

I ~

~ ~

Page 38 of 55 J~~

ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX A OPERABILITY INSTRUCTIONS (Sheet 3 of 5)

3. (continued) 3.12 Set the F-S (Fast-Slow) toggle switch to S.

3.13 Set the Ch1-Ch2-Sealer knob to SCALER.

3.14 Set the MINUTES thumbwheel to 01.

3.15 Perform a source check as follows:

1. Place the Ba-133 check source in the shield under the detector.

2. Depress the COUNT-RESET button to start counting.

3. When counting stops, compare the displayed counts with the acceptance range that is located on the side of the instrument.

4. If the displayed counts are within the acceptance range then go to step 3.17. If the displayed counts are not within the acceptance range then go to step 3.16.

3.16 High voltage (HV) adjustments are performed as follows:

1. Set the MINUTES knob to EXT.

2. Place the Ba-133 check source in the shield under the detector.

3. Depress the COUNT-RESET button to start counting.

4. Observe the COUNTS/MINUTE (Count Rate Meter) scale while making small adjustments in voltage to obtain the maximum count rate achievable.

5. Increase or decrease the voltage with the HV (High Voltage) dial ~

6. Set the MINUTES knob to X1 ~

7. Depress the COUNT-RESET button to start counting.

Page 39 of 55

~ ~ ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX A OPERABILITY INSTRUCTIONS (Sheet 4 of 5)

3. (continued) 3.16 (continued)

8. When counting stops, compare the displayed counts with the acceptance range that is located on the side of the instrument.

9. If the displayed counts are within the acceptance range then go to step 3.17. If the displayed counts are not within the acceptance range then repeat steps 3.3 through 3.15.4 using channel 2.

3.17 If the instrument successfully completed the operational response check, record the results on the appropriate Attachment.

3.18 If the instrument did not successfully complete the operational check, using channel 2:

1. Tag the instrument OUT OF SERVICE, give the reason.

2. Record the results in the appropriate Attachment.

3. Give the reason for failure in the Remarks section.

3.19 If the instrument successfully completed the operational response check using channel 2, record the results on the appropriate Attachment and label the instrument "use channel 2".

3.20 Tum the power knob to CHARGE.

4. Sealer and Detector - check the calibration sticker and response to supplied check source. This is a response check only; use the supplied kit check source used for dose rate instruments.

LUOLUQ swEETwATER TEKAs 200 300 X1K 8

~~

rEE Oo X100 QA X10 Goo -I COUNTS/MINUTE X1 COUNT RANGE Q x0 Oc CO O

QD Q, QQOHE Co 00 0 mm

" III m K Zl I

QJ X m ICEl

+ Co

+>

1 Qo Qo $ $

0 C

)I SUBTRACT MINUTES CO 33 9 Z.+

QF IOIICON TNIIEEIIOIO MULTIPUER XG001 I g fT1 ZZC Og0 Q~

2" 22 N-U cN 0m Qo (oO Qo;:: +X c:ag c~

MODEL2218 O mm UNE DUALNALYZER Ooo 0 ZZ H0 HV TEST BAT STAEIUZER 2Co CHARGE ENT. EAT 8 xU FIGURE 1 - LUDLUM2218 fNP40.8$ 6J CO C)

L'1't't'er "'0'hE* ~HU Ad'ustment Count Verification Zl M-setto BAT L-setto EXT L-setto XI -.0-toggle to

OFF L -set to'X1 m N- depress testbutton to C - depress button to start C - depress button to I - Ch1 to ADD; Ch2 to OFF K- toggle to LIVE" count start count H- toggle to BYPASS" for Ch1 Co check battery condition -:.

D - toggle to S A - Indicates battery cordition P - adjust voltage B - compare counts with and Ch2 E - set to SCALER 02 on'BAT TEST scale A - observe maximum acceptance range for :: G- Ch1 set WINDOW ard THRESHOLD J -set to "01 Cto count rate the instr Nnent in accordance with settings on side C - depress button to start Ul of instrigient; Ch2 set WINDOW and count THRESHOLD to 10.0 i F -toggleto IN for Ch1and OUT for Ch2

Page 41 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 1 of 15)

I. Control Rooms NOTE The NRC Emergency Notification System (ENS) phones are tested in conjunction with the Technical Support Center.

A. Unit 1 Control Room emergency communications equipment is tested in accordance with plant Operating Procedure 1-0010125, "Schedule of Periodic Tests, Checks and Calibrations."

B. Unit 2 Control Room emergency communications equipment is tested in accordance with plant Operating Procedure 2-0010125, "Schedule of Periodic Tests, Checks and Calibrations."

II ~ Technical Support Center (TSC)

A. Technical Support Center emergency communications equipment is tested in accordance with Plant Administrative Procedure ADM-17.01, "Duties and Responsibilities of the Shift Technical Advisor."

III ~ Operational Support Center (OSC)

A. "Videolink" - the "Videolink" is a closed circuit audio/visual communications link originating in the TSC with feeds to the OSC and the Emergency Operations Facility.

1. Instructions for Testing

a. Contact someone to go to the TSC to assist with the test of the "Videolink", if not previously arranged.

b, Tum on the television sets in both Rooms 2200 and 2300.

c. Set the channel selector to channel 9 and adjust volume.

4

~ ~

Page 42 of 55'T.

LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 2 of 15)

III. (continued)

A. (continued) 1 ~ (continued)

d. Request the person in the TSC to provide a test broadcast.

e. Operability is verified if both the video picture and audio output are received on the television sets in both rooms. The picture must be clear and the audio free from static.

f. Record operability status on the inventory form (Attachment 3).

g. If the "Videolink" is inoperable (one or both television sets), notify Emergency Planning.

h. Following completion of the tests, turn off the television sets in rooms 2200 and 2300.

IV. Emergency Operations Facility (EOF)

Testing the NRC Emergency Telecommunications System (FTS 2000) ~

A. Emergency Notification System (ENS)

1. Phone number: (700) 821-0005

2. 3 extensions

a. Room 101, NRC Table

b. Room 101, Recovery Manager Table

c. Room 114

l 0

Page 43 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 3 of 15)

IV. (continued)

A. (continued)

3. Test

a. Check all three phones for dial tone by lifting the handset of the telephone and listening for a dial tone.

b. Using one of the phone extensions, call the NRC Operation Center (NRCOC) by lifting the handset and dialing the first number listed on the sticker located on the telephone cradle. No access code is necessary, just dial all ten digits of the number. If the main number is busy, dial the backup number. Alternate numbers until contact is made.

c. After the NRCOC Duty Officer answers, inform him as follows: "This is the St. Lucie Emergency Operations Facility. I am conducting a check of the ENS, how do you receive me?" Ask the NRCOC Duty Officer if he wishes to call back, if so give him the telephone number and await the call.

d. The test is passed if (1) all phones have dial tone, (2) the link is operable, and (3) the NRCOC is successfully contacted.

e. Record the test result on the inventory form (Attachment 6).

f. If the test is a failure, see information under Trouble Notification.

B. Health Physics Network (HPN)

1. Phone number: (700) 821-0003

2. 3 extensions

a. Room 101, NRC Table

b. Room 103 (2)

3. Go to step F, Test Procedure

Page 44 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 4 of 15)

IV. (continued)

C. Reactor Safety Counterpart Link (RSCL)

1. Phone number: (700) 821-0008

2. 2 extensions

a. Room 101, NRC Table

b. Room 114

3. Go to step F, Test Procedure D. Protective Measures Counterpart Link (PMCL)

1. Phone number: (700) 821-0006

2. 2 extensions

a. Room 101, NRC Table

b. Room 114

3. Go to step F, Test Procedure.

E. Management Counterpart Link (MCL)

1. Phone number: (700) 821-0004

2. 2 extensions

a. Room 101, NRC Table

b. Room 114

3. Go to step F, Test Procedure

Page 45 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX 8 INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 5 of 15)

IV. (continued)

F. Test Procedure for HPN, RSCL, PMCL and MCL.

1. For each communication link, do the following:

a. Check all extensions for dial tone by lifting the handset of the telephone and listening for a dial tone.

b. Check link operability by using the phones on the NRC Table in Room 101. Each link must be able to call-out and receive a call to pass. Use the following call scheme:

HPN: Dial 700-821-0008 RSCL: Dial 700-821-0006 PMCL: Dial 700-821-0004 MCL: Dial 700-821-0003

c. The test is passed if (1) all phones have dial tone and (2) the link is operable.

d. Record the test result on the inventory form (Attachment 6) for each communication link.

e. If the test is a failure, see information under Trouble Notification.

G. Local Area Network (LAN)

1. Phone number: (700) 821-0007.

2. 1 extension

a. Room 114

3. Test

a. Check the telephone line by plugging in a telephone, lifting the handset and listening for a dial tone.

Page 46 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 6 of 15)

IV. (continued)

H. Trouble Notification

1. If any aspect of the Emergency Telecommunications System is inoperable notify the NRC Operations Center in Rockville, Maryland by using a commercial telephone and dialing one of the following numbers:

(301) 951-0550 (301) 816-5100

2. Provide the following information (per IN 86-97):

a. Name of contact- Donna Calabrese, Rick Walker or Steve Knapp /R35

b. Phone number of contact - Donna Calabrese (561) 467-7185 /R35 Rick Walker (561) 467-7170 Steve Knapp (561) 467-7246

c. Location of contact- FPL/PSL 6501 S. Ocean Jensen Beach, Florida 34957

d. Any other information that would expedite repair, if known or as requested.

3. Notify Donna Calabrese, Rick Walker or Steve Knapp. /R35

4 0

0

Page 47 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 7 of 15)

IV. (continued)

I~ The Local Government Radio (LGR) has two low band radio frequencies utilized by St. Lucie County, Martin County, the St. Lucie Plant Control Rooms, the Technical Support Center and the Emergency Operations Facility. This is a backup to the State Hot Ring Down Phone Circuit.

There are two Motorola Command Series radios, one set to the primary channel, F2 (39.180 MHz, State channel 1) and the other set to the secondary channel, F1 (39.100 MHz, State channel 2) The test includes testing both

~

channels with the Unit 1 Control Room, the Unit 2 Control Room, and the Technical Support Center.

CAUTION To safeguard against potential damage resulting from lightning striking the EOF, power cords for the LGR and HP Off-Site Channel Radios are left disconnected when not in use. The phone cables to each radio are NOT to be disconnected.

1. Powering Up the Radio:

a. Plug the power cord from each radio unit into the wall outlets behind the table. The F2 light will illuminate.

b. Ensure the phone cable from each radio is plugged into one of the 3 phone jacks on the wall behind the table. All the jacks are wired for all 3 radios (LGR F1, LGR F2, and Department of Health (DOH)).

(The DOH radio is NOT included in this test).

Page 48 of 55

~ pl0 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 8 of 15)

IV. (continued)

I. (continued)

NOTE Prior to commencing the testing with the Control Rooms, contact someone at the plant to go to the TSC to assist with testing of the TSC radios.

2. Instructions for Testing:

Control Rooms

a. Call one of the Plant St. Lucie Control Rooms and ask them to standby for testing the LGR.

b. Begin by testing the radio which is set to channel F2, the channel normally monitored by the Control Rooms.

c. The radio may be operated either by depressing the "transmit" button on the console or by removing the handset and depressing the "push-to-talk" bar in the handset. The "xmit" light is lit during transmission.

Transmit the following: "St. Lucie Unit 1 or 2 (whichever you arranged to test with), this is St. Lucie EOF, come in please, over."

Following acknowledgement from the Control Room, continue with:

"St. Lucie Plant, this is the St. Lucie EOF conducting a communications test, how do you read, over?" If the Control Room confirms clear transmission and you, can confirm clear reception of the response, then have the radio switched to channel F1, following termination of the message, and standby for a test. End the transmission with: "This is St. Lucie EOF, out." If transmission is unsuccessful, call the Control Room and have the radio switched to channel F1. Proceed to the next step.

Page 49 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 9 of 15)

IV. (continued)

I. (continued)

2. (continued)

d. Now test the radio which is set to channel F1. Transmit the following:

"St. Lucie Plant, this is St. Lucie EOF, come in please, over."

Following acknowledgement from the Control Room, continue with:

"St. Lucie Plant, this is the St. Lucie EOF conducting a communications test, how do you read, over?" If the Control Room confirms a clear transmission and you can confirm clear reception of the response, then end the transmission with: "This concludes this communications test, reset the radio to channel F2, this is St. Lucie EOF, KNGR 874 over and out." If transmission is unsuccessful, call the Control Room and have the radio reset to channel F2. Proceed to the next step.

e. Record operability status on the inventory form (Attachment 6).

f. If one or both channels of the system is/are inoperable, then notify an Emergency Preparedness Coordinator or the Emergency Preparedness Supervisor.

g. Repeat the test procedure in Steps c - f above with the other Control Room.

Technical Support Center

a. Contact someone at the plant to go to the TSC to assist with the radio test, if not previously arranged.

b. Begin by testing the radio which is set to channel F2, the channel the radio in the TSC is set on.

Page 50 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 10 of 15)

IV. (continued)

I. (continued)

2. (continued)

c. Transmit the following: "St. Lucie TSC, this is St. Lucie EOF, come in please, over." Following acknowledgement from the TSC, continue with: "St. Lucie TSC, this is the St. Lucie EOF conducting a communications test, how do you read, over?" If the TSC confirms clear transmission and you can confirm clear reception of the response, then have the radio switched to channel F1 (by depressing the "F1/F2" button), following termination of the message, and standby for a test. End the transmission with: "This is St. Lucie EOF, out." If transmission is unsuccessful, call the TSC and have the radio switched to channel F1. Proceed to the next step.

d. Now test the radio which is set to channel F1. Transmit the following:

"St. Lucie TSC, this is St. Lucie EOF,, come in please, over."

Following acknowledgement from the TSC, continue with: "St. Lucie TSC, this is St. Lucie EOF conducting a communications test, how do you read, over?" If the TSC confirms a clear transmission and you can confirm clear reception of the response, then end the transmission with: "This concludes this communications test, reset the radio to channel F2, this is St. Lucie EOF KNGR 874 over and out." If transmission is unsuccessful, call the TSC and have the radio reset to channel F2. Proceed to the next step.

e. Record operability status on the inventory form (Attachment 6).

f. If one or both channels of the system is/are inoperable, then notify an Emergency Preparedness Coordinator or the Emergency Preparedness Supervisor.

3. Powering Down the Radio;

a. Unplug the phone cables from both radios from the wall phone jacks.

b. Unplug both radios from the wall outlets.

Page 51 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX 8 INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 11 of 15)

IV. (continued)

J. HP Off-site Channel is a unique 900 MHz channel (TX 939.9375-RX 900.9375) for communications with the off-site Field Monitoring Teams.

The radio is a Motorola Spectra which has been set up so that the HP Off-site

, Channel is the "home" channel, but it has also been programmed for other channels of the plant 900 MHz trunking system.

1. Powering Up the Radio:

a. Plug the power cord into the wall outlet behind the table.

b. Press the red button on the speaker box (Astron RS-12S) to the up position, button will illuminate.

c. Depress the "pwr" button on the Spectra radio.

2. Instructions for Testing:

a. Contact someone at the plant to go to the TSC to assist with the radio test, if not previously arranged.

b. The home channel is "off-site," if this channel is not selected (on the LED), then depress the "sel" button until "off-site" shows in the display.

c. Press the transmit side (with the lightning bolt) of the microphone base and announce: "St. Lucie TSC, this is the St. Lucie. EOF, come in please, over." Following acknowledgement from the TSC, continue with: "St. Lucie TSC, this is the St. Lucie EOF conducting a communications test, how do you read?" If the TSC confirms clear transmission and you can confirm clear reception of the response, then end the transmission with: "This concludes this communications test, this is St. Lucie EOF, WMIF 540 over and out."

d. Record operability status on the inventory form (Attachment 6).

P

e. If the radio is inoperable, then notify an Emergency Preparedness Coordinator or the Emergency Preparedness Supervisor.

Page 52 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 12 of 15)

IV. (continued)

J. (continued)

3. Powering Down the Radio:

a. Depress the "pwr" button on the Spectra radio.

b. Press red button of the speaker box to the down position (light will extinguish).

c. Unplug the power cord from the wall outlet.

K. The State Warning Point (SWP) Hot Ring Down (HRD) circuit is a dedicated phone system linking the State agencies, St. Lucie County and Martin County with the Plant Control Rooms, Technical Support Center and the Emergency Operations Facility.

1. Instructions for Testing.

a. Go to the Division of Emergency Management's office Room 108, in the EOF and locate the phone labeled Hot Ring Down (HRD).

b. Pick up the handset and dial the State Warning Point (SWP) in Tallahassee. This is done by dialing 100. The State Warning Point Duty Officer will acknowledge by saying, "This is State Warning Point, go ahead." You in turn will announce "This is St. Lucie EOF, I am conducting a communications check, how do you receive me? The State will acknowledge. Request the State Warning Point to call you back on Station number 123.

C P

,, Page 53 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 13 of 15)

IV. (continued)

K. (continued)

1. (continued)

I

c. Self test procedure for additional extensions.

(1) Conduct a self test on 2 extensions.

A. Extension 120 in the conference room B. Extension 122 in the bull pen (2) To perform the self test, adjust the volume control to the mid-range position. Lift the handset and press the push to talk bar while speaking into the handset mouthpiece. You should hear yourself in the handset earpiece (this is called sidetone). Now locate the black button on the rear of the telephone next to the power connector. Activate the test mode by holding this button down while simultaneously depressing the push to talk bar and speaking into the handset mouthpiece. Voice should now be heard in the speaker.

Satisfactory completion of the self test is determined when the presence of sidetone is detected while pressing the push to talk bar and speaking into the handset, and when a loopback of the speaker's voice is heard in the loudspeaker while pressing the test switch located on the rear of the terminal. The self test is a complete audio loopback of the terminal's audio circuits up to, but not including, the line matching transformers. As such, this test is a good method to evaluate instrument performance.

d. Record operability status on the inventory form (Attachment 6).

e. If the system is inoperable, notify an Emergency Preparedness Coordinator or the Emergency Preparedness Supervisor.

Page 54 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 14 of 15)

IV. (continued)

L. "Videolink" - the "Videolink" is a closed circuit audio/visual communications link originating in the TSC with feeds to the OSC and the EOF.

1. Instructions for Testing

a. Contact someone at the plant to go to the TSC to assist with the test of the "Videolink", if not previously arranged.

b. Obtain key ¹14 from the keybox in room 107. The key to the keybox is located on the wall next to the box.

c. Use key ¹14 to unlock room 132.

d. Turn on the master video switch located in the rack mount cabinet.

e. In the "Bullpen", room 101, turn on the two television sets using the remote controls (one for each television set) on the Recovery IVlanager's table.

f. Set the channel selector to channel 7 and adjust volume.

g. Request the person in the TSC to provide a test broadcast.

h. Operability is verified if both the video picture and the audio output are received on both television sets. The picture must be clear and the audio free from static.

i. Record operability status on the inventory form (Attachment 6).

j. If the "Videolink" is inoperable (one or both television sets), notify Emergency Planning.

Page 55 of 55 ST. LUCIE PLANT HEALTH PHYSICS OPERATING PROCEDURE NO. HP-90, REVISION 35 EMERGENCY EQUIPMENT APPENDIX B INSTRUCTIONS FOR TESTING EMERGENCY COMMUNICATIONS EQUIPMENT (Sheet 15 of 15)

IV. (continued)

L. (continued)

1. (continued)

k. Following the completion of the test:

1. Tum off both television sets in room 101.

2. Turn off the master video switch in room 132.

3. Lock room 132.

4. Return key 414 to the keybox.

V. Site Assembly Station A. Conduct functional check of the Site Assembly Station (SAS) telephone located on the west wall.

1. Place a local call and request a call back to ensure that the phone works properly.

2. Record operability status on the inventory form (Attachment 4).

3. If the phone is inoperable, notify Emergency Planning.

~ '

L

~ "'

gg+ c Procedure No.

ST. LUCIE PLANT EF iP-04 EMERGENCY PLAN Current ev. No.

F L IMPLEMENTATIONPROCEDURE 4 SAFETY RELATED ective Date:,

07107199

Title:

ACT ATION AND OPERATION F THE T CHNICAL SUPPORT C TER Responsible Departme t: EMERGENCY PLANNIN Revision Summary s

Revision 4 - Removed refe nce to the rotating myi tenance shift supervisor filling the position of TSC coordinator th OSC. (J. R. Wa Ker, 07/01/99)

PSL O

I-GC O

C3 PROCEDURE PRODUCTION Revision FRG Review Date Approved By App oval Date S OPS DATE 12/15/97 J. Scarola 12 5/97 DOCT PROCEDURE Plant General Manager DOCN EPIP-04 SYS R (sion FRG Review Date Approved By Approval ate COMP COMPLETED 4 07/01/99 R. G. West 07/01/9 ITM 4

/ Plant General Manager N/A Designated Approver

0

'.","" > v U ~

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 2 of 84 EPIP-04 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE .. ~ . ~.... ~................. ~ .. ~........... ~ 4

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS 6 3.0 RESPONSIBILITIES 7 3.1 Emergency Coordinator ~ ~ .. ~ ~ ~ ~ 7 3.2 TSC EC Assist/Logkeeper 8

~ ~ ~ ~

3.3 TSC Supervisor ~ . 8 3.4 TSC Coordinator with OSC . 8

~

3.5 TSC OPS Coordinator ~ ~ ~ ~ 9 3.6 TSC Reactor Engineer ..... 9 3.7 TSC,Chemistry Supervisor .. 9 3.8 TSC HP Supervisor ~...... 10 3.9 TSC Security Supervisor 10 3.10 TSC Problem Solving Team . ~ ~ 10 4.0 DEFINITIONS ~........... ~,..... ~ ~ .. ~.... ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 0 5.0 INSTRUCTIONS ............;.... ~...........

~ 12 ATTACHMENTS ATTACHMENT 1 TSC Emergency Response Organization and Shift Staffing... ~....... ~............ ~.... ~ 14 ATTACHMENT2 TSC EC Assist/Logkeeper Checklist..... 5...... '.

15 AT1 ACHMENT 2A Typical Information to be Included in the EC Logbook .. ~....... ~... ~...... ~........ 17 ATTACHMENT3 TSC Supervisor Checklist .... ~.......... ~.... 18 ATTACHMENT3A TSC ERO Shift Staffing and Accountability Roster... 22 3B TSC Minimum Staffing Requirements ~... ~....... 23 'TTACHMENT ATTACHMENT3C TSC Facility Briefings . ~ ~ .. ~.... ~ . ~ .., .. ~.... 24 ATlACHMENT3D Guidelines for Relocation of the TSC ............ 25

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 3of84 EPIP-04 ST. LUCIE PLANT TABLE OF CONTENTS (CONTINUED)

SECTION PAGE ATTACHMENTS (continued)

ATTACHMENT4 TSC Communicator Checklist ................. 28 ATTACHMENT4A Communications Guidelines ~..... ~......... .. ~ 32 ATTACHMENT4B Safety Functions Equipment Status and Radioactive Gaseous Source Terms - Unit 1, Unit 2 ~......... 37 ATT ACHMENT 5 TSC ERDADS Operator Checklist ~ ~ ~ ~ ~ ~ ~ 41 ATTACHMENT5A ERDADS Data Acquisition ~ . ~ .. ~ ~........... ~ . 43 ATTACHMENT5B ERDADS Data Points ~...................... 46 ATTACHMENT6 TSC Administrative Staff Checklist.............. 54 ATTACHMENT7 TSC Coordinator with OSC Checklist ~..... ~....

. 57 A IlACHMENT 7A Re-entry/SAMG Worksheet ................... 59 ATTACHMENT7B Re-entry Log ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 64 ATTACHMENT8 TSC OPS Coordinator Checklist... ~.... ~....... 65 ATTACHMENT9 TSC Reactor Engineer Checklist ~ ~... ~.... ..

~ . ~ 68 ATTACHMENT9A Initiating and Terminating the ERDS Link ......... 71 ATTACHMENT 10 TSC Chemistry Supervisor Checklist ......... .. ~ 73 ATTACHMENT 11 TSC Dose Assessor Checklist ..... ~........ ~ .. 76 ATTACHMENT 11A Off-Site Radiological Assessment .. ~... 78 ATTACHMENT 11B Protective Action Recommendations............. 79 ATTACHMENT 12 TSC Problem Solving Team Checklist 80 ATTACHMENT 13 TSC Security Supervisor Checklist............. 82

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 4 of 84 EPIP-04 ST. LUCIE PLANT 1.0 PURPOSE 1.1 Discussion This procedure provides instructions for the activation and operation of the Technical Support Center (TSC).

1.2 Location and Description The TSC is on the 62 foot elevation of the Unit 1 Reactor Auxiliary Building (RAB). The TSC is located adjacent to the Unit 1 Control Room and is enclosed in the same habitability envelope. The TSC has emergency communications equipment, precalculated emergency data, pertinent reports, plans, procedures and drawings available for use.

Should the Unit 1 Control Room envelope require evacuation, alternate locations for the TSC have been identified as follows:

1 ~ South Service Building

2. Nuclear Training Center 1.3 TSC Functions

1. Mandatory Functions NOTE The following tasks become the responsibility of the Emergency Operations Facility (EOF) when manned and fully operational.

A. Relief to the Control Room for off-site communications to the State and local agencies and the NRC in accordance with EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

B. Performance of off-site dose calculations in accordance with EPIP-09, Off-site Dose Calculations.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 5of84 EPIP-04 ST. LUCIE PLANT 1.0 PURPOSE (continued) 1.3 TSC Functions (continued) h

2. Additional Functions A. Management of emergency mitigation activities.

B. Technical support in determining current and projected plant status and providing in-depth diagnostic and engineering assistance to the Control Room.

C. Direct the re-entry activities of the Operational Support Center (OSC) ~

D. Coordination with the Emergency Operations Facility (EOF) regarding emergency status, corrective and protective actions, off-site interface, radiological conditions, core damage assessment, etc.

1.4 Minimum Staffing The following is the list of the minimum positions needed for TSC operation:

Emergency Coordinator TSC Supervisor TSC Chemistry Supervisor TSC Reactor Engineer TSC Elec Rep - PST (Problem Solving Team)

TSC Mech Rep - PST (3) TSC Communicator (HRD, ENS, EOF) 1.5 Activation Activation of the TSC is the responsibility of the Emergency Coordinator (EC) and is required for an Alert or higher declared emergency. Arrangements have been made to staff the TSC in a timely manner.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 6 of 84 EPIP-04 ST. LUCIE PLANT 1.0 PURPOSE (continued) 1.6 Operations The TSC has sufficient space to accommodate the Florida Power 8 Light Company (FPL) response organization and designated representatives of the Nuclear Regulatory Commission (NRC) Site Team. Arrangements have been made which allow for continuous operation, as necessary.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

2.1 REFERENCES

1 ~ St. Lucie Plant Technical Specifications Unit 1 and Unit 2 (Section 6.10.1)

2. St. Lucie Plant Updated Final Safety Analysis Report (UFSAR)

Unit 1 and Unit 2

3. St. Lucie Plant Radiological Emergency Plan (E-Plan)

4. St. Lucie Plant Topical Quality Assurance Report (TQAR)

5. E-Plan Implementing Procedures (EPIP 00-13)

6. HP-200 Series Procedures

7. ADM-17.09, Invoking 10 CFR 50.54(x)

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE TECHNICALSUPPORT CENTER '7 of 84 PROCEDURE NO.

EPIP-04 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS (continued)

2.1 REFERENCES

(continued)

8. ADM-17.11, 10 CFR 50.59 Screening

9. St. Lucie Plant Emergency Response Directory (ERD)

10. QI-17-PSL-1, Quality Assurance Records

11. ERDADS Reactor Operator's Manual (8770-12058)

12. Fitness for Duty Rule, 10 CFR 26

13. NUREG 1394, Emergency Response Data System (ERDS) 2.2 RECORDS REQUIRED 1 ~ The following shall be retained following a plant emergency:

~ Checklists, data and paperwork generated per this procedure.

~ Log books maintained during the plant emergency.

2. Recorded information shall be forwarded to Emergency Planning following the event, for review and archival in accordance with Technical Specification 6.10.1 and Ql 17-PR/PSL-1.

2.3 COMMITMENTDOCUMENTS

1. PMAI PM97-04-142, Training Drill Critique 1/24/97, (ERDADS screen mimics and full staffing guidance)

2. Condition Report 97-1389, (Emergency Supplies) 3.0 RESPONSIBILITIES 3.1 Emergency Coordinator (EC)

1. The responsibilities for this position are provided in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO. TECHNICAL SUPPORT CENTER Sof84 E PIP-04 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.2 TSC EC Assist/Logkeeper 1 ~ Initiates and maintains the EC Logbook.

2. Provides assistance to the EC to ensure.EC responsibilities are met.

3. Performs duties as directed/assigned by the EC.

3.3 TSC Supervisor

1. Provides command and control of TSC activities.

2. Supervises the TSC staff particularly the communicators and administrative personnel.

3. Coordinates activities to ensure adequate support of the EC.

4. Ensures communications are performed with off-site agencies until the EOF is activated.

5. Ensures the communication flow is maintained within the facility and with the Control Room, OSC and EOF.

6. Coordinates facility briefings.

7. Arranges for long term operation of the TSC.

3.4 TSC Coordinator with the OSC

1. Serves as the coordinator with the OSC.

2. Provides the OSC with requests for Re-entry Teams.

3. Tracks the re-entry activities of the OSC.

4. Updates the TSC regarding OSC team status and corrective actions.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 9 of 84 EPIP-04 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.5 TSC OPS Coordinator NOTE This position is filled by two persons, one located in the affected unit's Control Room, the other in the TSC.

1 ~ Provides expertise in plant operations to the EC in the TSC.

2. Provides communications assistance to the NPS in the affected Control Room.

3. Ensures the unaffected unit's Control Room is kept apprised of the status of the emergency.

4. Maintains communication flow between the TSC and the affected Control Room concerning status of operations.

Serves as primary Severe Accident Management Guidelines (SAMG) decision maker.

3.6 TSC Reactor Engineer

1. Monitors critical safety functions for indications of core status.

2. Assists Nuclear Fuels personnel in the EOF in assessment of core damage.

3. Assists in Severe Accident Management Guidelines (SAMG) evaluation.

3.7 TSC Chemistry Supervisor

1. Directs dose assessment activities in the TSC.

2. Keeps the EC apprised of chemistry related issues.

3. Assists the Chemistry Supervisor in the OSC.

REVISION No.: PROCEDURE PAGE:

TITLE.'CTIVATION 4 AND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 10 of 84 EPIP-04 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.8 TSC HP Supervisor (TSCHPS)

1. The responsibilities for this position are provided in HP-200, Health Physics Emergency Organization.

3.9 TSC Security Supervisor 1 ~ Establishes and maintains site accountability.

2. Arranges site access for the NRC Site Team.

3. Controls on-site security operations throughout the emergency.

3.10 TSC Problem Solving Team (PST)

1. Evaluates plant conditions and provides recommendations. to the EC.

2. Anticipates component failures and accident consequences.

3. Researches affected systems and components.

4. Develops mitigation strategies and/or countermeasures.

5. Performs Severe Accident Management Guidelines (SAMG) evaluation.

4.0 DEFINITIONS 4.1 Facility Status

1. Activation - the request to staff and establish an Emergency Response Facility (ERF).

2. Operational - when sufficient personnel (i.e., minimum staff) are available to accomplish the mandatory facility functions of off-site notifications and dose calculations.

3. Fully Staffed - the complete complement of personnel is present in the facility.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 11 of 84 E PIP-04 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4.2 FPL Emergency Recall System (ERS) - the call-out system used as a means of off hours call-out, as described in EPIP-03, Emergency Response Organization/Staff Augmentation.

4.3 Videolink - a closed circuit audio/visual communications link originating in the TSC with feeds to the OSC and the EOF allowing the EC briefings to be available in all the Emergency Response Facilities (ERFs).

REVISION No.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 12 of 84 E PIP-04 ST. LUCIE PLANT 5.0 INSTRUCTIONS NOTE

~ This section provides general information and instructions for all TSC responders.

~ Position specific checklists are included as attachments to this procedure.

~ Individuals specifically designated as members of the TSC Emergency Response Organization (ERO) are identified in the ERD.

5.1 When notified, TSC emergency responders are to report to the facility as quickly as possible.

5.2 The initial responder to the TSC should do the following:

1. Unlock the facility with a key from the NPS, Assistant Nuclear Plant Supervisor (ANPS), or Shift Technical Advisor (STA). If these persons are unavailable, break the glass to the keybox next to the door and remove the key.

2. Turn on the facility lights.

3. Open the document cabinets.

5.3 Upon arrival at the facility, each TSC emergency responder should perform the following:

1. Sign-in on the status board on the South (rear) waIl of the facility in the space corresponding to your position.

2. Obtain a "Player" badge and place your name (and position title, if necessary) on the badge with a dry erase marker or in any other non permanent manner.

3. Obtain position specific notebook with procedural checklists, forms and instructions.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 13 of 84 E PIP-04 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.3 Upon arrival at the facility, each TSC emergency responder should perform the following: (continued)

4. Make your workstation/location oper'ational.

5. Notify your supervisor or the TSC Supervisor of your readiness status.

6. Assist in establishing accountability by signing-in on a form similar to Attachment 3A, TSC ERO Shift Staffing and Accountability Roster.

g, 5.4 Only controlled copies of nuclear safety-related procedures, drawings and other available plant information shall be used. Non-controlled documents or drawings should be verified with a controlled copy prior to use in the TSC, 5.5 During facility briefings, stop what you are doing, pay attention and contribute, as requested.

5.6 Upon termination of the event:

All TSC personnel should return their workstations/locations to a normal state and assist in restoring the facility to a ready condition.

2. Collect all significant information and documentation, such as completed EPIPs and attachments, logs, notification forms and other notes and data sheets, and forward this material to Emergency Planning.

END OF SECTION 5.0

101 ITl 8

EMERGENCY U O 0 Z

COORDINATOR O 102 U 0

TSC SvpewIsor CO C

z0 I XI Q

J r

I Z 8 r"

I 113 ~ I 113 TSC SP Phcnetafker 114 TSC ERDADS Oper 0 O TSC SP 118 TSC ERDADS Tech C L Phcnelaaer~

(Located Iri Ihe 121 TSC Admin StaN (2) 0l ilt Contrd Room.) 108 TSC Conimunhalor (3) 0 (ENS Coinm) m(

0> r~

~ (HRD Ccnvn) 0 (EOF COmm) 0 Z ZH" m 0) zp 0z 124 122 120 r - a 158 OSC XK Q

~n rz0 CO TSC EC Asstl Logkeeper TSC EP Coordinator Coordinator with OSC Coordinator with TSC 0 (=p Zm m (Nd a reqdred posiyhis) (tocaNd in the OSC.)

NZ ~ lTl 33

'05 ~', 0 0p 1110 TSC OPS 110 TSC OPS TSC Reactor 103 TSC KP 115 TSC PST ;

104 TSC Chemsuy

~

180 TSC Secu

'Supervisor z mz Coordnatcr J (Located in Ihe Cocrrrrohr Eny'neer n4sor leader Supeviscr Mole 3)

Z zHP Conlrd Rcoa) 112 TSC HP Comm (2) 0107 TSC Enc Rcp PST 111 TSC 0 lTl ~

(HPN Comm) 0108TSCMcchRep PST(3) i Dose Assessor Zl ~

AutNfiafer position numbers are gsted with position tiths.

(FMT COmm) (Note I) 117 TSC Iao Rep4iST (Note 2) U) x z m

118 TSC SRO RepPST

~ 30 mlnuto response goal, per NUREG 0654, Table B-1 U) o 60 minute response goal, per NUREG 0654, Table B.f (PNPlarvEPIP44 F fffto)

Note 1 Only one person is required as minimum staff.

No<<2 The Dose Assessor functhn wiN initiallybe performed by the on. shift Chemist.

Z Q m

Note 3 The TSC Security Supervisor poslthn Is filled by the on-shift Security Shift Spedalist. G)

C3 Indhates minimum staffing posithns that must be filled In order to dedare the fadlity operathnal. 0 00

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 15 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT2 TSC EC ASSIST/LOGKEEPER CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to section 5.0 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITYOPERATION

1. Remove the EC Logbook from the EC position notebook and initiate the EC Log (use Attachment 2A, Typical Information to be Included in the EC Logbook).

2. Review the requirements of EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3. Steps to occur continually while the facility is in operation:

a. Maintain the EC Logbook.

b. Assist the EC in the completion of the requirements of EPIP-02.

c. Ensure checklists/paperwork are properly completed.

d. Verify that the EC approves all off-site notification forms.

e. Remind the EC of time limits for notification of off-site agencies.

f. Provide EC a summary of recent log entries for facility briefings.

g. Support EC as needed or requested.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 16 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT2 TSC EC ASSIST/LOGKEEPER CHECKLIST (Page 2 of 2)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Ensured all facility activities closed out.

/

2. Closed out the EC Log, returned the Logbook to the EC position notebook and returned the notebook to the storage cabinet.

3. Ensured all paperwork collected.

4. Returned position notebook to storage cabinet.

5. Provided all completed paperwork to, Emergency Planning.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 17 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT2A TYPICAL INFORMATION TO BE INCLUDED IN THE EC LOGBOOK (Page 1 of 1)

Maintaining concise, detailed logs during an emergency event is important.

Following the event, all information recorded will be needed to provide a clear picture of actions taken.

A., The following information should be included in the EC Logbook:

1. Key events (e.g., classification changes, injuries, etc.).

2. Status changes in equipment, radiological conditions, personnel, etc.

3. Decisions made or actions taken.

4. Other items of significance.

B. Log entry requirements:

1. Time of entry.

2. Use ink.

3. Write/print legibly.

4. Use concise and accurate wording.

5. Strike through and initial changes.

6. Do not remove pages from the log.

REVISION No.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 18 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT3 TSC SUPERVISOR CHECKLIST (Page 1 of 4)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL Refer to Section 5.0 of this procedure (included in the position notebook) and review the general instructions.

2. Determine operational readiness of the TSC by verifying the following:

NOTE Attachment 3B, TSC Minimum Staffing Requirements, should be used to determine staff and suitable alternates.

a. Minimum staff available (use to Attachment 3A, TSC ERO Shift Staffing and Accountability Roster).

b. Communications equipment, procedures and other supplies are available, checked and ready to use.

~ Commercial phone as backup to State/County and NRC Notifications (DO NOT test call HRD or ENS) ~

~ Extension phones in TSC.

~ Procedure, drawing, tech manual cabinets unlocked.

~ TSC personnel are verifying procedures in position notebooks.

c. Minimum staff prepared to accomplish mandatory facility functions.

3. Recommend to the EC that the TSC should be declared operational. Operational at

S REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 19 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3 TSC SUPERVISOR CHECKLIST (Page 2 of 4)

A. (continued) INITIAL NOTE Unless authorized by the EC, facility staffing should be in accordance with Attachment 3A, TSC ERO Shift Staffing and Accountability Roster.

4. Review additional staffing status with the EC.

5. TSC fully staffed.

6. Ensure that the EC log, completed notification forms and checklists and any other pertinent information have been faxed to the EOF.

B. FACILITYOPERATION 1 ~ Initiate the TSC Logbook.

NOTE The TSC Reactor Engineer, in coordination with the Shift Technical Advisor (STA), is responsible for establishing the communication between the St. Lucie Plant's Emergency Response Data Acquisition and Display, System (ERDADS) and the NRC's Emergency Response Data System (ERDS).

2. Ensure ERDADS Link with the NRC (ERDS) established/

attempted.

Obtain food and water supply for the Unit 1 Control Room/TSC personnel.

4. Obtain food and water supply for the Unit 2 Control Room personnel.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO. TECHNICAL SUPPORT CENTER 20 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3 TSC SUPERVISOR CHECKLIST (Page 3 of 4)

B. (continued) iNITIAL

5. Arrange for long term staffing (use Attachment 3A, TSC ERO Shift Staffing and Accountability Roster).

6. As directed by the EC, initiate steps for relocation of the TSC (use Attachment 3D, Guidelines for Relocation of the TSC).

7. Steps to occur continually while the facility is in operation:

a. Maintain the TSC Logbook.

b. Manage/supervise activities of TSC Communicators (HRD, ENS, EOF, HPN, Sound-Powered Phonetalker, FMT).

c. Manage/supervise activities of the TSC Administrative Staff.

d. Maintain low noise levels in the facility.

e. Coordinate overall support functions of the TSC.

f. Conduct briefings in accordance with Attachment 3C, TSC Facility Briefings.

g. Ensure the OSC is kept well informed regarding emergency status and plant conditions (an audio/video link may be used for this purpose) ~

h. Ensure the EOF is kept well informed regarding emergency status and plant conditions (an audio/video link may be used for this purpose).

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 21 of 84 EPIP-04 ST. LUCIE PLANT ATlACHMENT 3 TSC SUPERVISOR CHECKLIST (Page 4 of 4)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. All communications links terminated.

2. All communications paperwork collected.

3. All facility activities closed out.

4. All documents, equipment and supplies returned to pre-activation condition and/or location.

5. Closed out TSC Logbook.

6. Returned position notebook to storage cabinet.

7. Provided all completed paperwork to Emergency Planning.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 22 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT3A TSC ERO SHIFT STAFFING AND ACCOUNTABILITYROSTER (Page 1 of1)

Shift' Hours To POSITION BADGE POSITION BADGE NAME NAME (Minimum staff in bolds) NO. (Minimum staff in bolds) NO.

Emergency Coordinator TSC HP Comm TSC Supervisor TSC HP Comm TSC SP Phonetaiker (in TSC)

TSC Chemistry Supervisor TSC SP Phonetaiker (in Control Room)

TSC Reactor Engineer TSC ERDADS Operator TSC Communicator TSC PST Leader TSC Communicator TSC ERDADS Tech TSC Communicator TSC l&C Rep - PST TSC Elec Rep- PST TSC SRO Rep - PST TSC Mech Rep - PST TSC Coordinator with OSC TSC Mech Rep - PST TSC Admin Staff TSC Mech Rep - PST TSC Admin Staff TSC HP Supervisor TSC EC Assistf Logkeeper TSC Security Supervisor TSC EP Coordinator (not required)

TSC OPS Coord (in TSC)

TSC OPS Coord (in Control Room)

TSC Dose Assessor

'ong term staffing, refer to the St. Lucie Plant Emergency 2

Response Directory (ERD) for position alternates.

Long term staffing includes the Control Rooms, attach list to this sheet.

s Refer to Attachment 3B, TSC Minimum Staffing Requirements, to this attachment for temporary alternates "for minimum staff positions.

4 TSC Communicator position fills the following positions:

a. TSC ENS Communicator

b. TSC HRD Communicator

c. TSC EOF Communicator

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 23 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3B TSC MINIMUMSTAFFING REQUIREMENTS (Page 1 of 1) ff in Qualifications/

Major Functional Position Title and ID Position Temporary Alternate Area'enior No.'mergency Senior Manager with Emergency Mgmt. Rep. Coordinator, 101 Coordinator qualifications Off-site Dose Assessment TSC Chemistry Supv, 104 Member of Chemistry Department Member of the Reactor Engineering Core/Thermal Hydraulics TSC Reactor Engineer, 105 Department or current or prior STA TSC responder with STA or equivalent background for ENS Notification/Communication TSC Communicator, 106 Communicator Technical/operational background for HRD or EOF Communicator Electrical Engineer or Electrical Electrical TSC Elec Rep - PST, 107 Maintenance Supervisor Mechanical Engineer or Mechanical Mechanical TSC Mech Rep - PST, 108 Maintenance Supervisor Facility Command and TSC Coordinator with OSC TSC Supervisor, 102 1 Control This function(s) may be accomplished during the first 75 minutes of an emergency by an individual(s) meeting the corresponding listed qualifications.

These Emergency Response Organization (ERO) positions were established to accomplish the indicated function(s).

REVISION No.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 24 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3C TSC FACILITYBRIEFINGS (Page 1 of 1)

NOTE Briefings should be carried by the Videolink.

A. GENERAL GUIDELINES

1. Conducted by the TSC Supervisor or his/her designee.

2. Establish a frequency (e.g., approximately every 30 minutes).

3. Set criteria (i.e., attendance, noise and activity level, circulation of information, etc.) ~

B. GENERAL FORMAT - the following information should be included in facility briefings.

1. Initial status and summary by the Emergency Coordinator to include:

a. Time of the briefing.

b. Emergency Classification.

c. Plant status (affected unit, unaffected unit).

d. Radiological conditions (e.g., release in progress, contaminated areas, etc.) ~

e. Status of protective actions (e.g., site evacuation, actions underway by the public, etc.).

f. Status of activities underway in the facility.

2. Request input/update information from other representatives:

a. Operations.

b. Health Physics (including field monitoring activities).

c. Reactor Engineering (including dose assessment).

d. Problem Solving Team.

e. TSC Coordinator with the OSC (including re-entry activities).

3. Major activities underway in other facilities.

4. Concerns or questions.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 25 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3D GUIDELINES FOR RELOCATION OF THE TSC (Page 1 of 3)

If habitability of the Unit 1 Control Room is challenged (e.g., due to fire/smoke) and evacuation is required, the TSC will need to be relocated. The following guidelines are provided to assist in this endeavor.

A. Emer enc Coordinator

1. Transfer the responsibilities of the EC as follows:

a. Classification of the emergency - NPS NOTE The EOF, once operational, has responsibility for recommending protective actions and for off-site notifications.

b. Protective Action Recommendations (PARs) - NPS

c. Decision to notify off-site officials and the content of notification messages - NPS

d. Request the unaffected Control Room ANPS to support the NPS in off-site notifications.

2. Conduct a transfer of EC responsibilities with the NPS (via phone conversation) once the alternate TSC is prepared to go operational.

~. T~SG S

1. In conjunction with the EC and the TSC HP Supervisor, determine the appropriate area to relocate the TSC. Choose one of the following:

a. South Service Building

b. Nuclear Training Center

2. Direct the evacuation by briefing TSC personnel on location, travel route, materials to take and any immediate actions prior to leaving the facility (e.g., formally terminate communications, turn off equipment, etc.)

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 26 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3D GUIDELINES FOR RELOCATION OF THE TSC (Page 2 of 3)

B. (continued)

3. Re-establish command and control of TSC functions as quickly as possible.

a. Transfer the responsibility for off-site notifications from the unaffected Control Room (if this responsibility has not been transferred to the EOF) to the communicators in the relocated TSC.

C. All TSC Personnel Formally discontinue communications.

2. Gather position notebooks and other pertinent materials.

3. Travel per the prescribed route to the alternate TSC location.

4. Assist Security in re-establishing accountability as quickly as possible.

5. Re-establish TSC functions as quickly as possible.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO. TECHNICALSUPPORT CENTER 27 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT3D GUIDELINES FOR RELOCATION OF THE TSC (Page 3 of 3)

Suggested Arrangements and Equipment Availability at Alternate TSC Locations:

SOUTH SERVICE BUILDING NUCLEAR TRAINING CENTER Communications HRD Phone EP area fourth floor Simulator ENS Phone Any commercial phone Any commercial phone HPN Phone Any commercial phone Any commercial phone EOF Phone Any commercial phone Any commercial phone FMT Radio EP area fourth floor Simulator Dose Assessment Class A Model EP area fourth floor Technical Training area second floor TSC Functions Command and EP area fourth floor Conference room and Control Supervisor offices second floor Problem Engineering area Conference room Solving Team third floor second floor Other Cubicles second and Cubicles second floor fourth floor

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 28 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4 TSC COMMUNICATOR CHECKLIST (Page 1 of 4)

NOTE

1. This checklist applies to the following Communicator positions in the TSC:

HRD Communicator ENS Communicator EOF Communicator Sound-powered Phonetalker (CR/TSC)

2. The responsibilities of the TSC HP Communicators are provided as follows:

HPN Communicator - in HP-200, Health Physics Emergency Organization FMT Comm/Coord - in EPIP-10, Off-site Radiological Monitoring

3. When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

NOTE Communicator positions should be filled in the following order:

1. Hot Ring Down (HRD) Phone

2. Emergency Notification System (ENS)

3. EOF

4. Sound-powered Phone (CR)

5. Sound-powered Phone (TSC)

2. Filling the position of

3. Review appropriate information in Attachment 4A, Communications Guidelines.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 29 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4 TSC COMMUNICATOR CHECKLIST (Page 2 of 4)

B. FACILITYOPERATION

1. Steps to occur continually while the facility is in operation:

HRD Communications

a. Assist the EC with State and County notifications by preparing the State Notification Form (see Attachment 2 in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

b. Ensure notifications are initiated within 15 minutes of a classification/Protective Action Recommendation (PAR) change or other significant event.

c. Ensure State Notification Forms:

1. Contain PAR information that matches the PAR Worksheet (see Attachment 5 in EPIP-02).

d. Request the TSC EC Assist/Logkeeper log notification times.

ENS Communications

a. At an Alert or higher emergency classification, request the NRC to establish the ENS conference bridge.

b. Maintain an open line of communication and a transmission log (initially, this will be the NRC Notification Form in Attachment 7 of EPIP-02).

c. Ensure notifications are initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (immediately following State and County notification) of a classification/PAR change or other significant event.

d. Request the TSC EC Assist/Logkeeper log notification times.

e. Log all questions asked by NRC.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 30 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4 TSC COMMUNICATOR CHECKLIST (Page 3 of 4)

B. (continued)

1. (continued)

ENS Communications (continued)

f. Obtain answers to questions from appropriate TSC staff member.

g. Obtain EC approval prior to providing additional information to the NRC.

EOF Communications

a. Maintain an open line of communication with the EOF.

b. If ERDADS is out of service, use Attachment 4B, Safety Functions Equipment Status and Radioactive Gaseous Source Terms, to obtain plant parameter and radiological data (use Attachment 4B) via the Sound-powered Phonetalker and share the information with the EOF (via the TSC Communicator in the EOF).

c. Provide clarification of any discrepant information as'equested by the EOF.

Sound-powered Phonetalker

a. Provide an open line of communication between the affected Control Room and the TSC.

b. Provide fan status for dose assessment.

c. Provide clarification of data and/or obtain additional data as requested by the TSC.

d. If ERDADS is out of service, use Attachment 4B, Safety Functions Equipment Status and Radioactive Gaseous Source Terms, to obtain plant parameter and radiological data.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 31 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4 TSC COMMUNICATOR CHECKLIST (Page 4 of 4)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

All communications links (HRD, ENS, EOF, Sound-powered phone) terminated.

2. All communications paperwork collected.

3. All phone equipment returned to pre-activation condition.

4. Returned position notebook to storage cabinet.

5. Provided all completed paperwork to the TSC Supervisor.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 32 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4A COMMUNICATIONS GUIDELINES (Page 1 of 5)

NOTE If communications are associated with drill or exercise, the statement "This is a drill" should precede and follow the actual message.

A. GENERAL GUIDELINES

1. Always speak clearly, firmly and with normal tone when using any communication system.

2. The sender and receiver should be clearly identified.

3. Message text:

a. Communication must be free of ambiguity. Slang terms should not be used. Avoid the use of words that sound alike; for example, avoid increase and decrease, use raise and lower instead.

b. Communications must be specific. Use noun names for plant equipment, not acronyms; for example lower pressure safety injection pump instead of LPSI ~

c. The phonetic alphabet should be used to identify specific train, bus, channel or equipment designations, not just letter identifier; for example, refer to the 1Alpha heater drain pump, not the 1A heater drain pump. The following is the phonetic alphabet to be used:

A Alpha J Juliet S Sierra B Bravo K Kilo T Tango C Charlie L Lima U Uniform D Delta M Mike W Whiskey E Epsilon N November X X-ray F Foxtrot 0 Oscar Y Yankee G Golf P Papa Z ZUIU H Hotel Q Quebec I India R Romeo

d. The phonetic alphabet should not be used for stringed letter references, acceptable acronyms or location symbols; for example, AB bus, AC or DC, TSC, respectively.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO. TECHNICAL SUPPORT CENTER 33 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT4A COMMUNICATIONS GUIDELINES (Page 2 of 5)

A. (continued)

4. Acknowledgement and confirmation (3-way communication) - messages shall be comprised of proper transmission, acknowledgement, and confirmation.

a. The message is properly transmitted from the originator to the receiver.

b. The message receiver should acknowledge the communication by giving functional repeat-back to the message originator. The repeat-back can be provided by either paraphrasing or explaining the message in one's own words, or by verbatim repeat-back. In all cases, verbatim repeat-back should be used for equipment identifiers.

c. If the message receiver does not understand the message he/she should ask for the message to be repeated.

d. If an incorrect repeat-back is given, the message originator should immediately correct the miscommunication with a statement such as, "WRONG", followed by restating the correct message.

e. The message originator should confirm the acknowledgement (repeat-back) with a statement such as, "That is correct".

5. The Call Sign should be used periodically when using the Local Government Radio (LGR).

6. Prior to transmission, ensure that information has been verified and approved by the appropriate authority, as necessary.

7. Ensure that any incoming pertinent information is provided to the TSC Supervisor and the Emergency Coordinator or designee.

8. Maintain documentation of any significant information provided or received.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 34 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT4A COMMUNICATIONSGUIDELINES (Page 3 of 5)

B. COMMUNICATIONS SYSTEMS

1. State Warning Point (SWP) Hot Ring Down Phone (HRD)

a. This is the primary communications pathway to the State Warning Point and St. Lucie and Martin Counties.

b. A self-verifying phone system which is initiated by entering the 3 digit code corresponding to the desired location of contact. The codes appear on a list in a pull-out drawer attached to the base of the phone or in the St. Lucie Plant Emergency Response Directory (ERD). A confirmation ring-back (double tone) will be heard if the dialed terminal is successfully contacted. When the party answers, begin transmission by depressing the "push-to-talk" bar in the handset. Release the "push-to-talk" bar to receive response.

2. NRC Emergency Notification System (ENS)

a. This is the primary communications pathway to the NRC.

b. Part of the NRC FTS 2000 phone system. Initiate contact by dialing (direct, no access code needed) one of the phone numbers provided on the phone or in the ERD. This will become an open line of communication at the Alert or higher emergency class. The EOF will join the conference bridge.

3. EOF Direct-line Telephone

a. This is a direct line to the Emergency Operations Facility (EOF).

Initiate contact by removing the handset from the cradle which will cause the phone in the EOF to ring. When the phone is answered, begin transmission. This link can also be initiated from the EOF.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 35 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4A COMMUNICATIONS GUIDELINES (Page 4 of 5)

B. (continued)

4. Sound-powered Phone

a. As the name implies, these phone (headsets) are powered by sound.

b. The Unit 1 phone jack is located near the Dose Assessment Status Board; the Unit 2 phone jack is located next to the Chronology Status Board in the rear of the room.

c. Once the headsets have been connected in both the affected Control Room and the TSC, transmission can begin by speaking into the mouthpiece.

5. Commercial Telephone

a. This is the first alternate communications pathway to the State Warning Point and St. Lucie, Martin Counties, and NRC.

b. Dial 9 for a Fort Pierce exchange; dial 8-1-Area Code for all other numbers. An authorization code is needed for long distance calls.

6. Emergency Satellite Communications System (ESATCOM)

a. This is a second alternate communications pathway to the State Warning Point and St. Lucie and Martin Counties.

b. To initiate transmission, lift the handset and depress the "push-to-talk" bar in the handset. Wait 3-5 seconds to hear a beep before starting to talk. The red light on the phone is a power indicator, when lit, power is available.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 36 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4A COMMUNICATIONS GUIDELINES (Page 5 of 5)

B. (continued)

7. Local Government Radio (LGR) - Call Sign: Kilo November Golf Romeo 8-7-4 (KNGR874) ~

I

a. This is the third alternate communications pathway to the State Warning Point.

b. A backup communication system to the Counties and indirectly to the State. A table radio, Motorola Command Series, provides two channels, the primary F2 (39.180 MHz, State Channel 1) and the secondary F1 (39.100 MHz, State Channel 2). Channel selection can be made by depressing the "F1/F2" button (the radio is set to monitor F2) The radio can be operated either by depressing the

~

"transmit" button on the console or be removing the handset and depressing the "push-to-talk" bar in the handset. The "xmit" light is lit during transmission. (Preference should be given to using the handset).

8. Very High Frequency Radio (VHF) - Call Sign: St. Lucie Plant

a. Communication link to the FPL Storm Center. May also be used to monitor National Weather Service transmissions. To operate, locate "corbett" (transmission tower) in the alpha display by depressing "home" or use "mode". This Motorola DGT 9000 radio unit can be operated either by depressing the "transmit" button on the console or by removing the handset and depressing the "push-to-talk" bar in the handset. The transmit light is lit during transmission. (Preference should be given to using the handset).

9. Satellite Telephone

a. Instructions for use of the satellite telephone are provided in the phone's briefcase.

b. The phone is stored in a supply cabinet in the TSC.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 37 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT4B SAFETY FUNCTIONS EQUIPMENT STATUS - UNIT 1 (Page 1 of 4)

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 38 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4B RADIOACTIVEGASEOUS SOURCE TERMS - UNIT 1 (Page 2 of 4)

ERDADS RG1 Screen Mimic 10 METER 57.9 METER WIND SPEED MPH MPH WIND DIRECTION DEG DEG AIR TEMP DEG F DEG F DIFF TEMP DEG F/50 METER CHANNEL MAIN STEAM VALUE UNITS CHANNEL CONTAINMENT VALUE UNITS 05-01 A MAIN STM MR/HR 58 A Hl RANGE R/HR 05-02 B MAIN STM MR/HR 59 B Hl RANGE R/HR PRESSURE PSIG CHANNEL ECCS 1A VALUE UNITS CHANNEL PLANT VENT VALUE UNITS 02-05 LOW RANGE uC/cc 01-05 LOW RANGE uC/cc 02-07 MID RANGE uC/cc 01-07 MID RANGE uC/cc 02-09 HI RANGE uC/cc 01-09 Hl RANGE uC/cc 02-10 FLOW SCFM 01-10 FLOW SCFM CHANNEL ECCS 1B VALUE UNITS CHANNEL FUEL BLDG VALUE. UNITS 03-05 LOW RANGE uC/cc 04-05 LOW RANGE uC/cc 03-07 MID RANGE uC/cc 04-07 MID RANGE UC/cc 03-09 Hl RANGE uC/cc 04-09 Hl RANGE uC/cc 03-10 FLOW SCFM 04-10 FLOW SCFM

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PLANT PARAMETERS SAFEGUARDS CONTAINMENT BALANCE OF PLANT Zl O 0 z

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RX VSL PLENUM LEVEL LPSI A ON/OFF 4.16 KV B3 VOLTS LPSI B ON/OFF LEVEL(WR) FEET RCS PRESSURE (NR) PSIA CHRG A ON/OFF ((-1) TO 26) DIESEL GENERATORS 8 (1500-2500) CHRG B ON/OFF O CHRG C ON/OFF TEMPERATURE D/G A VOLTS C RCS PRESSURE (LR) PSIA CCW A ON/OFF zO 0 m (0-750) CCW B ON/OFF ATMOSPHERE DEG F D/G A ~MPS ITl CCW C ON/OFF 33 O

PRESSURIZER LEVEL AFW A AFW B ON/OFF ON/OFF SUMP DEG F D/G B VOLTS Og zp

~MPS O CETTEMPERATURE DEG F AFW C ON/OFF RADIATION LEVEL D/G B (D tD 0 (0 l

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xITI S/G A PRESSURE PSIG B1 B2 HVE 8A ON/OFF CONTAINMENTCOOLERS HVE 6B ON/OFF S/G A LEVEL (WR) SIT'S PRESS PSIA (ON/OFF) HVE 9A ON/OFF At A2 HVE 9B ON/OFF S/G 8 PRESSURE PSIG B1 82 CNTMT COOLER A ON/OFF HVE 10A ON/OFF HVE 10B ON/OFF S/G B LEVEL (WR) SAFEGUARDS SIGNALS CNTMT COOLER B ON/OFF SIAS A YES/NO CNTMT PRESS (WR) PSIG SIAS B YES / NO CNTMT COOLER C ON/OFF MSIS A YES / NO CONTAINMENTTEMP DEG F MSIS B YES / NO CNTMT COOLER D ON/OFF

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 40 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT4B RADIOACTIVEGASEOUS SOURCE TERMS - UNIT 2 (Page 4 of 4)

ERDADS RG2 Screen Mimic 10 METER 57.9 METER WIND SPEED MPH MPH WIND DIRECTION DEG DEG CURRENT TEMP DEG F DEG F DIFF TEMP DEG F CHANNEL MAIN STEAM VALUE UNITS CHANNEL CONTAINMENT VALUE UNITS 631 A MAIN STM MR/HR 40 A Hl RANGE R/HR 632 B MAIN STM MR/HR 41 B Hl RANGE R/HR 633 BACKGROUND MR/HR PRESSURE PSIG CHANNEL ECCS 2A VALUE UNITS CHANNEL PLANT VENT VALUE UNITS 601 LOW RANGE uC/cc 621 LOW RANGE uC/cc 602 MID RANGE uC/cc 622 MID RANGE uC/cc 603 Hl RANGE UC/cc 623 Hl RANGE UC/cc 604 EFFLUENT uC/SEC 624 EFFLUENT uC/SEC CHANNEL ECCS 2B VAI UE UNITS 611 LOW RANGE uC/cc 612 MID RANGE uC/cc 613 HI RANGE uC/cc 614 EFFLUENT uC/SEC

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 41 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT5 TSC ERDADS OPERATOR CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITYOPERATION CAUTION Ensure data is being collected for the affected unit. Each unit has predesignated ERDADS terminals.

1. Check out ERDADS terminals and determine operability status.

If ERDADS is inoperable or printouts are not available, Then assist the Sound-powered Phonetalker in collecting plant parameter and radiological data by completing Attachment 4B, Safety Functions Equipment Status and Radioactive Gaseous Source Terms.

2. Steps to occur continually while the facility is in operation:

a. Call up EPIP screens and additional data as requested, refer

, to Attachment 5A, ERDADS Data Acquisition.

b. Provide the following printouts to the TSC Administrative Staff.

1. Safety Functions Equipment Status (SF 1/2).

2. Radioactive Gaseous Source Terms (RG 1/2).

3. Other screens as requested.

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ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 42 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT5 TSC ERDADS OPERATOR CHECKLIST (Page 2 of 2)

B. (continued) INITIAL

2. (continued)

c. Support dose assessment by providing requested data from ERDADS.

d. Observe ERDADS data during interval between report printing for significant changes and trends, report changes to appropriate members of the TSC staff.

e. Refer to Attachment 58, ERDADS Data Points, for a description of ERDADS data points.

C. FACILITYCLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. ERDADS system returned to preactivation condition.

2. Returned position notebook to storage cabinet.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 43 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT5A ERDADS DATA ACQUISITION (Page 1 of 3)

I. DATA ACQUISITION A. ERDADS - Emergency Response Data Acquisition and Display System, the following information is available on the display screens indicated.

Meteorological Data-Display: SMD (Site Meteorological Data)

2. Plant Parameter Data-CAUTION Certain parameters (e.g., fan status) available on Unit 2 are NOT available on Unit 1.

Display: in the TSC - SF (1/2) (Safety Functions and Equipment Status)

3. Radiological Data-Display: RG (1/2) (Radiation Gaseous Source Terms) RBS (Health Physics Evaluation Screen - containment radiation levels and trends) R11 (Area Radiation Monitors, Unit 1) R21 (Area Radiation Monitors, Unit 2)

4. Chemistry Data-Display: R12 (S/G Blowdown, Steam Jet Air Ejector, Unit 1)

R22 (S/G Blowdown, Steam Jet Air Ejector, Unit 2)

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 44 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT5A ERDADS DATA ACQUISITION (Page 2 of 3)

I. DATA ACQUISITION (continued)

A. (continued)

5. To access data-

a. Press "CLEAR"

b. Type in "Pup Unit (1/2)"

c. Press "EXEC"ute, top of screen will read "Unit change is complete" or "Current Unit is same as entered Unit"

d. Press "EPIP"

e. The "PAGE UP" and "PAGE DOWN" keys will cause the following display sequence:

SMD - RG (1/2) - SF (1/2) - RBS - EF (1/2) - SMD

6. To go directly to a screen-

'. b.

Press "CLEAR" Type in screen designation, e.g., "RG1"

c. Press "DISPLAY" B. Sound-powered Phonetalker - The Sound-powered Phonetalker can be utilized as a primary source of information or as an alternate method to ERDADS.

1. Primary source - status of fans needed for dose assessment: all fans for Unit 1; fans 6, 7, 8, 15, 16 and 17 for Unit 2.

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 45 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT5A ERDADS DATA ACQUISITION (Page 3 of 3)

II ~ ERDADS - COLOR/SYMBOL CONVENTIONS Color/S mbol Ex lanation Numeric value in white on dark green Data value is valid and within the background instrument range.

Numeric value blinking (yellow on blue/ Value may be yellow on blue red on white) background (urgent alarm) or red on white background (critical alarm),

indicates an alarm setting has been exceeded, the alarm must be acknowledged in the Control Room (operators are unable to acknowledge ERDADS alarms in the Simulator Control Room), the value will continue to blink until acknowledged; the value will continue to update.

"BAD" (blue on white) Preceded by a numeric value in white on a blue background signifying a suspect value indicating that one or several inputs to this composite point is/are out of instrument range, when all inputs to the point are out of range the word "BAD" replaces the numeric value.

"FAILED" Point is from a single instrument and the value is out of range.

"NO DATA" Point does not have input to ERDADS, usually point available on one unit, but not the other.

'Based on Table 4.1 in the ERDADS Reactor Operator's Manual (8770-12058)

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 46 of 84 E PIP-04 ST. LUCIE PLANT ATIACHMENT GB ERDADS DATA POINTS (Page 1 of 8)

The following data point descriptions for St. Lucie Plant correspond with the data normally tracked on the plant parameters status board. Consult ERDADS Manual, as necessary, for verification of point IDs, point names or description information.

POINT PT ID POINT, TYPE NOTES DESCRIPTION NAME CALCULATION Avg. RCS T Hot QTA541-1/2 Average This parameter is the average of the A and 'B (HLA and HLB) steam generator inlet temperature. It is also referred (deg. F) to as the average hot leg temperature. The individual

'A'nd 'B'ot leg temperatures are derived by choosing between current narrow and wide range sensor values. The choice depends on the current values, qualities and direction of the rates of change of the instrumentation values, as well as two pairs of overlapping switching limits and the most recent range utilized. The outputs from the calculation consist of the choice of range, the associated value and rate of change together with the quality of each.

RCS Pressure QA0501-1/2 RCS Average This parameter is a Reactor Coolant System (RCS)

WR (psia) Pressure wide range instrument. It derived from Pressurizer Pressure signals PT1107-2 and PT1108-2 which are linear. These signals are processed by an average with expanded quality algorithm. This function obtains the average of all values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are:

~ Greater than 50% of inputs have good status, result Is good.

~ Only one good value and the total inputs are 3 or more, the result is poor.

~ When there are no good data values, but there are some with poor or suspect, the result is poor.

~ The result is suspect for all other cases except all bad, in this case the result is bad.

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ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 47 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 2 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION RCS QA0001-1/2 PRZR LVL Average This parameter is pressurizer level. It is derived from Pressurizer Pressurizer Level control signals LT1110X-2 and Level (%) LT1110Y-2 which are linear. These two signals are processed by an average with expanded quality algorithm. This function obtains the average of all values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are:

~ Greater than 50% of all inputs have good status, result is good.

~ Only one good value and the total inputs are 3 or more, the result is poor.

~ When there are no good data values, but there are some with poor or suspect, the result is poor.

~ The result is suspect for all other cases except all bad, in this case the result is bad.

The top of the heaters is 73.98 inches above the lower top centerline.

Charging Flow FT2212-1/2 RCS This parameter is reactor coolant system makeup to Regen Hx CHG/MU flow. It is converted to engineering units using a (GPM) linear equation.

Subcooling QA0005-1/2 Submargin Minimal This parameter is derived from eight subcooled Margin (deg. F) values, TMARHEAD-A-1/2,TMARRCS.B-1/2, TMARUR-A-1/2,TMARHEAD-B-1/2,TMARCET-A-1/2 TMARUR-B-1/2, TMARRCS-A-1/2 and TMARCET-B-1/2, which are provided by the Qualified Safety Parameter Display System (QSPDS). They are processed by a signal auctloneering minimum algorithm. This function finds the highest usable data va!ue in a specified group. Each data value of the group and its quality is examined and the following quantities are obtained:

1. Lowest usable data value,

2. Point number of the lowest usable data value,

3. Number of usable data values, and

4. Lowest quality of the usable data.

~ For two or more usable data values, the result is the highest usable value and the quality Is the lowest quality of the usable data.

~ For only one usable data value, the result is set to that value and the quality is poor.

~ For no usable data, the value of the result is set to the highest of all the (bad) data and the quality is bad.

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ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 48 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 3 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION Avg. Core Exit QA0003-1/2 Temp. Average This parameter is derived from 45 Unit 1 detectors, Temperature Core Ex. or 56 Unit 2 detectors located just above the upper (deg. F) fuel alignment plate. The Qualified Safety Parameter Display System (QSPDS) provides the values. They are processed by an average with expanded quality algorithm. This function obtains the average of all values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are:

~ Greater than 50% of all inputs have good status, result is good.

~ Only one good value and the total inputs are 3 or more, the result is poor.

~ When there are no good data values, but there are some with poor or suspect, the result is poor.

~ The result is suspect for all other cases except all bad, in this case the result is bad.

Reactor Vessel Unit 1: Minimum The reactor vessel level for Unit 1 QA0004-1 is Level (%) QA0004-1 derived from the reactor vessel levels RLEV-A-1 and RLEV-B-1 which aie provided by the Qualified Safety Unit 2: Parameter Display System. The ERDADS select the RLEV H-2 lowest of the two values. For only one good data RLEV P-2 value, the result is set to that value and the quality is poor.

The reactor vessel level for Unit 2 is displayed as reactor plenum level RLEVPB-2 and reactor head level RLEVHB-2 which is provided by the 'B'ide Qualified Safety Parameter Display System (QSPDS). These two parameters are displayed with no calculations being performed by the ERDADS internals. system.

computer The QSPDS obtains these values from the heated and unheated junction thermocouples located Inside the reactor. They are positioned between the head and upper fuel alignment plate in the reactor

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 49 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 4 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION Reactor Vessel Unit 1 Level Information: Head and Plenum together Level %

(continued) Locationn.

to fuel) Level Value if Sensor ~ali nment tate ~Se ment % ~Uncovered %

None 100 1 186 1/4 20 80 2 144 3/8 19 61 3 108 18 43 4 71 5/8 14 29 5 50 5/8 10 19 6 29 5/8 7 12 7 19 5/8 5 7 8 10 5/8 7 0 Unit 2 Level Information: Head and Plenum together Location

('n. to fuel) Level Value if Sensor ~ali nment tate ~Se ment % ~Uncovered %

None 100 1 170 1/2 52 48 2 140 3/4 28 20 3 111 1/8 20 0 None 100 4 98 5/8 18 82 5 74 5/8 21 61 6 53 5/8 20 41 7 32 5/8 19 22 8 12 5/8 22 0

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 50 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 5 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION HPSI Total HSI ITLF-1/2 HPSI Flow Sum This parameter measures total HPSI flow and is Flow (GPM) derived from HPSI Header Flow signals FT3311-1/2, FT3321-1/2, FT3331-1/2 and FT3341-1/2 which are square roots. 'The signals are processed with a sum of inputs algorithm. This function obtains the algebraic sum of values with a good status.

LPSI Total QA0 908-1/2 LPSi Flow Sum This parameter measures total LPSI flow and is Flow (GPM) derived from LPSI Header Flow signals FT3312-1/2, FT3322-1/2, FT3332-1/2 and FT3342-1/2 which are square roots. These signals are processed by an algorithm which provides a sum of the inputs. 'This function obtains the algebraic sum of values with a good status.

Containment TE07-3B-1/2 Cntmnt This parameter is a containment temperature Temp. (deg. F) Temp instrument. It is converted to engineering units using a linear equation.

Containment QA0507-1/2 Cntmnt Average This parameter measures containment pressure and Pressure WR Press is a wide range indicator. It is derived from Wide (psig) Range Containment Pressure signals PT07-4A1-1/2 and PT07<Bt-1/2 which are linear. They are processed by an average with expanded quality algorithm. This function obtains the average of afl values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are:

~ Greater than 50% of all inputs have good status, result is good.

~ Only one good value and the total inputs are 3 or more, the result is poor.

~ When there are no good data values, but there are some with poor or suspect, the result is poor.

~ The result is suspect for all other cases except all bad, in this case the result is bad.

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICALSUPPORT CENTER 51 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 6 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION Containment QA0008-1/2 Cntmnt Maximum This parameter is a containment sump wide range Sump Level Smp WR instrument. It is derived from Containment Sump WR (Ft.) Level signals LT07-13-A-1/2 and L007-13B-1/2 which are linear. They are processed by a signal auctioneering maximum algorithm. This function finds the highest usable data value in the specified group. Each data value of the group and its quality is examined and the following rules are used.

~ For two or more usable data values, the result is the highest usable data value and the quality is the lowest quality of the usable data.

~ For only one usable data value, the result is set to that value and the quality h poor.

~ For no usable data, the value of the result is set to the highest of all the (bad) data and the quality is bad.

Containment CH2-1/2 H2 Conc. Average This parameter is a containment hydrogen average Hydrogen (%) concentration measurement. It is derived from Hydrogen Concentration signals A-HYDROGEN-1/2 and B-HYDROGEN-1/2 which are linear. These signals are processed by an average with expanded quality algorithm. This function obtains the average of all values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs.

The possible status values are:

~ Greater than 50% of all Inputs have good status, result is good.

~ Only one good value and the total inputs are 3 or more, the result is poor.

SG Level A LT9012-1/2 SG Level This parameter is the "A steam generator wide WR (%) A range level instrument. It is converted to engineering units using a linear equation. LTCL =

Lower Tap Center une. The lower tap is 19.5 inches above the bottom of the U tubes.

SG Level B LT9022-1/2 SG Level This parameter is the 'B'team generator wide WR (%) B range level Instrument. It is converted to engineering units using a linear equation. LTCL =

Lower Tap Center Line. The lower tap is 19.5 inches above the bottom of the U tubes.

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 52 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 7 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION SG Pressure A QA0021-1/2 SG Pres JA Redundant Sensor This parameter is the A'team generator pressure.

(pslg) Algorithm It is derived from three Steam Generator Pressure Signals, PT8013A-1/2, PT8013B-1/2 and PT8013C-1/2, which are linear. These signals are processed by a redundant sensor algorithm. This function obtains the average of the current values that have a good status and are close to the statistical majority.

SG Pressure B QA0022-1/2 SG Pres JB Redundant Sensor This parameter is the 'B steam generator pressure.

(psig) Algorthim It is derived from three Steam Generator Pressure Signals, PT8023A-1/2, PT8023B-1/2 and PT8023D-1/2, which are linear. These signals are processed by a redundant sensor algorithm. This function obtains the average of the current values that have a good status and are dose to the statistical majority.

Refueling RWTAL-1/2 BWST Average This parameter measures refueling water tank level.

Water Tank Level It is derived from three inputs. They are Avg. Level (Ft.) LT07-2A-1/2, LT07-2B-1/2 and LT07-2C-1/2. These points are processed by an average with expanded quality algorithm. This function obtains the average of all values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs.

The possible status values are:

~ Greater than 50% of all inputs have good status, result is good.

~ Only one good value and the total inputs are 3 or more, the result is poor.

~ When there are no good data values, but there are some with poor or suspect, the result is poor.

~ The result is suspect for all other cases except all bad, in this case the result is bad.

Tank bottom refers to zero gallons.

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 53 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT5B ERDADS DATA POINTS (Page 8 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION CHRRM. Unit 1: Cntmnt. Maximum The high containment radiation instruments for Channel Rad Unit 1 are the A side monitor RE 26-58-1 and the (R/HR) RE 26-58-1 'B'ide monitor RE 26-59-1. These monitors are (A Channel) only range checked and flagged bad if out of range.

Both detectors are located at the 90 foot RD 26-59-1 containment elevation and are positioned at 0 and B Channel) 180 degrees.

Unit 2: The high containment radiation instruments for Unit 2 are the A'ide monitor RIM 26-40-2 and the RIM 26-40-2 'B'ide monitor RIM 26-41-2. These monitors are (A Channel) only range checked and are flagged bad if out of range. Both detectors are located at the 90 foot RIM 26-41-1 containment elevation and are positioned at 0 and (B Channel) 180 degrees.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 54 of 84 E PIP-04 ST. LUCIE PLANT A lTACHMENT6 TSC ADMINISTRATIVESTAFF CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

2. Using Controlled Copy 5, post all EPIP revision numbers on the status board.

3. Telecopy the EC Log, completed notification forms and checklists, and any other pertinent information to the EOF.

B. FACILITYOPERATION NOTE Information should be updated every 15-30 minutes and not longer than 60 minutes.

1. Synchronize the facility clock(s) with ERDADS. In case of ERDADS failure, synchronize with the affected Control Room.

2. Steps to occur continually while the facility is in operation:

a. Obtain the following ERDADS data sheets (printouts) from the ERDADS Operator:

1. Safety Functions Equipment Status (SF 1/2) ~

2. Radioactive Gaseous Source Terms (RG 1/2).

b. Update status boards with new ERDADS data.

c. Verify all data has been accurately transferred to the status board.

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 55 of 84 E PIP-04 ST. LUCIE PLANT ATIACHMENT 6 TSC ADMINISTRATIVESTAFF CHECKLIST (Page 2 of 3)

B. (continued) INITIAL

2. (continued)

d. Update the sequence of events board following each facility briefing and as needed. Provide relevant information concerning items such as:

1. Change in classification.

2. Significant change in plant condition.

3. Status of plant system(s) of concern.

4. Injured personnel status.

5. Other items of relevant interest.

~

e. Update dose assessment and field monitoring data as information is provided by Chemistry and HP, respectively.

f. Make corrections, when identified, by circling the corrected data.

g. When all status board columns/blanks are filled, erase the first two columns/blanks, enter new data with a different colored marker leaving a space between the new and the old data.

h. Provide any incoming telecopy materials to the TSC Supervisor or as designated on the cover page.

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4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 56 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT6 TSC ADMINISTRATIVESTAFF CHECKLIST (Page 3 of 3)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Status boards have been cleaned and returned to preactivation condition.

2. Provided all completed paperwork to the TSC Supervisor.

3. Returned position notebook to storage cabinet.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER . 57of84 EPIP-04 ST. LUCIE PLANT ATI ACHMENT 7 TSC COORDINATOR WITH OSC CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

/R4 A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITYOPERATION

1. Establish contact with the OSC Coordinator with the TSC (in the OSC).

2. Steps to occur continually while the facility is in operation:

a, Ensure all requests for re-entry activities are documented on Attachment 7A, Re-entry/SAMG Worksheet.

b. Ensure all re-entry requests have been approved and prioritized by the EC.

c. Track all requests for Re-entry Teams using Attachment 7B, Re-entry Log.

d. Communicate re-entry requests,to the OSC Coordinator with the TSC per Attachment 7B, Re-entry Log.

e. Update the OSC Status Board with Re-entry Team information.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 58 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT7 TSC COORDINATOR WITH OSC CHECKLIST (Page 2 of 2)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Closed out all Re-entry Teams entered in the Re-entry Team Log and the status board.

2. Status board has been cleaned and returned to preactivation condition.

3. All paperwork completed and provided to the TSC Supervisor.

4. Returned position notebook to storage cabinet.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 59 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT7A RE-ENTRY WORKSHEET (Page 1 of 5)

NOTE This worksheet is used for the following:

~ Requesting Re-entry Team dispatch from the Operational Support Center (OSC).

~ Requesting Engineering Support from the Emergency Operations Facility (EOF).

~ Providing SAMG directives to the Control Room(s) (CR(s)).

1 ~ Describe the nature of the request in Section 1.

2. The PST Leader should determine if the request is complex such that it needs the PST for review and development.

A. If the PST does NOT need to review the request, Then COMPLETE only Section 1 and Section 5.

B. If PST does need to review the request, Then COMPLETE all sections.

Section 1 DESCRIBE the Prob! em/Concern/Request:

(ATTACH ADDITIONALPAGES IF REQUIRED)

Originated by:

Section 2

1. PST Leader ASSIGN a PST team member to fill out the following Assessment/Review:

(ATTACH ADDITIONALPAGES IF REQUIRED)

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 60 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT7A RE-ENTRY WORKSHEET (Page 2 of 5)

INITIAL Section 2 (continued)

2. If the PST shall develop the recommendation/response, Then FILL IN the Recommendation/Response (ATTACH ADDITIONALPAGES IF REQUIRED)

Section 3 If EOF assistance is determined to be required, Then the PST Leader shall perform the following:

1. SEND the Attachment 7A to the EOF (verbal and/or fax)

2. RETURN the EOF recommendation/response to the PST for review and appropriate action.

3. REVIEW and APPROVE PST recommendation/response.

4. Signature Date/Time:

Section 4 lf the actions are SAMG related, Then the PST Leader shall ASSIGN a SAMG tracking number and POST the task on the PST SAMG White board.

SAMG Sequence number: SAMG-PST

0 REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE TECHNICALSUPPORT CENTER 61 of 84 PROCEDURE NO.:

EPIP-04 ST. LUCIE PLANT ATTACHMENT7A RE-ENTRY WORKSHEET (Page 3 of 5)

INITIAL Section 5 The following instructions are required for Emergency Coordinator task approval:

NOTE 50.59 Screening is required for any alterations of systems, structures or components.

Actions that are outside of design basis shall require implementation of ADM-17.06, Invoking 10 CFR 50.54(x) and (y).

1. If requested tasks are NOT routine or covered by existing plant procedures, Then PERFORM 50.59 Screening on the tasks and any attached instructions in accordance with ADM-17.11.

PST

2. The Emergency Coordinator shall consider the following questions in the review for task approval (EC initials required):

A. Do these actions affect the margin of nuclear safety of the unaffected unit that has NOT been addressed?

B. Are the instructions clear and easy to understand?

C. Are all referenced components and systems properly identified and labeled?

D. Have appropriate Engineering reviews been performed to avoid unintentional operation of systems outside design characteristics?

E. Do steps, that have operating parameters specified, contain

'perating bands?

NOTE CONSULT the TSC Ops Coordinator for 10 CFR 50.54(x) SRO evaluation.

During Severe Accident events, where 10 CFR 50.54(x) has been invoked at the entry of the SAMGs, alterations affecting the non-affected unit's hardware, structures, systems or components, outside of design basis, shall require separate ADM-17.06 invocations.

F. If implementation of 10 CFR 50.54(x) is required, Then IMPLEMENT ADM-17.06, Invoking 10 CFR 50.54(x) and (y).

REVISION NO PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICALSUPPORT CENTER 62 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT7A RE-ENTRY WORKSHEET (Page 4 of 5)

INITIAL Section 5 (continued)

2. (continued)

G. Approval:

~ Approved as written.

~ Approved with the following corrections:

CAUTION Priorities are set based on the urgency of the task and by considering resources available (NOT everything is or can be priority 0).

0 = Dispatch Team in less than 5 minutes (fire, injury or certain operator actions) 1 = Dispatch Team in less than 15 minutes (Emergency Coordinator top priority) 2 = Dispatch Team in less than 30 minutes (routine re-entries)

~ Priority Signature Date/Time:

Emergency Coordinator

3. FORWARD the Attachment 7A to the applicable communicator:

A. If the task is specifically for the OSC, Then the TSC Coordinator with OSC shall PERFORM the following:

1. ASSIGN a task description:

2. COMPLETE Re-entry Log entry

3. COMMUNICATE the task to the OSC Time call complete

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 63 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT7A RE-ENTRY WORKSHEET (Page 5 of 5)

INITIAL Section 5 (continued)

3. (continued)

B. If the task is specifically for Operations, Then the TSC Ops Coordinator shall PERFORM the following:

1. COMMUNICATE the task instructions to the required Control Room(s).

B. Priority C. Time I. Re-entry Supv.:

D. Reason for request: J. Time out: K. Time in:

L. Comments:

E. Info contact:

F. Phone:

'0 = Dispatch in less than 5 minutes (e.g., fire, injury, or certain Operator Actions) 1 = Dispatch in less than 15 minutes (e.g., Emergency Coordinator top priority) 2 = Dispatch in less than 30 minutes (e.g., routine re-entries)

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 65 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT8 TSC OPS COORDINATOR CHECKLIST (Page 1 of 3)

NOTE

1. This position is filled by two persons, one located in the affected Control Room, the other in the TSC. The position in the Control Room is also known as the NPS Communicator.

2. When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL NOTE The first person to arrive at the TSC should report to the affected Control Room to relieve the Duty Call Supervisor.

1. Filling position in:

2. (TSC position only) Refer to Section 5 of this procedure (included in the'position notebook) and review the general instructions.

B. FACILITYOPERATION Establish communications with counterpart.

2. Initiate the OPS Logbook. (TSC only)

3. Steps to occur continually while the facility is in operation:

TSC

a. Provide expertise in plant operations to the EC.

b. Maintain communication flow between the TSC and the affected Control Room concerning status of operations.

c. Maintain OPS Logbook.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 66 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT8 TSC OPS COORDINATOR CHECKLIST (Page 2 of 3)

B. (continued) INITIAL

3. (continued)

d. Severe Accident Management Guidelines (SAMG) actions

1. Perform evaluations in accordance with ADM-17.09, Invoking 10 CFR 50.54(x), as needed.

2. Review/approve actions as outlines in Attachment 7A, Re-entry/SAMG Worksheet.

3. Communicate SAMG actions to the affected Control Room(s).

Control Room

a. Provide communications assistance to the NPS.

b. Monitor procedure use and keep the TSC informed.

c. Investigate questions/concerns as requested by the TSC.

d. Update the unaffected unit's Control Room with emergency status.

e. Gather Severe Accident Management Guidelines (SAMG) instructions/information from the TSC OPS Coordinator.

1. If the TSC is unable to telecopy, Then use Attachment 7A, Re-entIy/SAMG Worksheet to record SAMG instructions/

information.

f. Communicate SAMG actions to the NPS.

g. Provide feedback to the TSC OPS Coordinator regarding SAMG actions.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 67 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT8 TSC OPS COORDINATOR CHECKLIST (Page 3 of 3)

INITIAL C. FACILITYCLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Phone connection terminated.

2. Closed out the OPS Logbook.

3. Returned position notebook to storage cabinet.

4. Provided all completed paperwork to the TSC Supervisor.

0 REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 68 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT9 TSC REACTOR ENGINEER CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps in this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITYOPERATION

1. In coordination with the Shift Technical Advisor (STA), establish the ERDADS link with the NRC Emergency Response Data System (ERDS) (use Attachment 9A, Initiating and Terminating the ERDS Link).

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 69 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT9 TSC REACTOR ENGINEER CHECKLIST (Page 2 of 3)

B. (continued) INITIAL

2. Steps to occur continually while the facility is in operation:

CAUTION Be aware of the following conditions. These initiating conditions are associated with Emergency Actions Levels (EALs) used in the classification of emergencies (EPIP-01, Classification of Emergencies).

The Emergency Coordinator needs to know if any of these conditions exist.

1. Dose Equivalent Iodine (DEQ) I-131 activity greater than 275 pCI/ml.

2. CHHRM readings greater than 7.3E+03 R/hr OR greater than 1.46E+05 R/hr.

3. Post LOCA Monitor readings greater than 100 mR/hr OR greater than 1000 mR/hr.

4. Step increase in radiation monitor readings in the Plant Vent and/or Fuel Handling Building.

5. Loss of subcool margin resulting in saturated conditions.

6. Highest Core Exit Therrnocouple (CET) per core quadrant indicates greater than 10'F superheat or 700'F.

7. Damage to more than one irradiated fuel assembly.

8. Uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.

a. Monitor critical plant parameters for indications of core status.

b. Assist Nuclear Fuels personnel in the EOF in the assessment of core damage in accordance with EPIP-11, Core Damage Assessment.

c. Assist the STA with core monitoring functions and STA support functions.

d. Assist in Severe Accident Management Guidelines (SAMG) activities as a SAMG Evaluator.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 70 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT9 TSC REACTOR ENGINEER CHECKLIST (Page 3 of 3)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook Core damage assessment activities terminated.

2. Returned position notebook to storage cabinet.

3. All completed paperwork provided to the TSC Supervisor.

REVISION No.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 71 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT9A INITIATINGAND TERMINATING THE ERDS LINK (Page 1 of 2)

This attachment provides the instructions for initiating and terminating the communications link between the St. Lucie Emergency Response Data Acquisition and Display System (ERDADS) and the NRC Emergency Response Data System (ERDS). This communications link must be activated not later than one hour after declaring an emergency class of ALERT or higher. If communications cannot be established then the accepted method of data transmission to the NRC will be through the Emergency Notification System (ENS).

INITIATINGthe ERDS communication link:

1. At any TSC ERDADS terminal clear the display screen by depressing the CLEAR key.

2. Log on to ERDADS by typing in PSW ¹¹ XXXXXXXX(the Xs stand for the password issued to Operations Support Engineering). Then depress the EXEC key.

3. Clear the screen with the CLEAR key and select the desired St. Lucie Unit by typing PUP UNIT X (the X will be either a 1 or 2 depending on the unit). Then depress the EXEC key.

4, Clear the screen by depressing the CLEAR key and type in ERD and depress the DSPLY key. This will display the ERDS link control picture on the terminal ~

5. Depress the TAB + keys to place the cursor on the INITIATE action bar and then depress the ENTER key. The depressing of the ENTER key will initiate the communications link to the NRC ERDS.

6. After the communication link with the NRC ERDS has been established clear the terminal screen by depressing the CLEAR key and log off by typing in PSW 0 and depressing the EXEC key. The logging off of the terminal's screen will allow that terminal to be used in obtaining information for TSC activities without affecting the communication link with the NRC ERDS.

7. Periodically check the status of the ERDS link by typing in HLX (the X will be a 2 for Unit 1 or 3 for Unit 2) and depress the DSPLY key.

REVISION No.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 72 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT9A INITIATINGAND TERMINATING THE ERDS LINK (Page 2 of 2)

NOTE

~ If the blinking message NOTIFY THE NRC appears after the CURRENT STATUS then the communications link has been lost and a reconnection is necessary when the NRC requests it through the established voice connection in the TSC. If this happens then it will be necessary to reinitiate the communications link beginning with step 1 ~

~ Generally the ERDS link will be terminated by the NRC. The following steps are to be used if the link needs to be terminated from the TSC.

TERMINATING the ERDS communication link:

1. At any TSC ERDADS terminal clear the display screen by depressing the CLEAR key.

2. Log on to ERDADS by typing in PSW ¹¹ XXXXXXXX(the Xs stand for the password issued to Operations Support Engineering). Then depress the EXEC key.

3. Clear the screen with the CLEAR key and select the desired St. Lucie Unit by typing PUP UNIT X (the X will be either a 1 or 2 depending on the unit). Then depress the EXEC key.

4. Clear the screen by depressing the CLEAR key and type in ERD and depress the DSPLY key. This will display the ERDS link control picture on the terminal.

5. Depress the TAB - keys to place the cursor on the TERMINATE action bar and then depress the ENTER key. The depressing of the ENTER key will terminate the communications link to the NRC ERDS.

6. After the communication link with the NRC ERDS has been terminated clear the terminal screen by depressing the CLEAR key and log off by typing in PSW 0 and depressing the EXEC key.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 73 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT10 TSC CHEMISTRY SUPERVISOR CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps in this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Initiate the Chemistry Logbook.

2. Steps to occur continually while the facility is in operation:

NOTE Dose assessment shall be a primary responsibility of the EOF once it becomes operational.

a. Supervise dose assessment activities.

b. Review all dose projection printouts.

c. Advise the EC of dose projection results.

d. Assist the EC in evaluating off-site dose estimates for PARs.

e. Provide technical support to the OSC Supervisor.

REVISION No.: . PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 74 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT10 TSC CHEMISTRY SUPERVISOR CHECKLIST (Page 2 of 3)

B. (continued)

CAUTION Be aware of the following conditions. These initiating conditions are associated with Emergency Action Levels (EALs) used in the classification of emergencies (EPIP-01, Classification of Emergencies). The Emergency Coordinator needs to know if any of these conditions exist.

1. Dose Equivalent Iodine (DEQ) I-131 activity greater than 275 pCI/ml.

2. Result of analysis of a gaseous or liquid release is greater than ten (10) times the ODCM limit.

3. CHHRM readings greater than 7.3E+03 R/hr OR greater than 1.46E+05 R/hr.

4. Post LOCA Monitor readings greater than 100 mR/hr OR greater than 1000 mR/hr.

5. Step increase in radiation monitor readings in the Plant Vent and/or Fuel Handling Building.

6. Off-site dose calculation worksheet values at one (1) mile in excess of 50 mrem/hr (total dose - TEDE) or 250 mrem/hr (thyroid dose - CDE) for one half (1/2) hour OR 500 mrem/hr (total dose - TEDE) or 2500 mrem/hr (thyroid dose - CDE) for two (2) minutes.

7. Off-site dose calculation worksheet values indicate site boundary (one (1) mile) exposure levels have been exceeded as indicated by any of the following:

a. 1000 mrem/hr (total dose rate)

b. 1000 mrem (total dose - TEDE)

c. 5000 mrem/hr (thyroid dose rate)

d. 5000 mrem (thyroid dose - CDE)

f. Advise the EC on plant chemistry related matters.

g. Maintain chronological log of activities.

h. Review and verify radiological and protective action information entered on status boards.

REVISION NO.: PROCEDURE TITLE: PAGE:

ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 75 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT I 0 TSC CHEMISTRY SUPERVISOR CHECKLIST (Page 3 of 3)

C. FACILITYCLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Dose assessment activities terminated.

2. Closed out the Chemistry Logbook.

3. Returned position notebook to storage cabinet.

4. All paperwork provided to the TSC Supervisor.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 76 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT11 TSC DOSE ASSESSOR CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps in this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITYOPERATION NOTE Initial operating instructions for use of the Class A Model are provided in EPIP-09, Off-site Dose Calculations.

2. If the computerized Class A Model is not available, dose projections shall be performed in accordance with EPIP-09.

1. Ensure all previous dose calculation paperwork is sent to the EOF.

2. Establish communication link with the EOF Dose Assessor.

3, Complete Class A Model QC Check.

4. Steps to occur continually while the facility is in operation:

a. Obtain input data for the Class A Model from the ERDADS Operator (RG 1/2 Screen).

b. Report dose projection results to the TSC Chemistry Supervisor.

c. Coordinate dose assessment with the EOF.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 77 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT11 TSC DOSE ASSESSOR CHECKLIST (Page 2 of 2)

B. (continued) INITIAL

4. (continued)

d. Provide status board update information to the TSC Administrative Staff (use Attachment 11A and Attachment 11B) ~

1. Using carbon paper make a copy as data is entered into the form in either Attachment 11A or 11B. Retain the original, provide the copy to the TSC Administrative Staff to update the status boards.

C. FACILITYCLOSEOUT AND RESTORATION NOTE Att paperwork completed in the position notebook should remain in the position notebook.

1. Dose projection activities terminated.

2. EOF communications linked terminated.

3. All documents, equipment and supplies returned to preactivation condition and/or location.

4. All paperwork collected.

5. Returned position notebook to storage cabinet.

6. Provided all completed paperwork to the TSC Chemistry Supervisor.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 78 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT11A OFF-SITE RADIOLOGICALASSESSMENT (Page 1 of 1)

OFFSITE DOSE RADIOLOGICALASSESSMENT STATUS AND TRENDS PARAMETER Unit Highest Downwind Sector Dose Rates Day ¹ of Month Time of Day 2400 Downwind Sectors Dose Rate e TEDE CDE TEDE CDE TEDE CDE TEDE CDE 1 mile mRem/hr 2 miles mRem/hr 5 miles , mRem/hr 10 miles mRem/hr Wind Direction at Degrees 10 meter elev Downwind Sector Wind Speed at mph 10 meter elev 60 meter - 10 meter Deg F delta T Stability Class 10 meter Temperature Deg F Noble Gas Rel Rate Ci/sec Iodine Rel Rate Ci/sec Noble Gas Total Ci Ci Iodine Total Ci Ci Contain Hi Range Vent Ci/sec ECCS A Ci/sec ECCS B Ci/sec Main Steam A mR/hr Main Steam B mR/hr TEDE = Total Dose CDE = Thyroid Dose

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 79 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT11 B PROTECTIVE ACTION RECOMMENDATIONS (Page 1 of 1)

PROTECTIVE ACTION RECOMMENDATIONS REASON:

ISSUED BY: DATE/TIME:

S = SHELTER E = EVACUATE SECTOR 0- 2 Miles 2- 5 Miles 5- 10 Miles A (N )

(NNE)

(NE )

(ENE)

(E )

(ESE)

(SE )

(SSE)

(S )

(SSW)

(SW )

(WSW)

(W )

(WNW)

Q (NW )

(NNW)

ADDITIONALCOMMENTS:

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE No.: TECHNICAL SUPPORT CENTER 80 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT12 TSC PROBLEM SOLVING TEAM CHECKLIST (Page 1 of 2)

NOTE

1. This checklist applies to the following Problem Solving Team (PST) positions:

TSC PST Leader Engineering TSC Elec Rep - PST TSC l&C Rep - PST TSC Mech Rep PST (3) TSC SRO Rep - PST

2. When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITYOPERATION NOTE

1. Refer to the Document Control Index for a listing of Tech Manuals available in the TSC.

2. The computer provides a LAN connection and access to the Total Equipment Database (TEDB).

1. Steps to occur continually while the facility is in operation:

a. Problem Solving Team Leader

1. Maintain command and control of all PST activities.

2. Ensure all PST members are aware of and understand the status of equipment.

3. Maintain high level of inquiry and investigation by all PST members.

4. Tack progress of all Re-entry/SAMG Worksheets (Attachment 7A) given to or initiated by the PST.

REVISION No.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICALSUPPORT CENTER 81 of 84 EPIP-04 ST. LUCIE PLANT ATTACHMENT12 TSC PROBLEM SOLVING TEAM CHECKLIST (Page 2 of 2)

B. FACILITYOPERATION (continued) INITIAL

1. (continued)

a. (continued)

5. Encourage development of multiple success paths.

6. Review all Re-entry/SAMG Worksheets (Attachment 7A).

b. Problem Solving Team Member

1. Participate as a member of the Problem Solving Team by providing technical support in your area of expertise.

2. Evaluate system and equipment failures.

3. Propose mitigative and corrective action(s) as promptly as possible.

4. Document recommendations on a form similar to Attachment 7A, Re-entry/SAMG Worksheet.

5. Serve as a Severe Accident Management Guidelines (SAMG) Evaluator.

6. Provide all recommendations to the EC.

C. FACILITYCLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Returned all documents, equipment and supplies to preactivation condition and/or location.

2. Returned position notebook to storage cabinet.

3. Provided all completed paperwork to the TSC Supervisor.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 82 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT13 TSC SECURITY SUPERVISOR CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL NOTE This position is normally filled by the on-shift Security Shift Specialist.

Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

2. Verify that the Energy Encounter has been notified of the emergency. (consult the ERD for the phone number)

B. FACILITYOPERATION

1. Establish access control for the TSC.

2. Contact the Control Rooms and request a ~corn ieted "Operations Department Accountability Aid" be forwarded to the TSC.

3. initiate facility accountability by requesting a ~corn ieted copy of Attachment 3A, TSC ERO Shift Staffing and Accountability Roster from the TSC Supervisor.

4. Telecopy the completed Attachment 3A, TSC ERO Shift Staffing and Accountability Roster, and the "Operations Department Accountability Aid" forms to Security.

5. Contact the EOF Emergency Security Manager (ESM).

a. Establish responsibility/protocol for notification of off-site authorities regarding the status of site evacuation.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER 83 of 84 E PIP-04 ST. LUCIE PLANT ATTACHMENT13 TSC SECURITY SUPERVISOR CHECKLIST (Page 2 of 3)

A. (continue) INITIAL

6. Upon declaration of a Site Area Emergency.

a. Start accountability at:

b. Start sweeps at:

1. Off-site work areas.

2. West forty and Fitness Center.

3. Owner Controlled Area.

a. Beach side.

b. River side.

4. On-site and Radiation Controlled Area.

5. Marine Research Center.

c. Accountability completed at

d. Sweeps completed at 7.. Steps to occur continually while the facility is in operation:

CAUTION Ensure the EC is aware of any actions required by the Security Plan (e.g., alert or emergency declaration, suspension of safeguards, etc.) ~

a. Advise the EC on Security related manners.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 ACTIVATIONAND OPERATION OF THE PROCEDURE NO.: TECHNICALSUPPORT CENTER 84 of 84, E PIP-04 ST. LUCIE PLANT ATTACHMENT13 TSC SECURITY SUPERVISOR CHECKLIST (Page 3 of 3)

A. (continue) INITIAL

7. (continued)

b. In conjunction with the ESM, provide liaison function between local law enforcement and rescue agencies and FPL for issues such as:

1. Bomb threats or acts of terrorism.

2. Member of the public or media arriving at the site.

3. Site egress and ingress.

4. Fire or rescue/medical response.

c. Coordinate safeguards suspension with the ESM and EC.

d. Maintain site accountability of all personnel throughout the emergency.

e. Follow Security Procedures.

C. FACILITYCLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Closed out with the local law enforcement agencies, as needed.

2. Closed out Security Logbook.

3. All paperwork collected.

4. Returned position notebook to the storage cabinet.

5. Provided all completed paperwork to the TSC Supervisor.

S OPS DATE DOCT PROCEDURE FLORIDA POWER & LIGHT DOCH EPIP-07 PSL SYS COMP COMPLETED ST. LUCIE PLANT O O

ITM 1 O

K O

O PnOCEDURq PqODU PREVIOUSLY ISSUED AS 3100026E EPIP-07 REVISION 1 CONDUCT OF EVACUATIONS/ASSEMBLY EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISION REVIEWED BY APPROVED BY DATE FRG ON 12/1 5/97 J. Scarola 12/15/97 Plant General Manager 12/02/98 R. G. West 12/02/98 Plant General Manager ResPonsible SERVICES Department:

~

REVISION No.: PROCEDURE TITLE: PAGE:

1 PROCEDURE NO.: CONDUCT OF EVACUATIONS/ASSEMBLY 2 of 13 EPIP-07 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ~ ~ ~ ~ ~ ~ ~ 3

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS........... ~.................... ~ ~ ~ ~ ~ ~ ~ 3 3.0 RESPONSIBILITIES ~ ~ ~ 4 3.1 Nuclear Plant Supervisor 4 3.2 Emergency Coordinator ~................... 4 3.3 Security Shift Specialist 4

~.................

~ ~ ~

3.4 Escorts/Tour Guides . ~... ~ ~ ~ ... 5 3.5 Site Assembly Area Supervisor............... 5 3.6 Non-Emergency Response Organization Personnel ~ ~ ~ 5 4.0 DEFINITIONS ...... ~..... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 5.0 INSTRUCTIONS . ~ ~ .. ~.... ~ ~ . ~ ~ ~.............. ~ ~ o 8 ATTACHMENT ATTACHMENT 1 Criteria for Evacuation ........... ~ ~ ~.... ~....

~ 10 ATTACHMENT2 Assembly Area Supervisor Checklist.............. 11 ATTACHMENT2A Off-site Assembly Area Roster ....... 13

REVISION NO.: PROCEDURE TITLE: PAGE:

1 PROCEDURE NO.: CONDUCT OF EVACUATIONS/ASSEMBLY 3 of 13 EPIP-07 ST. LUCIE PLANT THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN, PLEASE READ ENTIRE PROCEDURE BEFORE PROCEEDING. /R1 1.0 PURPOSE This procedure provides criteria for determining if evacuation of a local area on-site or the Owner Controlled Area should be carried out. It provides instructions of effecting an orderly, rapid and safe evacuation of a local area or the Owner Controlled Area. It also provides instructions for personnel accountability.

NOTE One or more of the following symbols may be used in this procedure:

g Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS 2.1 References

1. St. Lucie Plant Radiological Emergency Plan (E-Plan)

2. St. Lucie Plant Physical Security Plan

3. E-Plan Implementing Procedures (EPIP 00-13)

4. HP-207, Monitoring Evacuated Personnel During Emergencies

5. HP-208, Personnel Decontamination During Emergencies

6. Security Procedure 0006123, Owner Controlled Area, Site Evacuation and Traffic Control

7. Administrative Procedure 0005770, On-Site Medical Program

8. ADM-15.02, Access Authorization and Control

REVISION NO.: PROCEDURE TITLE: PAGE:

1 PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 4 of 13 EPIP-07 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS 2.2 Records Required

1. A list of all persons at the Off-site Assembly Area should be documented on a form similar to Attachment 2, Off-site Assembly Area Roster, by the Assembly Area Supervisor.

2.3 Commitment Documents None 3.0 RESPONSIBILITIES 3.1 Nuclear Plant Supervisor (NPS)

1. Initiates the evacuation of any area in which a criterion for evacuation as expressed in Attachment 1, Evacuation Criteria is met.

2. Acts as the Emergency Coordinator (EC) after declaration of an emergency until relieved as specified in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3.2 Emergency Coordinator (EC)

1. Advises the Security Shift Specialist of a Local Evacuation or an Owner Controlled Area Evacuation. (EPIP-02)

(This notification may be by the plant alarm and/or plant/public address (PA) system.)

2. Reviews weather and plant conditions and makes Protective Action Recommendations (PARs) as necessary in accordance with EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3.3 Security Shift Specialist

1. When the TSC is activated, normally serves as the TSC Security Supervisor in accordance with the instructions provided in EPIP-04, Activation and Operation of the Technical Support Center.

REVISION NO.: PROCEDURE TITLE: PAGE:

PROCEDURE NO.: CONDUCT OF EVACUATIONS/ASSEMBLY 5 of 13 E PIP-07 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.4 Escorts/Tour Guides

1. Maintain personnel accountability of their groups.

2. Conduct evacuation of group upon hearing alarm, PA announcement, or receiving information from Security to do so.

3.5 Assembly Area Supervisor

1. Reports to and establishes the Off-site Assembly Area as directed by Operational Support Center (OSC) Supervisor.

3.6 Non-emergency Response Organization (ERO) Personnel Report to their normal office/lab/shop area upon notification.

2. Follow the instructions provided by the EC.

4.0 DEFINITIONS 4.1 Escort An individual specifically assigned to accompany another person(s) who is/are required by the Security Plan or Health Physics Manual to be escorted.

4.2 Essential Personnel Personnel essential to plant operation, security or currently filling or relieving an on-site emergency response position, including all qualified operators.

4.3 Health Physics Office Area The Health Physics Office Area, located in each of the Reactor Auxiliary Buildings (RABs), is likely to be used as an assembly location during a Local Evacuation of a radiologically affected area.

REVISION NO.: PROCEDURE TITLE: PAGE:

PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 6 of 13 EPIP-07 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4.4 Local Evacuation An evacuation of some portion of, but not all of, the Protected Area.

It may include evacuation of personnel from a room, area or building, located within the Protected Area.

A Local Evacuation outside the Protected Area, but within the Owner Controlled Area, may be ordered if the EC determines it to be an appropriate action. Conditions which may warrant a Local Evacuation involve uncontrolled radioactive materials outside the Radiation Controlled Area/Protected Area, hazards resulting from natural emergencies, fire damage, or a situation exists for which a Local Evacuation is deemed appropriate by the EC.

4.5 Nonessential Personnel Personnel NOT essential to plant operation or currently filling or relieving an on-site emergency response position.

4.6 Normal Workday The hours of 0700 to 1630 on all weekdays except holidays.

4.7 Normal Work Location A location to which Non-ERO personnel initially report upon declaration of an Alert. These areas are usually the employees'ormal work reporting locations (i.e., office/lab/shop area).

4.8 Off-site Assembly Area In an Owner Controlled Area Evacuation with a radiological release in progress, personnel from the Protected Area will report to the Off-site Assembly Area at Jaycee Public Park on Highway A1A, 7 1/2 miles north of the plant or Jensen Beach Parking Area 6 miles south of the plant, as directed by the EC. This area allows for personnel contamination control, assistance in accountability and for provision of additional information to evacuees as needed. An off-site Assembly Area may not be established if evacuation occurs prior to radiological release.

REVISiON NO.: PROCEDURE TITLE: PAGE:

PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 7 of 13 E PIP-07 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4.9 Owner Controlled Area That portion of FPL property surrounding and including the St. Lucie Nuclear Power Plant which is subject to limited access and control as deemed appropriate by FPL.

4.10 Owner Controlled Area Evacuation (= Site Evacuation)

The evacuation from the Owner Controlled Area of all personnel except those required to place the plant in a safe condition, the ERO and Security personnel necessary to fulfill responsibilities for evacuation.

4.11 Protected Area The area (within the Owner Controlled Area) occupied by the nuclear units and associated equipment and facilities enclosed within the security perimeter fence. The area within which accountability of personnel is maintained in an emergency.

4.12 Re-entry Access to areas where evacuation (local or site) has been ordered constitutes a re-entry. Re-entry into an evacuated area is authorized only by the EC.

I' REVISION NO.: PROCEDURE TITLE: PAGE:

1 PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 8 of 13 EPIP-07 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 NPS/Emergency Coordinator (EC)

Review plant conditions and take protective actions per EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

5.2 Security Shift Specialist 1 ~ Normally acts as the TSC Security Supervisor in accordance with EPIP-04, Activation and Operation of the Technical Support Center.

5.3 Assembly Area Supervisor Perform activities in accordance with Attachment 2, Off-site Assembly Area Supervisor Checklist.

5A Emergency Response Organization (ERO) Personnel Respond to your assigned emergency facility as directed.

2. Sign in on accountability roster.

3. Perform instructions in accordance with Facility EPIP.

5.5 Non-Emergency Response Personnel Site Assembly A. Report promptly to your normal office, lab or shop area as directed by PA announcement.

B. Follow any further instructions provided by the EC.

2. Site Evacuation (= Owner Controlled Area Evacuation)

A. Promptly proceed to the nearest access point upon hearing alarm or as directed by the PA announcements.

B. Retain possession of you TLD.

REVISION No.: PROCEDURE TITLE: PAGE:

PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 9 of 13 EPIP-07 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.5 Non-Emergency Response Personnel (continued)

2. (continued)

C. If there has not been a radiological release, Then personnel are directed to proceed home on the specified route.

D. If there has been or is currently a radiological release, Then personnel are directed to proceed to either Jensen Beach Park or Jaycee Park as directed.

END OF INSTRUCTIONS SECTION

REVISION NO.: PROCEDURE TITLE: PAGE:

1 PROCEDURE NO.: CONDUCT OF EVACUATIONS/ASSEMBLY 10 of 13 EPIP-07 ST. LUCIE PLANT ATTACHMENT1 CRITERIA FOR EVACUATION (Page 1 of 1)

Criteria for Local Evacuation The need for Local Evacuation shall be determined in accordance with the following criteria:

Evacuate the affected local area in which any of the following conditions occur:

1. Area Radiation Monitor Alarm.

2. Containment Evacuation Alarm.

3. Unevaluated direct radiation dose rate increase in excess of 100 mRem/hour above normal levels.

4. Unexpected airborne radioactivity concentration in excess of 1 x 10'icro Ci/cc.

5. Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm'eta-gamma over an area of 100 ft'.

6. Removable radioactive surface contamination in an unposted area in excess of 50 dpm/100cm'lpha over an area of 100 ft'.

7. The Emergency Coordinator determines that a situation exists for which Local Evacuation is appropriate.

Criteria for Owner Controlled Area Evacuation The Owner Controlled Area shall be evacuated in the following circumstances:

1. Site Area Emergency

2. General Emergency

3. If the Emergency Coordinator determines that the entire Owner Controlled Area should be evacuated.

END OF ATTACHMENT1

REVISION No.: PROCEDURE TITLE: PAGE:

1 PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 11 of 13 EPIP-07 ST. LUCIE PLANT ATTACHMENT2 ASSEMBLY AREA SUPERVISOR CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITYACTIVATION INITIAL Refer to Section 5 of EPIP-05, Activation and Operation of the Operational Support Center (included in the position notebook) and review the general instructions.

2. Obtain a radio and spare battery (use personal radio, if possible)

B. FACILITYOPERATION CAUTION An Off-site Assembly Area is required if a radiological release is in progress during the evacuation of the Owner Controlled Area.

1. Determine probable Off-site Assembly Area from consultation with the OSC Supervisor.

2. Determine personnel resource availability from:

a. HPOSC:

b. Security:

c. Available non-essential personnel:

3. Coordinate with the HPOSC for monitoring and decontamination assistance.

4. Coordinate with Security for traffic control assistance from off-site law enforcement agencies.

5. When directed by the OSC Supervisor, report to the designated Off-site Assembly Area.

REVISION No.: PROCEDURE TITLE: PAGE:

1 PROCEDURE No.: CONDUCT OF EVACUATIONS/ASSEMBLY 12 of 13 EPIP-07 ST. LUCIE PLANT ATTACHMENT2 ASSEMBLY AREA SUPERVISOR CHECKLIST (Page 2 of 2)

C. OFF-SITE ASSEMBLY AREA OPERATION INITIAL

1. Upon arrival at the Off-site Assembly Area, establish communications with the OSC Supervisor.

2. Steps to occur continually while the Off-site Assembly Area is in operation.

a. Using a form similar to Attachment 2A, ensure that arriving personnel are logged on the Off-site Assembly Area Roster.

b. Ensure all personnel frisk for contamination, assisting non-trained personnel as necessary.

3. Contact the OSC regarding any identified contamination for instructions and assistance.

D. DEACTIVATIONOF THE OFF-SITE ASSEMBLY AREA NOTE All paperwork completed in the position notebooks should remain in the position notebook.

1. At the direction of the OSC Supervisor, deactivated the Off-site Assembly Area.

2. Returned position notebook to the storage location in the OSC.

3. Provided all completed paperwork to the OSC Supervisor.

END Of ATTACHMENT2

E.'

t

REVISION NO.: PROCEDURE TITLE: PAGE:

1 PROCEDURE NO.: CONDUCT OF EVACUATIONS/ASSEMBLY 13 of 13 EPIP-07 ST. LUCIE PLANT ATTACHMENT2A OFF-SITE ASSEMBLY AREA ROSTER (Page 1 of 1)

NAME BADGE NO. NAME BADGE NO.

END OF ATTACHMENT2A

S OPS DATE OCT PROCEDURE FLORIDA POWER & LIGHT CN EPIP-01 SOS'7/ 8p S

CO COMPLETED ST. LUCIE PLANT ITM 0 PBQOVCJlCi'<

PREVIOUSLY ISSUED AS 3100022E EPIP-01 REVISION 0 CLASS ICATION 0 EMERGENCIES EME GENCY PLAN IMPLEMEN 8 PROCEDURE REVISION REVIEWED BY APPROVED Y DATE FRG ON 12/1 5/97 J. Scarola 12/15/97 Plant General Manag r Plant General Manager This procedure had a minor editorial change (/R )

on this cover page - Effective 4/15/98.

Depaftnlent'ROA Responsible

k t

REVISION NO.: PROCEDURE TITLE: PAGE:

0 CLASSIFICATION OF EMERGENCIES PROCEDURE No.: 2of28 EPIP-01 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS..... ~ . ~........... ~.....,..... ..,......

~ 3 3.0 RESPONSIBILITIES 4 3.1 Nuclear Plant Supervisor 4 3.2 .Emergency Coordinator ........... ~........ ~, 4 4.0 DEFINITIONS ............,.... ~..... ~...... ~.......... 4 5.0 INSTRUCTIONS ....................................... 6 ATTACHMENT ATTACHMENT 1 Emergency Classification Table...........,... 9

REVISION NO.: PROCEDURE TITLE: PAGE:

0 CLASSIFICATION OF EMERGENCIES PROCEDURE No.: 3 of 28 E PIP-01 ST. LUCIE PLANT 1.0 PURPOSE This procedure provides instructions on the classification of emergencies at St. Lucie Plant.

Emergency classifications in order of increasing seriousness are:

Unusual Event Alert Site Area Emergency General Emergency Specific criteria are provided to assure proper escalation and de-escalation between emergency classification levels.

NOTE One or more of the following symbols may be used in this procedure:

Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS 2.1 References

1. St. Lucie Plant Radiological Emergency Plan (E-Plan)

2. E-Plan Implementing Procedures (EPIP 00-13)

3. C-200, Offsite Dose Calculation Manual (ODCM).

4. AP 0010502, Oil and Hazardous Material Emergency Response Plan.

REVISION No.: PROCEDURE TITLE: PAGE:

0 CLASSIFICATION OF EMERGENCIES PROCEDURE No.: 4of28 E PIP-01 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS (continued) 2.2 Records Required The basis for classifying an emergency condition shall be recorded in appropriate emergency logs.

2.3 Commitment Documents None 3.0 RESPONSIBILITIES 3.1 Nuclear Plant Supervisor (NPS)

The Nuclear Plant Supervisor is responsible to promptly classify abnormal situations into one of the four defined categories.

2. If an emergency has been declared, the Nuclear Plant Supervisor is responsible for assuming the position of Emergency Coordinator and retaining this position until relieved.

3.2 Emergency Coordinator (EC)

The Emergency Coordinator is responsible to continually evaluate changes in plant conditions against the classification table in this procedure.

4.0 DEFINITIONS 4.1 Unusual. Event This classification is represented by off-normal events or conditions at the plant for which no significant degradation of the level of safety of the plant has occurred or is expected. Any releases of radioactive material which may have occurred or which may be expected are minor and constitute no appreciable health hazard.

REVISION No.: PROCEDURE TITLE: PAGE:

CLASSIFICATION OF EMERGENCIES PROCEDURE NO.: 5 of 28 E PIP-01 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4.2 Alert This classification is represented by events which involve an actual or potential substantial degradation of the level of safety of the plant combined with a potential for limited uncontrolled releases of radioactivity from the plant.

4.3 Site Area Emergency This classification is composed of events which involve actual or likely major failures of plant functions needed for protection of the public combined with a potential for significant uncontrolled releases of radioactivity from the plant.

4.4 General Emergency This classification is composed of events which involve actual or imminent substantial core degradation and potential loss of containment integrity combined with a likelihood of significant uncontrolled releases of radioactivity from the plant,

REVISION NO.: PROCEDURE TITLE: PAGE:

CLASSIFICATION OF EMERGENCIES PROCEDURE NO.: 6 of 28 EPIP-01 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Direct Initial Investigative and Mitigating Actions to Address the Event If the event involves entry into EOP's or ONOP's, Then perform steps per EOP's or ONOP's until appropriate or directed to classify event.

2. If the event involves a release of hazardous materials to the environment, Then respond per AP 0010502, Oil and Hazardous Material Emergency Response Plan.

3. If the event involves a release of radioactive material to the environment, Then direct Chemistry personnel to implement EPIP-09, Off-site Dose Calculations.

END OF SECTION 5.1

REVISION NO.: PROCEDURE TITLE: PAGE:

0 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.: 7 of 28 EPIP-01 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continUed)

NOTE Emergency Action Levels/Initiating Conditions are applicable to all modes unless otherwise indicated.

5.2 Classify event using best available information per Attachment 1, I. When apparently conflicting information is available, classify the condition at the most serious level indicated.

2. If in the judgement of the Nuclear Plant Supervisor (Emergency Coordinator), a situation is more serious than indicated by instrument readings or other parameters, Then classify the emergency condition at the more serious level.

3. If an Emergency Action Level (EAL) was met and the condition completely cleared prior to an emergency classification being declared, Then classify the event in accordance with Attachment 1 of this procedure.

CAUTION Only the Recovery Manager (RM) can authorize the downgrading (or terminating) of emergency classifications from Site Area Emergency or General Emergency.

4. If the Nuclear Plant Supervisor determines that the Initiating Condition(s) are met for an Unusual Event or Alert Emergency Action Level (EAL), even if the condition has cleared, Then declare and terminate the emergency condition.

END OF SECTION 5.2

REVISION No.: PROCEDURE TITLE: PAGE:

CLASSIFICATION OF EMERGENCIES PROCEDURE No.: 8of28 EPIP-01 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.3 If subsequent information of a more detailed nature (e.g., sampling results) becomes available after the initial classification has been made, Then reclassify as appropriate.

END OF SECTION 5.3

3J m EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0O CO 0

1A. ABNORMAL Reactor Coolant S stem RCS Leaka e GREATER LOCA GREATER THAN A release has occurred or is C PRIMARY RCS Leaka e ~THAN 50 Q 3) O z m capacity of charging pumps in r ressresultin in: m 0 LEAK RATE O z0 (Page 1 of 2) 1. RCS leakage 1. Charging/letdown 1. RCS leakage greater 1. Containment High Range GREATER THAN mismatch or measured than 132 gpm occurring Radiation monitor greater 10 gpm as indicated RCS leakage indicates with RCS pressure than 1.46 X 10'/hr (if by: greater than 50 gpm above HPSI shutoff CHRRM Inoperable, Post-but less than 132 gpm head. LOCA monitors greater 0 m O A. Control Room RCS leak. OR than 1000 mR/hr). m O

observation 2. RCS leakage greater OR C OR than available makeup 2. Performance of EPIP-09 XI O g B. Inventory balance occurring with RCS (Off-site Dose 6) calculation pressure below HPSI Calculations) or ITI CO ~

OR shutoff head. measured dose rates Z (g m C. Field observation OR OR

3. Loss of RCS subcooled from off-site surveys indicate site boundary O~ Tl CO O D. Emergency margin due to RCS (1 mite) exposure levels Coordinator leakage (saturated have been exceeded as I Judgement conditions). indicated by either A, B, N >

I 0z OR OR C or D below:

0 Mg 0

2. Indication of leaking RCS safety or relief

4. Containment High Range Radiation Monitors A. 1000 mrem/hr lQ Z m 0Il valve which causes fndicate (total dose rate) C) O~ 0 ITI RCS pressure to drop 7.3 X 10 R/hr (If below 1600 psia. CHRRM inoperable, B. 1000 mrem 0 m Post-LOCA monitors indicate between (total dose - TEDE) Z 33 C) 100 and 1000 mR/hr). C. 5000 mrem/hr m Z

(thyroid dose rate) UJ 0

D. 5000 mrem m m CD (thyroid dose - CDE)

(continued on next page) 1.A. ABNORMAL PRIMARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

3) 33 m 0

O EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY V) m m C7 0Z C

1.A. ABNORMAL Loss of 2 of the 3 fission 0 m 0 z0 PRIMARY roduct barriers with Q z0 LEAK RATE imminent loss of the third (Page 2 of 2) (any two of the following exist and the third is imminent).

0 O

1. Fuel element failure m

(confirmed DEQ I-131 O C

activity greater than 275 pCI/mL).

m 0 m AND Q 5'

2. LOCA or Tube rupture on m unisoiable steam z Pg m

generator. O~ t AND U 0) O

3. Containment Integrity fn (0

Breached. CD PO I M> 0z tO NOTE 0 U)

~mg 0 0ll Also refer to Potential m Core Melt Event/ D O~ 0 lTl Class 6.A.

0 ITI z 37 Q

fll W

zo I

m m CO 1.A. ABNORMAL PRIMARY 6) m LEAK RATE Cr AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0 M

CO

37 m 0

O EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY O 0 z

C 1.B. ABNORMAL PRIMARY TO RCS PRI/SEC Leaka e Ra id ross failure of one steam enerator tube Ra id ross failure of steam enerator tubes GREATER Loss of 2 of the 3 fission roduct barriers viith U g

37 nl 0 z0 SECONDARY 1. Measured RCS to THAN char in um imminent loss of the third O z0 LEAK RATE secondary leakage ca aci with loss of offsite ca aci with a loss of (any two of the following (Page 1 of 2) exceeds Tech. Spec. f)OWBf ~offeire ower exist and the third is limits. imminent).

AND 1. Measured RCS to 1. Measured RCS to

2. Secondary plant activity secondaiy leakage secondary leakage is 1. Fuel element failure 0 0

is detected. greater than Tech. Spec. greater than charging (confirmed DEQ l-131 m m O

Lfmits and within pump capacity. activity greater than charging pump capacity. AND 275 IrCI/mL). Zl AND 2. Secondary plant activity AND Q

2. Secondary plant activity is detected. 2. LOCA or Tube rupture ill is detected. AND on unisolable steam z m AND

3. Loss of both Non-Vital

3. Loss of both Non-Vital 4.16 KV buses.

generator. O~ ll AND U CO O 4.16 KV buses. 3. Containment integrity continued on next page breached.

I PO>

tD CD CO I

0z (continued on next page) 0 CO g 0 0ll NOTE m Also refer to Potential C) I 0 Core Melt Event/ m Class 6.A.

0 m z Zl G) m Ul z

O m Ill CO 1.B. ABNORMAL PRIMARY TO A SECONDARY m LEAK RATE 0

AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR h3 00

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 37 0

O m

(

Ch 0 0 Z

C 1.B. ABNORMAL PRIMARY TO Ra id failure of steam enerator tubes GREATER Ra ld failure of steam enerator tube s GREATER U 3J m

0 z0 SECONDARY THAN char in um THAN char in um O z LEAK RATE ca aci with steam release 0

~ca acity}

(Page 2 of 2) ~in regress

1. Measured RCS to secondary leakage 1. Measured RCS to greater than charging secondary leakage 0 O

pump capacity. greater than charging m O

AND pump capacity.

2. Secondary plant activity AND m O ZJ m is detected. 2. Secondary plant activity Q ls detected. m ~

U) m AND z

3. Secondary steam release in progress from affected O~ ll D O generator (i.e., ADVs, Q Steam Safety(s) or Unisolable.)

(D PO I

()

M~ n 0 mm 0 tQ CO oz m Z

z0 ITI XI Q

m W O m m V) 1.B. ABNORMAL PRIMARY TO SECONDARY Q m

LEAK RATE lV AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0 IQ Co

33 XI EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY 0

O GENERAL EMERGENCY ITl m 0

1.C. LOSS OF Ra id de ressurizatton of C Z SECONDARY ~seconda tant GREATER THAN 10 m GREATER THAN 50 m A release has occurred or is tn ro ress resultin in: U 37 m

0 Z 0

COOLANT rima Iseconda leaka e rima Iseconda leaka e O Z (Page 1 of 2) 1. Rapid drop in either and fuel dama e Indicated 1. Containment High Range 0

steam generator 1. Rapid drop in either Radiation monitor greater pressure to less than steam generator 1. Rapid drop in either than 1.46 X 10'/hr (If 600 psia. pressure to less than steam generator pressure CHRRM inoperable, Post-600 ps!a. to less than 600 psia.. LOCA monitors greater than 0 O

AND AND 1000 mR/hr). m O

2. Known pri/sec leak of 2. Known prVsec teak of OR greater than 10 gpm. greater than 50 gpm. 2. Performance of EPIP-09 XI O m AND AND (Off-site Dose Calculations) Q

3. Secondary plant activity 3. Secondary plant activity is or measured dose rates from ~

is detected. detected. off-site surveys indicate site zm CO Ill AND

4. Fuel element damage is boundary (1 mile) exposure levels have been exceeded O~ rl Total loss of feedwater indicated (Refer to Fuel U (6 O as indicated by either A, B, C Ql

1. No main or auxiliary feedwater flow available Element Failure Event/Class 4.A).

or D below:

A. 1000 mrem/hr (Q

CD Ol 0

I ng>

2 U)

I C

O 0z for greater than (total dose rate) 0Tl 15 minutes when required for heat TLOF with once-throu h

~tntnttn tntttatad B. 1000 mrem tQ C) 0+m Tl ITI U

fTl I

removal.. (total dose - TEDE)

AND

2. Steam Generator levels

1. No main or auxiliary feedwater flow available. C. 5000 mrem/hr 0z XI ITl are less than 40% wide AND (thyroid dose rate) G) range. 2. PORV(s) have been opened to facilitate core D. 5000 mrem UJ zOfTl heat removal. (thyroid dose-CDE) a m m (0

(continued on next page) 1.C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

XI m 0

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m O 0 C Z 1.C. LOSS OF SECONDARY Loss of 2 of the 3 fission gi Zl rn 0 2 0

COOLANT imminent loss of the third Q z0 (Page 2 of 2) (any two of the following exist and the third is imminent).

1. Fuel element failure 0O (confirmed DEQ I-131 m m activity greater than O C

m O 275 pCI/mL).

AND xQ ~m

2. LOCA or Tube rupture ITl i-on unisolable steam z CO m

generator.

AND O) q

3. Containment Integrity 0 (0 O ID Breached.

I PO (D

CD 0z NOTE O Also refer to Potential Core 0 Tl m m 0 Melt Event/Class 6.A. M C) 0+ I U 11 ITl I

0 ITI z Zl G)

ITl W

zO m ITl (0

1.C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO. TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

7l ill GENERAL EMERGENCY 0 C EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY fll in O

CO 0z 2.A. UNCONTROLLED Radiolo ical effluent A release has occurred or A release has occurred or is in A release has occurred or is in EFFLUENT limits exceeded ro ress resultin in: r ress resultin in: U m 0 z0 RELEASE 10 times the effluent limit o z0

1. Plant effluent 1. Containment High Range 1. Containment High Range monitor(s) 1. Plant eNuent Radiation Monitor greater Radiation monitor greater than exceed alarm monitor(s) significantly than 7.3 X 10'/hr 1 46 X 10s R/hr (If CHRRM setpoint(s). exceed alarm (Post-LOCA monitors inoperable, Post. LOCA monitors AND setpoints. indicate between 100 and greater than 1000 mR/hr). 0 O

2. Confirmed AND 1000 mR/hr, if CHRRM OR analysis results 2. Confirmed analysis inoperable). 2. Performance of EPIP-09 (Off-site O C

for gaseous or results for gaseous or liquid release which OR

2. Measured Dose Rates or Dose Calculations) or measured dose rates from off-site surveys Zl 0 m liquid release Q

which exceeds ODCM limits.

exceeds 10 times ODCM limits.

Offsite Dose Calculation (EPIP-09) worksheet values indicate site boundary (1 mile) exposure levels have been m

z ~

ffi m NOTE at one mile in excess of: exceeded as indicated by either A,B,CorDbelow:

O~ "1 If analysis is not NOTE A. 50 mrem/hr (total dose- U 0) O If analysis is not A. 1000 mrem/hr Q available within TEDE) or 250 mrem/hr CO one hour and it is available within one (thyroid dose-CDE) for (total dose rate) CD PO I 0

hour and it is expected 1/2 hour. V U)

N

~ C expected that release is greater that release ls equal to OR B. 1000 mrem 0 ~m g O 0ll or greater than 10 times B. 500 mrem/hr (total (total dose - TEDE) ITl than ODCM limit, M dassify as ODCM limit, classify as ALERT.

dose-TEDE) or C) O~ 0 lll UNUSUAL EVENT. 2500 mrem/hr (thyroid C. 5000 mrem/hr dose-CDE) for two minutes at one mile.

(thyroid dose rate) 0z ill ZI D. 5000 mrem Q (thyroid dose-CDE) ITl W

z O

ITI (6

ODCM - refers lo Chemistry Procedure C-200, Olfsite Dose Calculation Manual (ODCMI 2.A. UNCONTROLLED EFFLUENT RELEASE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

37 37 0O EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

~

m m O 0 z

2.B. HIGH RADIATION LEVELS IN PLANT Hi h radiation levels or hl h airborne contamination which U

~

xm 0 z0 indicates a severe de radatton Q z0 in the control of radioactive materials

1. Any valid area monitor alarm from Indeterminable 0 O

source with meter near or greater than full scale deflection (10'R/hr).

r m

O ~m O

C OR t Q

2. Unexpected plant Iodine or m S r m

particulate airborne R (g concentration of 1000 DAC as seen in routine surveying O~ ll or sampling. D (0 O OR (D

3. Unexpected direct radiation 6 %A I 0

dose rate reading or Co (D ~

unexpected airborne 0 'Tl ~

0)

ITl O

0Ti ITl radioactivity concentration from an indeterminable IO C) O~

Z 0 source in excess of m

1000 times normal levels.

0 ITl 33 6)

ITI Z'.

W 0 m ill CO 2.B. HIGH RADIATION 6)

LEVELS IN PLANT m CD AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0 h3 Oo

37 m

0 EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY le m O

CO 0z C

3. FIRE Uncontrolled fire within the lant lastin more than Uncontrolled fire Fire corn romlsln the function of sate s stems NOTE m

0 z0 0z Refer to Potential Core MeIt O 10 minutes. 1. Potentially affecting i.e. both trains rendered Event/Class 6.A.

safety systems. ino erable.

AND

2. Requiring off-site support in the opinion of the NPS/EC. 0 O

m O

C m O ZJ EXPLOSION Occurrence of an Severe dama e to safe Q m (0 i-ex losion which affects shutdown e ui ment from

~ex loslon.

z (O m Ovmer Controlled Area. ~lant o nraaon O~ Tl O

U A4 (0 I U)Pn~

(Q CO I

0 0 U) ~ O IQ m 0rl C) U I fll 0 m z XI G) fTl W 0 m fll (0

3. FIRE EXPLOSION Q

m AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0

M Co

37 Ill EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0

m O 0 4.A. FUEL Fuel element dame e Fuel element failure Fuel element failure with A release has occurred or is in Z 0

ELEMENT FAILURE '. Process monitors or area radiation surveys Process monitors or area radiation surveys inade uate core coolin

1. RCS DEQ I-131 activity ro ress resulbn 1.

in:

Containment High Range Q

U m z0 z0 indicate increased Indicate increased greater than or equal to Radiation monitor greater than letdown activity letdown activity and 275 pCVmL. 1.46 X 10'/hr (If CHRRM AND

2. Confirmed RCS sample indicating:

confirmed RCS Samples indicating DEQ 1-131 activity greater than or

'. AND Highest GET per core quadrant indicates greater inoperable, Post-LOCA monitors greater than 1000 mR/hr). m 0

0 m

than 10'F superheat or O

equal to 275 pCVmL. OR C A. Coolant activity greater than the 700'F. 2. Performance of EPIP-09 (Off-site Dose Calculations) or m o g Q

Tech Spec limit for iodine spike (Tech measured dose rates from off-site surveys indicate site m

z ~ m Spec Figure 3.4-1.).

OR boundary (1 mile) exposure levels have been exceeded as U O~ Tl B. Coolant activity NOTE indicated by either A, B, C or fu CD O If analysis is not available tO greater than D below:

100/E pCi/gram within one hour and it is expected that RCS activity (D

PO U) ~

I 0z specific activity. for DEQ I-131 is greater A. 1000 mrem/hr C) Mg 0 than 275 fiCi/mL, classify (total dose rate) 0 Ill 0ll as an ALERT.

B. 1000 mrem lQ C) 0+ I U fil NOTE (total dose - TEDE)

If analysis is not available 0 fil within one hour and it is expected that activity is C. 5000 mrem/hr (thyroid dose rate) z 37 Q

greater than Tech Spec limit, classify as UNUSUAL EVENT.

D. 5000 mrem (thyroid dose - CDE)

I m

ITI O

Ill I

CO 4.A FUEL ELEMENT FAILURE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

37 x

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY 0

GENERAL EMERGENCY m rn 0 0 4.8. FUEL HANDLING Fuel handlin accident which Ma or dame e to irradiated g C z ACCIDENT results in the release. of fuel in Containment or Fuel Q O z O

m z0 0 radioactivi to Containment or Fuel Handiin Buildin

1. Step increase in the

1. NPS/EC determines that an reading of radiation Irradiated fuel assembly may monitors in the plant have been damaged. vent and/or in the Fuel 0 0

AND Handling Building. Ill

2. Associated area or process AND radiation monitors are in 2. Damage to more than xQ O m alarm. one irradiated fuel assembly. ~

OR z CO g) m Uncovering of one or more irradiated fuel O~ "l assemblies in the Spent (0 O Fuel Pool.

2 N

n> C I

0z U) ~ O 0

z ITIU 0rl M O~

O I Ill 0z z ITI 33 6) m W

z 0

ill m CO 4.8. FUEL HANDLING ACCIDENT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

rrl EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0

V)

ITI m 5.A. EARTHQUAKE A confirmed earth uake A confirmed earth uake occurs which A confirmed earth uake occurs which g U 0 z

C has occurrod re isters GREATER THAN 0.05 r lsters GREATER THAN 0.1 . with NOTE 0 z0

1. A confirmed lant not at cold shutdown Refer to Potential Coro Melt Event/Class 6.A.

0P mz0 earthquako has been experienced within the Owner Controlled Area.

OR 0O rTI m

2. An earthquake is O detected by plant C solsmlc monitor m

XI 0 g instruments. Q CO ~

Z g) m 5.B. HURRICANE Hurricane Wamln Hurricane wamin with winds near Hurricane wamln with winds NOTE O~ n dsshen bash GREATER THAN desi n basis Refer to Potential Core fD (0 O Melt Event/Class 6.A.

6 %A I

1. Confirmed hurricane 1. Confirmed hurricane warning is in 1. Plant not at cold shutdown. M>

tQ N 0z warning Is in effecL effect and winds are expected to excoed 175 mph within the Owner AND

2. Confirmed hum'cane warning is fn 0 mm g O 0 m

Controlled Area. effect and winds are expected to tQ OZI 0 exceed 194 mph within the Owner C) fll Controlled Area.

NOTE NOTE 0 ITI Zl At FPL's request, NOAA will provide At FPL's roquost, NOAA will provide Z Q an accurato projection of wind speeds an accurato projoction of wind m onsfte 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to tho onset of speeds onsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the hurricane force winds. If that projection Is not available within onset of hurricane force winds. If that projection is not avaihble within UJ 0

m Pl 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering into tho warning, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering into the warning, (0 dassify the event using current track dassify tho event using current track and wind speeds to project onsite and wind speeds to project onsite conditions. For example, projected conditions. For example, projected onsite wind speed would be less than onsite wind speed would be fess than maximum hurricano wind speed if the maximum hurrlcano wind speed if tho track is away from PSL track Is away from PSL 5.A. EARTHQUAKE m S.B. HURRICANE C) 0 AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR fQ Co

37 33 0

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m O 0 5.C. TORNADO Notification of a tornado An tornado strikin facili Z si hted fn the Owner NOTE Refer to Potential Core VI t

2 Ill 0 Z 0

Controlled Area O Z Melt Event/Class 6.A. 0 m 00m O

3J 0 ~

nl Q

5.D. ABNORMAL Abnormal water level Flood low water hurricane sur e or Flood low water hurricane sur e or ~

WATER LEVEL conditions are ex ected other abnormal water level other abnormal water level z CO (g frl

~or occumn conditions conditions causin failure of vital 0)

1. Low Intake canal 1. The storm drain capacity is erteut rmmeenntt Q

U (8 0 (D

level of -10.5 ft. exceeded during hurricane surge 1. Rood/surge water level reaching (D 2 O 0 MLW for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or or known flood conditions. elevation +1 9.5 ft. (turbine N ~ I z more. OR building/RAB ground floor). CD U) ~ 0 OR 2. Low Intake canal tevel of -10.5 ft. OR 0 m 0ll

2. Visual sightings by station personnel MLW for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or more with emergency barrier valves open.

2. Low intake canal level has caused the loss of all ICW flow. C) 0+ I U ITl that water tevels are approaching storm 0 m drain system Z Zl G) capacity.

m m

I 0

m m (0

5.C. TORNADO 5.D. ABNORMAL WATER LEVEL AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

33 NOTE 0 (

m ITl m Activation of the Emergency Response Facilities does not require dedaration of an emergency or entry into a specific emergency classification. O 0 C

O z SITE AREA i m 0 EVENT/CLASS UNUSUAL EVENT ALERT EMERGENCY GENERAL EMERGENCY O z0 Eme e Coordinatoi's Emer enc Coordinatoi's Emer e Coordinator's ud emont that ud einent that hnt ud ement that hnt lant conditions exist that make release or conditions exist which conditions exist which lar e amounts of radioactivi in a short warrant: warrant riod a ear ossiblo or like . (Any core 0 melt situation.)

m O m

1. Increased awareness 1. Activation of C

and activation of emergency responso 1. LOCA with failure of ECCS leading to fll 0 Emergency Response facilities and severe coro degradation or melt. g personnel. monitoring teams or a OR Q Emer en Coordinator's precautionary 2. LOCA with initially successful ECCS and ITT f/) m notification to the subsequent failure of containment heat R g) conditions exist which public near tho site. removal systems for soveral hours. O~ n warrant increased awareness on the art of 3.

OR Total loss of feedwator followod by failure Q U (0 0 the eratl staff and/or of once-through~ling (ECCS) to (D 6 PO local authorities. adequately cool tho coro.

Ul ~ 0 OR 0) ~ 0

1. The plant is shutdown 4. Failure of off-site and on-site power along 0 Tl ITl fTl 0ll under abnormal conditions (e.g.,

with total loss of emergency feedwater makeup capability for soveral hours. tO O

0+ 0 ITl exceeding cooldown OR rates or primary 5. ATWS occurs which results in core system pipe cracks are damage or causes faituro of core cooling 0 fll found during and make-up systems. R 33 Q

operation). OR fll 6.A. INCREASED OR

2. Any plant shutdown

6. Any major internal or oxtornal ovent (e.g.,

fire, earthquake or tornado substantially Ql z0 AWARENESS required by Technical OR SpeciTications in which beyond design basis) which In the ECs opinion has or could bauso massive fll m CO POTENTIAL the required shutdown damage to plant systems resulting in any CORE MELT h not reached within of the above.

(Page 1 of 2) action limits. (continued on next page) 6A. INCREASED AWARENESS OR POTENTIAL CORE MELT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

2l m

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0

fII

~

CO m

O 0 z

6.A. INCREASED NOTES 0 37 O Z AWARENESS 1. Most likely containment failure g m 0 OR POTENTIAL mode is melt-through with O z0 CORE MELT release of gases only. Quicker (Page 2 of 2) releases are expected for failure of containment isolation system.

2. General Emergency must be 0O declared for the above listed events. The likelihood of O C

corrective action (repair of AFW pump, etc.) should not be ITI ZJ 0 m considered. Q m U)

0) g ~ ~

O~ II U

fo (D 0 (O

Co

)

M n~ C:I 0Z Ol Ul

'll ~

0 0 fff 0II lQ O

0+ I ITl m

z0 fTI Q

fTI UJ z0 III fll (D

6.A. INCREASED AWARENESS OR POTENTIAL CORE MELT 6) m CD AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0 lQ Co

37 m

0 EVENT/CLASS UNUSUAL EVENT ALERT SlTE AREA EMERGENCY GENERAL EMERGENCY m m 0 0 7.A. LOSS OF Loss ot off-site wer or Station Blackout otal Loss Station Blackout otal Loss g C z NOTE 0 3' O z POWER loss of all on-site AC ower of AC of AC tor GREATER THAN Refer to Potential Core m 0

~aa abili 15 minutes Melt Event/Class 6.A.

O z0

1. Loss of off-site

1. Loss ot off-site AC AC power. 1. Loss of offsite AC power.

power. AND AND OR 2. Failure ot both 2. Sustained failure of both

2. Loss of capability to emergency diesel emergency diesel 0 power at least one vital 4.16 kv bus from~an generators to start or synchronize.

generators to start or synchronize.

r m

0 O

m U

C avaffable emergency AND ZJ g diesel generator. 3. Failure to restore Q Loss of all on-site DC AC power to at least one tll (0 ~

~ower vital 4.16 kv bus within Z (0 m

1. DroplnAandBDCbus 15 minutes. O~ 'Tl 0 O voltages to less than AA (0 70 VDC. Loss of all vital on-site DC for reater than 15 minutes Q

CD I

PO lD ~

~

I O

0

1. Sustained drop in A and 0 m 0Tf B DC bus voltages to 70 VDC for greater than fQ O O~z ITl 15 minutes.

0 ITl R 33 G)

W z0m lTl lTl (0

m~

m 7.A. LOSS OF POWER 0

AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR M Co

33 37 EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 00 Ill m O 0Z 8.A. LOSS OF PlANT Loss of Plant Control Critical Loss of Plant Control CONTROL Functions Functions NOTE 0 0 Z

FUNCTIONS Refer to Potential Core 0 Z 0

1. Complete loss of any 1. Loss of any function or Melt Event/Class 6.A.

function needed for plant system which, in the cold shutdown. opinion of the Emergency OR Coordinator, precfudes

2. Failure of the Reactor placing the plant In Hot 0 O

Protection System to Shutdown. fll m bring the reactor OR O subcritlcal when needed.

OR

2. Fagure of the RPS to trip the reactor when needed m 0 g

3. Control Room is and operator actions fail to Q evacuated (for other than bring the reactor Ill CO i-drill purposes) with control subcritical. R rn established locally at the OR O) Il Hot Shutdown Control 3. Control Room Is evacuated Q

D (0 0 Panel. (for other than drill purposes) and control cannot be established I PO (O

0z Loss ol Shutdown Coolin locally at the Hot Shutdown 0

1. Complete loss of Control Panel within 15 minutes.

0 ~m z ITI 0fl functions needed to maintain cold shutdown.

0 O~

IQ U fll A. Failure of shutdown 0 fll cooling systems, Z 33 G) resulting in loss of fll cold shutdown conditions. 0 ANO Ill m B. RCS subcooling can CO NOT be maintained greater than O'.

8.A. LOSS OF PLANT CONTROL FUNCTIONS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

37 m

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY 0

GENERAL EMERGENCY fTl m 0

Z S.B. LOSS OF ALARMS / Si nificant loss of effiuent Loss of alarms Loss of alarms COMMUNICATION/ g m 0 2 0

MONITORING communications indication 1. Unplanned loss of all 1. Inability to monitor a O z0 and alarm anels etc. which safety system sign! ficant transient in Im airs abiii to erform annuncfators. progress.

accident or emer en AND assessment. 2. Plant transient in progress. 0 0

1. Lossofefftuentor radiological monitoring capability requiring plant r

Ill O g m

O 37 shutdown.

C)

OR ITI- CO ~

2. Loss of all primary and Z g) m backup communication capability with offsite O~ ll 0 CO O locations. Q OR (O

3. Unplanned loss of most CD

%0 N~

I 0

or all Safety System CO Mg 0 annunciators for greater 0 0Tl than 15 minutes.

fQ C) 0+ ITl U

ITI 0 ITl z Zl G) m W O Ill ITI (D

S.B. LOSS OF ALARMS /

COMMUNICATION/

MONITORING Q m

0)

AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0

IQ CO

m EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0O O 0 z

Unusual aircraft activi Aircraft/missile im act Dame e to vital s stems from aircraft/missiles g O z 0

1. Aircraft crash In the 1. Aircraft crash In the O z0 Owner Controlled Area Owner Controlled Area 1. Aircraft crash in the or unusual aircratt damaging plant Owner Controlled Area activity over facility that structures. damaging vital plant in the opinion of the OR systems.

NPS/EC, could 2. Visual or audible OR 0 o

threaten the satety of indication ot missile 2. Damage to safe 9.A. AIRCRAFT / the plant or personnel. impact on plant shutdown equipment O C

MISSILE structures. from any missile. ITI XJ Q

Ill m R

9.B. TURBINE FAILURE

~Turbtne rntettn corn onent failure causin Visual indication that the turbine casin has been O) ra Id lant shutdown. enetratedb bladin . Q U O (Q

(D PO MK I

()

CO Ã~ 0 0 0 tQ O m 9.C. TOXIC OR Un lanned/uncontrolled Ent of toxic or flammable Toxic or flammable as has 0

FLAMMABLE GAS toxic or flammable as release in the Owner as into areas otentiall affectin lant o eration.

diffused Into vital areas affectin access to or the z 33 6)

Controlled Area that could o eration ot safe shutdown iTl affect lant/ ersonnel ~cut recut. UJ O

m Il1 9.A. AIRCRAFT/ CO MISSILE 9.B. TURBINE FAILURE 9.C. TOXIC OR FLAMMABLE fn GAS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0 Co

m EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0

m Q o 0

10. SECURITY A SECURITY ALERT has A SECURITY A SECURITY EMERGENCY U C A successful takeover of the THREAT been called b the Secuii EMERGENCY has been O z lant includin the Control i m 0 Force in res onse to one occu an of the control Room oran otherarea s O z 0

or more of the items listed Force as defined In the room or other area s vital vital to the o eration of the below. Safe uards Contin en to the o aration of the reactor as er the Securi Plan. reactor as defined in the Plan .

1. Bomb threat Safe uards Contin en

2. Attack threat Plan. 0O

3. Civil disturbance m

4. Protected area O C

intrusion m XI

5. Sabotage attempt Q

6. Internal disturbance m M ~

7. Vital area intrusion z (g m

8. Security force strike O~ n U O (O

Q tQ PO M~

I 0

O U) ~ O 0 0ll lQ m

0z m 33 G)

ITI R O m ITI U)

10. SECURITY THREAT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

Procedure No.

ST. LUCIE PLANT EPIP-03 EMERGENCY PLAN Current Rev. No.

FPL IMPLEMENTING PROCEDURE 6 SAFETY RELATED Effective Date:

07/07/99

Title:

EMERGENCY RESPONSE ORGANIZATION NOTIFICATION/STAFF AUGMENTATION Responsible Department: EMERGENCY PLANNING Revision Summary Revision 6 - Removed reference to the rotating maintenance shift supervisor from the definition/description of the duty call supervisor and revised security title from supervisor to specialist. (J. R. Walker, 07/01/99)

Revision 5 - Transferred EP responsibilities from the Training Manager to the Protection Services Manager. Made editorial changes and added new position -regulatory affairs.

(J. R. Walker, 06/17/99)

Revision 4 - Added 2 new positions to call tree to address Security org. and added editorial/administrative changes. (J. R. Walker, 2/23/99)

PSL O

k 8

PROCEDtj BE PRODUCTION Revision FRG Review Date Approved By Approval Date S OPS DATE 12/1 5/97 1/30/98 J. Scarola 1/30/98 DOCT PROCEDURE Plant General Manager DOCN EPIP-03 SYS Revision FRG Review Date Approved By Approval Date COMP COMPLETED 07/01/99 R. G. West 07/01/99 ITM 6 Plant General Manager N/A Designated Approver

I ~

0 k

1 l5'

REVISION NO.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 2 of 24 EPIP-03 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ........................ ................

~ ~ . 3

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS 3 3.0 RESPONSIBILITIES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.1 Emergency Coordinator .. . ~ ~...... ~....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.2 Duty Call Supervisor ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.3 Members of Emergency Response Organization ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 3.4 Protection Services Manager ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 4.0 DEFINITIONS . ~ . ~... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 5.0 INSTRUCTIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 0 ~ ~ ~ ~ ~ ~ i 7 ATTACHMENT ATTACHMENT 1 EMERGENCY STAFFING CALL TREE ... ~ . ~...... 14

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 3of24 E PIP-03 ST. LUCIE PLANT 1.0 PURPOSE This procedure provides instructions to:

1.1 Activate the St. Lucie Plant Emergency Response Organization (ERO) for staff augmentation in response to an emergency declaration.

1.2 Conduct a quarterly update/verification of the ERO.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and 'shall NOT be revised without Facility Review Group review and Plant General Manager approval ~

Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff, 2.1 References

1. St. Lucie Plant Radiological Emergency Plan (E-Plan)

2. E-Plan Implementing Procedures (EPIP 00-13)

3. HP-200, Health Physics Emergency Organization

4. AP 0010120, Conduct of Operations

6. ADM-15.04, Fitness For Duty - Call-Out and For Cause Testing

6. St. Lucie Plant Emergency Response Directory (ERD)

7. QI-17-PSL-1, Quality Assurance Records 2.2 Records Required None

REVISION NO.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE No.: NOTIFICATION/STAFF AUGMENTATION 4 of 24 E PIP-03 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS (continued) 2.3 Commitment Documents None 3.0 RESPONSIBILITIES 3.1 The Emergency Coordinator (EC) has the overall responsibility for the notification and callout of the ERO as provided for in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3.2 The Duty Call Supervisor (DCS)

The Duty Call Supervisor reports to the affected Unit Control Room upon declaration of the emergency, If the unaffected Unit ANPS assumes the role of DCS, Then he/she shall fulfill the responsibilities without leaving the unaffected Control Room.

2. Complete the following as directed by the NPS/EC:

A. State Notification Form (EPIP-02).

B. Off-site notifications (EPIP-02).

C. Staff augmentation (per this procedure).

D. Operations Department Accountability Aid.

3. Conduct a turnover with the TSC OPS Coordinator (NPS Communicator in the Control Room) regarding the status of communications and other tasks underway.

3.3 Members of the Emergency Response Organization (ERO):

1. Advise the Protection Services Manager when his/her duties are changed such that he/she can no longer participate in the ERO.

2. Maintain a copy of the ERD readily available 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day (individuals with caltout duties only).

REVISION NO.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 5 of 24 E PIP-03 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.3 Members of the Emergency Response Organization (ERO): (continued)

3. Make notifications, as required by their position, when notified by the DCS, in accordance with the instructions contained in the ERD.

4. When notified, report to the assigned Emergency Response Facility (ERF).

3.4 Protection Ser vices Manager

1. Ensure verification of the following for ERO personnel quarterly:

A. Personnel phone/beeper numbers B. Training qualifications in accordance with EPIP-12, Maintaining Emergency Preparedness, Radiological Emergency Plan Training.

4.0 DEFINITIONS 4.1 Auto dialer See FPL Emergency Recall System below.

4.2 Duty Call Supervisor (DCS)

The Duty Call Supervisor is a specifically designated and trained supervisor responsible fore assisting the Emergency Coordinator in making notifications and calls to the Emergency Response Organization. /R6 4.3 Emergency Response Organization (ERO)

A trained group of personnel that are designated to perform specific duties during emergencies.

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 6 of 24 EPIP-03 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4A St. Lucie Plant Emergency Response Directory (ERD)

A printed directory which provides guidance for performing a call-out of the Emergency Response Organization. The ERD contains the names, positions, home phone numbers, and pager numbers for the members of the ERO.

4.5 FPL Emergency Recall System (ERS)

A computer-based automated call-out system used to activate the ERO.

This system is also referred to as the "autodialer".

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 7 of 24 EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Emergency Coordinator (EC)

1. Instructions for the EC are located in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

END OF SECTION 5.1

REVISION No.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION Sof24 EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Duty Call Supervisor (DCS)

1. Initiate call-out of ERO members as directed by the EC.

A. Instructions for activation of the autodialer are located in the Duty Call Supervisor Notebook which is maintained in accordance with Appendix E to AP-0010120, Conduct of Operations.

2. If during normal working hours, Then activate autodialer only.

A. Do NOT call-out ERO members using the ERD.

3. If during off normal working hours, Then begin call-out of ERO members, as detailed in the ERD, after initiating the autodialer.

A. Notify Security Shift Specialist AND HP Shift Supervisor/On-shift Tech by plant radio or other prompt means. /R6 B. Notify each of the following positions by cell/page/radio:

Emergency Coordinator

2. Recovery Manager

3. Nuclear Division Duty Officer C. If autodialer has NOT activated, Then continue to notify the following:

'. TSC Chemistry Supervisor

2. TSC EP Coordinator

3. EP Manager

4. EOF Emergency Technical Manager

5. TSC Coordinator with OSC.

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE No.: NOTIFICATION/STAFF AUGMENTATION 9 of 24 EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Duty Call Supervisor (DCS) (continued)

3. (continued)

D. When the responder answers, CLEARLY STATE THE FOLLOWING:

1. This is (your name), functioning as Duty Call Supervisor.

2. This is an/a (actual emergency/call-out drill/phone test) message.

3. St. Lucie Plant has declared an/a (ALERT/ SITE AREA EMERGENCY / GENERAL EMERGENCY) OFt is conducting a (call-out drill/phone test).

4. I am calling you for the position of (state position from Step 5,2.3 above).

a. Are you fit for duty and able to respond?

(If YES: record name on call-out list and continue with questions).

(If NO: Terminate the call and go to next person for the position.)

b. What is your estimated drive time to your emergency response facility?

(Record estimated arrival time under ETA on'call-out list).

5. Promptly complete your call tree section if applicable and report to your emergency response facility.

OR This is a phone test only, DO NOT report to your emergency response facility after completing your calls.

h REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 10 of 24 EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Duty Call Supervisor (DCS) (continued)

3. (continued)

E. If autodialer activation is indicated, Then NOTIFY Security Shift Specialist and HP Shift Supervisor/On-shift Tech to suspend call-out. /R6 END OF SECTION 5.2

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 11 of 24 EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.3 ERO Members with Call Tree Duties

1. Maintain a current copy of the ERD for use at all times.

2. Perform manual call-outs as instructed by the DCS and ERD.

A. Begin at the top of your call list and proceed down the list until either:

An individual is contacted to fill each position All positions have been attempted once.

B. When the responder answers, CLEARLY STATE THE FOLLOWING:

1. This is (your name), functioning as (ERO position title) ~

2. This is an/a (actual emergency/call-out drill/phone test) message.

3. St. Lucie Plant has declared an/a (ALERT/ SITE AREA EMERGENCY / GENERAL EMERGENCY) OR is conducting a (call-out drill/phone test).

4. I am calling you for the position of (state position from ERD Call-out Phone List).

a. Are you fit for duty and able to respond?

(tf YES: check name on call-out list and continue with questions).

(If NO: Terminate the call and go to next person for the position.)

b. What is your estimated drive time to your emergency response facility?

(Record estimated arrival time under ETA on call-out list).

1 0

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE No.: NOTIFICATION/STAFF AUGMENTATION 12 of 24 EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.3 ERO Members with Call Tree Duties (continued)

2. (continued)

B. (continued)

5. Promptly report to your emergency facility.

OR This is a phone test'only, DO NOT report to your emergency response facility.

C. Report to assigned emergency response facility upon completion of call-outs and furnish call-out data to facility manager.

If consumed alcohol in the past 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , Then report to Security prior to entering the site or EOF.

END OF SECTION 5.3

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 13 of 24 E PIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5A ERO Members with no call-out duties Report at once to your assigned emergency response facility.

If consumed alcohol in the past 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , Then report to Security prior to entering the site or EOF, END OF SECTION 5A

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 14 of 24 E PIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 1 of 11)

DUTY CALL SUPERVISOR AUTODIALER SECURllY ACTIVATED OFFICER 01 SECURilY OFRCER 02 SECURllY SHI SPEC!AUST SECURllY OFRCER 0S SECURIIY OFRCER 04 TSC HP SUPERVISOR OSC DOSIMETRY TECH OSC HP HP SHIFT SUPERVISOR SUPERVSOIV ONSHIFT TECH TSC HP OSC HP TECHS COMMUNICATORg)

BELD MONITOR TEAM DRIVER I3)

EMERGENCY COORDINATOR DUTY CALL SUPERVISOR NUCLEAR DMSON DUTYOFRCER TSC CHEMI SUPEBNSOR OSC CHEMIST (3)

EOF EMERGENCY TECHNICALMANAGE TSC COORDINATOR WITH OSC

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 15 of 24 E PIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 2 of 11)

SECURITY GUARD ¹1 TSC SECURITY SUPERVISOR TSC REACTOR ENGINEER*

TSC COMMUNICATOR (3)

SECURITY TSC ELECTRICAL OFFICER ¹1 REP - PST TSC SUPERVISOR*

TSC OPS COORDINATOR (2)

TSC MECHANICAL REP - PST (3)*

'INIMUMSTAFFING POSITION QB FIRST UNE ALTERNATETO MINIMUMSTAFFING POSITION (EPIP03B. WPG)

r REVISION NO.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 16 of 24 EPIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 3 of 11)

SECURITY GUARD ¹2 OSC MECHANICAL FOREMAN*

OSC ELECTRICAL CHIEF'SC I&C SHOP SUPERVISOR" SECURITY OFFICER ¹2 OSC MECHANIC (3)*

OSC ELECTRICIAN (3)

OSC I&C SPEC (3)*

'INIMUMSTAFFING POSmON 93 FIRST UNE ALTERNATETO MINIMUMSTAFFING POSIllON (EPIP03C. IVPG)

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 17 of 24 EPIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 4 of 11)

SECURITY GUARD ¹3 OSC SUPERVISOR OSC MECH REENTRY SUPV*

OSC I&C REENTRY SUPV

'SC ELEC REENTRY SUPV

OSC COORDINATOR WITH TSC OSC OPS REENTRY SUPV SECURITY OFFICER 3 ¹ OSC SAFETY REP OSC ADMINTECH/

LOGKEEPER 2 OSC PROTECTION

& CONTROL REP OSC NMM STAFF REP OSC PARAMEDIC OSC INFORMATION SERVICES REP ASSEMBLY AREA MINIMUMSTAFRNG POSITION QB SUPERVISOR FIRST UNE ALTERNATE TO MINIMUMSTAFRNG POSITION (EPIRUD. WPG)

'I REVISION NO.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO. NOTIFICATION/STAFF AUGMENTATION 18 of 24 EPIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 5 of 11)

SECURITY GUARD 44 EOF RM OPS ADVISOR/LOGKPR (2)

EOF COMMUNICATOR (4)'OF HEALTH PHYSICS MANAGER

'ECURITY OFFICER 0 4 EOF ERDADS OPERATOR

'OF DOSE ASSESSOR/FMT COORD. (3)

'OF EMERGENCY SECURITY MANAGER

~ MINIMUMSTAFFING POSITION OB FIRST UNE ALTERNATETO MINIMUMSTAFFING POSITION (EPIP03E. WPG)

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 19 Of 24 EPIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 6 of 11)

NUCLEAR DIVISION DUTY OFFICER ST. WCIE COUNlY TECH ADVISOR EOF EMERG ENCY INFORMATION MANAGER GOVERNOR' ADVISOR NUCLEAR DMSION GOVBLNMENTAL DUlYOFFICER AFFAIRS MANAGER GOVERNMENTAL.

AFFAIRS REF.

TALLAHASSEE AVIATOR RISK MANAGER

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 20 of 24 EPIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 7 of 11)

TSC EP COORDINATOR TSC SP PHONETALKER (2)

TSC ERDADS OPERATOR TSC SRO REP - PST TSC EP COORDINATOR TSC EC ASSISTANT/

LOGKEEPER TSC PROBLEM SOLVING TEAM LEADER TSC I&C REP - PST TSC ERDADS TECH TSC ADMIN STAFF (2)

(EPIP03G. WPG)

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 21 of 24 E PIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 8 of 11)

EP MANAGER EOF NUCLEAR LICENSING MANAGER EOF RAD STATUS BOARDS KEEPER EP MANAGER EOF HP TECH SUPPORT EOF ADMIN SUPERVISOR EOF ADMIN STAFF (3)

(EPIP03H. WPG)

REVISION NO.: PROCEDURE TITLE: PAGE:

'MERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 22 of 24 E PIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 9 of 11)

EOF EMERGENCY TECHNICAL MANAGER EOF IIIC ENGINEER EOF PROJECT EOF ELECTRICAL ENGINEER ENGINEER EOF MECHANICAL ENGINEER (2)

EOF EMERGENCY TECHNICAL MANAGER EOF NUCLEAR FUELS ENGINEER EOF NUCLEAR EOF CIVIL ENGINEER ENGINEER EOF STATUS BOARD KEEPER (EPIPMI. WPG)

REVISION NO.: PROCEDURE TITLE: PAGE:

6 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 23 of 24 E PIP-03 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY STAFFING CALL TREE (Page 10 of 11)

Emergency Response Organization Positions List Position Title Position Title 100 Duty Call Supervisor 161 OSC Electrician (3) ~

101 Emergency Coordinator 162 OSC Mechanic (3) 102 TSC Supervisor 163 OSC IKC Specialist (3) 103 TSC HP Supervisor 166 OSC Dosimetry Technician 104 TSC Chemistry Supervisor 167 OSC Paramedic 105 TSC Reactor Engineer 168 OSC Mechanical Foreman 106 TSC Communicator (3) 169 OSC NMM Staff Rep 107 TSC Elec Rep - Problem Solving Tm 170 OSC Safety Rep 108 TSC Mech Rep - Problem Solving Tm (3) 171 OSC Admin Tech/Logkeeper (2) 109'10 HP Shift Supervisor/On Shift Tech 172 Assembly Area Supervisor TSC Ops Coordinator (2) 173 OSC Ops Reentry Supervisor TSC Dose Assessor 174 OSC Protection and Control Rep 112 TSC HP Communicator (2) 175 OSC ILC Shop Supervisor 113 TSC SP Phonetaiker (2) 176 Field Monitoring Team Driver (3) 114 TSC ERDADS Operator 177 OSC information Services Rep 115 TSC Problem Solving Team Leader 180" Security Shift Specialist 116 TSC ERDADS Tech 181* Security Officer (4) 117 TSC IBC Rep - Problem Solving Tm 200 Recovery Manager 118 TSC SRO Rep - Problem Solving Tm 204 Risk Manager 119 TSC Security Supervisor 205 Governmental Affairs Manager 120 TSC Coordinator with OSC 209 EOF RM Ops Advisor/Logkeeper (2) 121 TSC Administrative Staff (2) 213 EOF ERDADS Operator TSC EP Coordinator 216 EOF Status Board Keeper 124 TSC EC Assistant/Logkeeper 230 EOF Emergency Technical Manager 151 OSC HP Tech (ALL) 231 EOF Project Engineer 152 OSC Electrical Reentry Supervisor 232 EOF Mechanical Engineer (2) 153 OSC l&C Reentry Supervisor 233 EOF Nuclear Engineer 154 OSC Mechanical Reentry Supervisor 235 EOF Nuclear Fuels Engineer 155 OSC Chemistry Supervisor 236 EOF Civil Engineer 156 OSC Electrical Chief 237 EOF l8C Engineer 157 OSC Supervisor 238 EOF Electrical Engineer 158 OSC Coordinator with TSC 240 EOF Health Physics Manager 159 OSC HP Supervisor 245 EOF Dose Assessor/FMT Coord. (3) 160 OSC Chemist (3) 246 EOF HP Tech Support Not ERO positions, but are needed to ensure automated call-out logic will function properly.

REVISION NO.: PROCEDURE TITLE: PAGE:

EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION/STAFF AUGMENTATION 24 of 24 E PIP-03 ST. LUCIE PLANT ATl ACHMENT 1 EMERGENCY STAFFING CALL TREE (Page 11 of 11)

Emergency Response Organization Positions List Position Title Position Title 247 EOF Rad Status Boards Keeper 279 Regulatory Affairs 250 EOF Nuclear Licensing Manager 280 EOF Administrative Supervisor 255 EOF Communicator (4) 281 EOF Administrative Staff (3) 260 EOF Emergency Security Manager 290 EP Manager 270 EOF Emergency Information Manager 291 Governor's Advisor 271 Nuclear Division Duty Officer 294 St. Lucie County Technical Advisor 273 EIM/ENC Technical Advisor (2) 295 Martin County Technical Advisor 275 Governmental Affairs Assistant 300 Emergency Control Officer 276 Gov Affairs Rep (Tallahassee) 301 President, Nuclear Division 278 Aviator END OF ATTACHMENT1

J Procedure No.

ST. LUCIE PLANT EPlP-12 EMERGENCY PLAN Current Rev. No.

FPL IMPLEMENTING PROCEDURE 5 SAFETY RELATED Effective Date:

12/08/99

Title:

MAINTAININGEMERGENCY PREPAREDNESS - RADIOLOGICAL EMERGENCY PLAN TRAINING Responsible Department: EMERGENCY PLANNING Revision Summary Revision 5 - Removed PAR training from the qualification requirements for the TSC Dose Assessor position. (J. R. Walker, 12/03/99)

Revision 4 - Changed title throughout (Protection Services Manager) and addressed changes prompted by use of PQD as official training database. (J. R. Walker, 07/08/99)

PSL I- O Q

O PROCEDURE P"tODUCTION Revision FRG Review Date Approved By Approval Date S OPS DATE 12/15/97 J. Scarola 12/1 5/97 DOCT PROCEDURE Plant General Manager DOCN EPIP-12 SYS Revision FRG Review Date Approved By Approval Date COMP COMPLETED R. G. West 12/03/99 ITM 5 12/03/99 Plant General Manager N/A Designated Approver

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 2 of 38 EPIP-12 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS .. ~... ~....... .,.............. ~..... ~....

~ 4 3.0 RESPONSIBILITIES 4.0 DEFINITIONS ~ . ~ ~......... ~ . ~ ~ ~ . ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 5.0 INSTRUCTIONS .... ~.... ~..... ~...... ~.....

~ ~ ~ .. ~ . ~ .. 10 5.1 Initial Training ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 0 5.2 Annual Retraining ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 13 5.3 Loss of ERO Qualifications . ~ ~..... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. 16 5.4 Training of Security Personnel ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e 17 5.5 Fire Brigade............ ~... ~... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 18 5.6 Training Exemptions and Substitutions ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 1 9 ATTACHMENTS ATTACHMENT 1 EMERGENCY RESPONSE ORGANIZATION CHANGE REQUEST................ ~ .. ~ ~ ~.... 20 ATTACHMENT2 ERO INITIALTRAINING MATRIX .. ~ ~ ~ ~ ~ 21 ATTACHMENT3 ERO ANNUAL REQUALIFICATIONMATRIX .. ~...... 30

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICAL EMERGENCY PLAN TRAINING 3 of 38 EPIP-12 ST. LUCIE PLANT 1.0 PURPOSE 1.1 This procedure provides the Emergency Plan (E-Plan) training requirements for site personnel and personnel in the St. Lucie Plant Emergency Response Organization (ERO).

1.2 In order to maintain emergency preparedness, personnel should be familiar with certain pre-planned actions specified in the Emergency Plan Implementing Procedures (EPIPs). The primary objectives of this training are as follows:

1. Familiarize appropriate individuals with the E-Plan and related EPIPs.

2. Instruct individuals in their specific duties to ensure effective and expeditious action during an emergency.

3. Periodically present significant changes in the scope or content of the E-Plan and the EPIPs.

4. Provide annual retraining to ensure that personnel are familiar with their emergency duties and responsibilities.

5. Provide the various emergency organization groups with the required training that will ensure an integrated and prompt response to an emergency situation.

1.3 The annual training cycle normally occurs in the first quarter of each year.

1.4 The E-Plan Training Review Committee provides for the review and evaluation of changes, the impact on training, and the determination if training is needed prior to the next cycle.

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 4of38 EPIP-12 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

2.1 References

1. St. Lucie Plant Radiological Emergency Plan (E-Plan)

2. Ql 1-PR/PSL-1, Site Organization.

3. QI-17-PSL-1, Quality Assurance Records.

4. AP 0005752, Plant Access Training Program.

5. AP 1800022, Fire Protection Plan.

6. ADM-11.11, Severe Accident Management Guidelines Program Administration

7. St. Lucie Plant Emergency Response Directory.

2.2 Records Required Records documenting the Emergency Plan Training received by individuals are Quality Assurance records and shall be maintained in the plant files in accordance with QI-17-PSL-1, Quality Assurance Records.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 5 of 38 EPIP-12 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS (continued) 2.3 Commitment Documents

1. St. Lucie Plant General Policy PSL-110, Emergency Response.

2. 10 CFR 50.47, Emergency Plans.

3. 10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities.

4. 10 CFR 26, Fitness for Duty.

5. NUREG 0737, 11.B.4, Training for Mitigating Core Damage

6. NOV Response L-97-20, Violation II.C, Part 4A.

7. NOV Response L-97-20, Violation II.C, Part 4B.

8. NRC Inspection Report 96-18 URI P5.2

9. QAS-EMP-96-01, Finding 2

10. PMAI PM99-05-183 (Use and Update of the Personnel Qualification Database (PWD))

11. PMAI PM99-09-077, CR 99-1353 (Training requirements for TSC Dose Assessor) /R5 3.0 RESPONSIBILITIES 3.1 The Training Manager is responsible for:

1. Designing, establishing, implementing and maintaining training programs for the St. Lucie Plant.

2. Ensuring initial orientation training is provided to permanently assigned new employees.

3. Ensuring all Emergency Plan Training, both initial training and periodic retraining, is conducted and documented for the St. Lucie Plant ERO.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 6 of 38 EPIP-12 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.2 Protection Services Manager is responsible for:

1. Ensuring that a qualified Emergency Response Organization (ERO) is maintained in compliance with the St. Lucie Radiological Emergency Plan.

2. Coordinating emergency planning at the plant.

3.3 Emergency Preparedness is responsible for:

1. Establishing qualifications standards for ERO personnel.

2. Reviewing and approving the Emergency Plan Training Program.

3. Offering training to each contracted local hospital, at least once each year.

A. The content of that training should consist of radiological controls, medical consideration of contaminated injuries, and other topics as appropriate.

4. Offering training to each State and local emergency response agency, at least once each calendar year.

A. The content of that training should consist of an overview of normal and emergency plant operations and concepts of radiation protection, including protective actions.

t B. This training may be in the form of a presentation, text, or other acceptable means.

5. Providing the table of Emergency Action Levels (EALs) to state and local officials for their review, on an annual basis.

0

6. Revising the St. Lucie Plant Emergency Response Directory (ERD) and the FPL Emergency Recall System (autodialer) database when notified via a form similar to Attachment 1.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 7 of 38 EPIP-12 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.3 Emergency Preparedness is responsible for: (continued)

7. Providing a list of personnel designated to fill emergency response positions and requiring training per this procedure, to the Training Department.

8. Removing individuals who fail to maintain training qualifications from the ERD and the FPL Emergency Recall System (autodialer) database when notified by the appropriate department head or the Training Department.

9. Providing guidelines to plant management to assist in identifying the appropriate number of ERO personnel for each ERO position.

10. Notifying the Training Manager if changes in the E-Plan and/or EPIPs justify additional training for ERO personnel.

11. Chairing EP Training Review Committee Meetings.

$3 3.4 Each Manager and Department Head is responsible to ensure that each ERO member under his/her supervision attends training in accordance with Attachments 2 and 3, and remains fully qualified at all times to perform his/her assigned emergency response duties.

1. Ensure personnel in his/her department who are assigned an on-site position in the ERO maintain unescorted access to the Protected Area and Radiation Controlled Area.

2. Ensure changes in his/her employees'tatus which would impair or limit the ability to perform emergency response duties be promptly reported to the Protection Services Manager (directly or through EP) ~

A. Provide alternate personnel to be trained to fill open positions.

3.5 The Protection Services Manager is responsible to ensure that Security personnel maintain EP training qualifications per this procedure.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING Sof38 EPIP-12 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.6 ERO members, supervisors, training instructors, HP dosimetry personnel and medical facility staff are responsible for promptly reporting any failure in training, testing or other condition, which would disqualify an emergency responder, to the Protection Services Manager (directly or through EP).

3.7 Each ERO member is responsible for advising the Protection Services Manager (directly or through EP) when changes in status occur that could impact ERO participation.

4.0 DEFINITIONS 4.1 Annual - occurring once per calendar year (January 1 through December 31).

4.2 Duty Call Supervisor (DCS) - is a specifically designated and trained supervisor responsible for assisting the Emergency Coordinator in making notifications and calls to the Emergency Response Organization.

4.3 Emergency Plan - formally known as the St. Lucie Plant Radiological Emergency Plan, establishes the requirements for training the Emergency Response Organization; also referred to as the Plan or E-Plan.

4.4 Emergency Planning (EP) - activities undertaken to satisfy the commitments of the Emergency Plan, used interchangeably with Emergency Preparedness.

4.5 Emergency Response Directory (ERD) - formally known as the St.

Lucie Plant Emergency Response Directory, provides a list of the current (revised on a quarterly basis) Emergency Response Organization personnel.

4.6 Emergency Response Organization (ERO) - personnel trained and qualified to provide specific emergency response functions as defined by their individual positions. Persons can become members of the Emergency Response Organization by following the instructions outlined in this procedure.

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 9 of 38 EPIP-12 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4.7 EP Training Review Committee (TRC) - representatives from Emergency Preparedness, Training, and other departments who meet periodically to discuss training issues related to the Emergency Response Organization.

4.8 SAMG - Severe Accident Management Guidelines.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 10 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS NOTE In the event of an emergency, the Emergency Coordinator or Recovery Manager has the authority to assign personnel to positions for which they have not received the required Emergency Plan training, if that action is prudent in order to protect the health and safety of the public and plant personnel.

The training requirements listed in this procedure are for the purpose of emergency preparedness and are in addition to other training required to hold a position, e.g., Nuclear Plant Supervisor (NPS), Shift Technical Advisor (STA).

Personnel filling the position of Emergency Coordinator, TSC OPS Coordinator, or RM OPS Advisor should have SRO level knowledge (i.e., current or previous SRO license or SRO equivalent training such as Engineering Management Operations Training (EMOT)).

5.1 Initial Training NOTE Initial Training is intended for personnel who are new to the ERO and is designed to orient the individual to his/her function and responsibilities within the ERO.

Drill participation is not required prior to qualifying for an ERO position.

~ It may be desirable to allow persons filling the following positions to participate in and/or observe their position in a drill prior to being assigned to the ERO:

Emergency Coordinator Recovery Manager TSC Supervisor OSC Supervisor TSC Coordinator with the OSC OSC Coordinator with the TSC

1. Initial Orientation Training (Plant Access Training - PAT) shall be provided to permanently assigned new employees.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 11 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 Initial Training (continued)

1. (continued)

A. Training includes information describing:

1 ~ Actions to be taken by an individual who discovers an emergency condition.

2. Location of assembly areas.

3. Identification of emergency alarms.

4. Action to be taken upon hearing alarms.

B. PAT Training is conducted in accordance with AP 0005752, Plant Access Training Program.

5o,4 2. Personnel shall complete the Initial Training requirements identified in Attachment 2, ERO Initial Training Matrix, prior to being assigned to the ERO.

3. To become a member of the ERO, an individual should fill out Attachment 1, Emergency Response Organization Change Request.

A. Complete the personal information (originator section).

B. Obtain Department Head approval ~

C. Forward the Attachment to Emergency Preparedness Supervisor.

4. Emergency Preparedness (EP) should authorize the training of personnel designated to become new members of the ERO on Attachment 1.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 12 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 Initial Training (continued) .

5. Training Department personnel should document completion of required training on Attachment 1 and forward to the Emergency Preparedness Supervisor when new members complete the training requirements as identified in Attachment 2, ERO Initial Training Matrix.

6. EP should make changes to the Emergency Recall System (ERS) and the Emergency Response Directory (ERD) upon receipt of Attachment 1 from Technical Training.

END OF SECTION 5.1

REVISION No.: PROCEDURE TITLE: PAGE:

5 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICAL EMERGENCY PLAN TRAINING 13 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued)

NOTE Retraining is intended to ensure that ERO personnel maintain the level of skill and knowledge necessary to accomplish their emergency duties.

Retraining may be accomplished through a combination of programmed instruction and/or participation in drills or exercises.

5.2 Annual Retraining

1. Annual retraining shall be provided at least once per calendar year.

2. The scope of annual retraining should be determined by the EP Training Review Committee and shall be approved by the Training Manager.

A. Annual retraining shall include a review of any significant changes in the scope or content of the Emergency Plan or applicable Emergency Plan Implementing Procedures.

I B. Annual retraining shall include the training topics identified in Attachment 3, ERO Annual Requalification Matrix.

C. Additional topics for annual retraining may include, but are not limited to, the following:

- a review of items listed in initial training

- industry operating experience

- a review of past drill/exercise performance problems NOTE Deviation from this schedule requires the approval of the President, Nuclear Division.

3. Emergency Response Facility (ERF) drills shall be conducted at least four times per calendar year and should be conducted approximately once each quarter.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 14 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Annual Retraining (continued)

3. (continued)

NOTE It is the intent of the drill and exercise program that each ERO member have an opportunity to function in his/her position annually.

A. Participation in drills and exercises should be tracked by Emergency Preparedness Supervisor and forwarded to Technical Training.

Drill rosters should be reviewed and used to record participants in all Emergency Response Facilities (ERFs) including the Emergency News Center (ENC).

2. Drill critiques should list Players, Controllers, Evaluators, and Observers for each facility.

3. Drill participation should be recorded in the training database.

54,S B. Personnel should be rotated through drills and exercises with the goal of having as many as feasible participate in at least one drill or exercise per year. This applies to all ERO members, including those who are NOT in the Nuclear Division.

1. Participation in a drill or exercise shall be recognized if an ERO member functions as a Player.

2. Participation in a drill may be recognized if an ERO member functions as a Controller, Evaluator, or Observer for a position to which that member is normally assigned.

3. Failure to participate in an ERF drill annually may result in remedial training as determined by the Training Manager and Protection Services Manager. Remedial training may include table top sessions or repeat of initial training.

REVISION No.: PROCEDURE TITLE: PAGE:

5 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 15 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Annual Retraining (continued)

4. An individual may complete annual retraining by passing the examination for each topic without attending the class(es).

5. Personnel who teach a class should receive credit for completion of that class at the discretion of the Technical Training Supervisor.

END OF SECTION 5.2

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 16 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) g4 5.3 Loss of ERO Qualifications

1. If an individual fails an initial training topic, Then that individual shall not be assigned to the ERO until he/she has successfully met requirements.

2. If an individual fails Plant Access Training (PAT), Radiation Controlled Area Training (RCAT), or fails to maintain qualifications for use of respiratory protection (as specified in Attachment 3),

Then he/she shall promptly be removed from the ERO.

3. If an individual fails an annual retraining evaluation, the Training Manager shall notify the Emergency Preparedness Supervisor or designee of the results.

A. The individual should then be removed from the ERS and ERD until appropriate remedial training, as recommended by the Training Manager and approved by the Emergency Preparedness Supervisor, has been completed.

4. The individual should complete remedial training at the earliest opportunity. As a minimum, remedial training shall consist of:

A. Trainee review of the training session material associated with identified knowledge deficiencies.

B. Trainee review of associated reference material identified by the instructor.

C. Administration of a second evaluation covering at least the identified deficiencies.

5. If an individual successfully completes a second examination, the individual should receive credit for completion of the required training.

END OF SECTION 5.3

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 17 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5A Training for Security Personnel

1. Security personnel shall receive initial training and annual retraining for emergency response in accordance with this procedure.

END OF SECTION 5.4

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 18 of 38 E PIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.5 Fire Brigade Fire Brigade training is covered by the Fire Protection Plan, AP 1800022.

END OF SECTION 5.5

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICAL EMERGENCY PLAN TRAINING 19 of 38 EPIP-12 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.6 Training Exemptions and Substitutions

1. No specific Emergency Plan Training is required for ERO positions whose emergency job functions are similar to normal job functions.

Examples of these positions include:

A. Emergency News Center/ Corporate Communications Staff B. Governmental Affairs Staff C. Risk Manager D. Regulatory Affairs

2. Personnel who participate in a drill or attend annual requalification training at PTN may receive credit/satisfy the requirements for drill participation and/or annual retraining as required by this procedure.

ERO positions eligible to receive credit include (but are not limited to):

A. Emergency Information Manager (EIM)

B. Nuclear Division Duty Officer (NDDO)

C. Emergency Control Officer (ECO)

END OF SECTION 5.6

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. RADIOLOGICAL EMERGENCY PLAN TRAINING 20 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT1 EMERGENCY RESPONSE ORGANIZATION CHANGE REQUEST NOTE Personnel will not be assigned to an emergency response organization position until required training for that position is completed.

Originator: Dept.

0 R

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Work Phone:

Home Phone:

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Other.

DEPT Department Head/Supv. Signature:

HEAD Authorization for ERO training EP Supervisor T $, 0 The individual listed above meets the training/qualification requirements of EPIP-12 for R the position(s) indicated per the Personnel Qualification Database (PQD).

A I

N 0 The individual listed above requires training. Notify the Dept. Head, Dept. Training I Coord. (if applicable) and the Technical Training Supervisor.

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Signature: Date ~~

0 Emergency Recall System database updated: Date: ~~ Init.:

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0 Notifications to ERO: Date: ~~ Init.:

$, 0 Notification of Personnel Qualification Database (PQD) Administrator Date: ~~ Init.:

Only information required if ~removin from ERO (by EP)

END OF ATTACHMENT1

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 21 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 1 of 9)

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ERO ¹ POSITION Ucensed EC 6 G' X X X STA X X X X NLO G Gl G G DCS G X' 101 Emergency Coordinator X X 102 TSC Supervisor X 103 TSC HP Supervisor X X 104 TSC Chem. Supervisor X G X X X B 105 TSC Reactor Engineer G X X X = Required E = PSL or PTN Training may be acceptable B = Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C = Respirator Only H = FFD Pool Induded in ERO Activation training for DCS only: D = Induded in Emerg. Rad. Monitoring Autodialer JPM Manual call-out exam Simulator practice session with E-Plan events If qualified to hold shift position, Then position meets ERO qualification criteria

REVISION No.: PROCEDURETITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 22 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 2 of 9)

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REVISION NO.: PROCEDURE TITLE PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 23 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 3 of 9)

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119 TSC Security Supv. G 120 TSC Coord. with OSC G 121 TSC Admin Staff 124 TSC EC Assist/Log. G X 151 OSC HP Tech. X G G X Required E = PSL or PTN Training may be acceptable B Accident Chemistry Considerations Module G = Training/Requai Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool Induded in ERO Activation training for DCS only: D = Included in Emerg. Rad. Monitoring Autodialer JPM Manual callwut exam Simulator practice session with E-Plan events If qualified to hold shift position, Then position meets ERO qualification criteria

0 REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 24 of 38 E PIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 4 of 9)

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160 OSC Chemist X X Required E = PSL or PTN Training may be acceptable B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool Included in ERO Activation training for DCS only: D = Included in Emerg. Rad. Monitoring Autodialer JPM Manual callwut exam Simulator practice session with E-Plan events If qualified to hold shift position, Then position meets ERO qualification criteria

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 25 of 38 E PIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 5 of 9)

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/R5

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MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 26 of 38 E PIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 6 of 9)

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X Required E = PSL or PTN Training may be acceptable B Acddent Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool Induded in ERO Activation training for DCS only: D = Included in Emerg. Rad. Monitoring Autodiaier JPM Manual callwut exam Simulator practice session with E-Plan events If qualified to hold shift position, Then position meets ERO qualification criteria

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REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICAL EMERGENCY PLAN TRAINING 27 of 38 E PIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 7 of 9) 0 0 CO C

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REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 28 of 38 E PIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 8 of 9)

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255 EOF Communicator X Emerg. Security Mgr. H X Required E = PSL or PTN Training may be acceptable B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool Included in ERO Activation training for DCS only: D = Included In Emerg. Rad. Monitoring Autodialer JPM Manual call-out exam Simulator practice session viith E-Plan events If qualified to hold shift position, Then position meets ERO qualification criteria

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 29 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT2 ERO INITIALTRAINING MATRIX (Page 9 of 9)

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ERO ¹ POSITION 270 EOF Emerg Info Mgr. E E 271 NDDO E E X X X 273 EIM/ENC Tech Advisor X X 280 EOF Admin Supervisor X X 281 EOF Admin Staff X X 291 Governor's Advisor 294 St. Lucie Co Tech Adv X X 295 Martin Co Tech Adv X X Emer Control Officer E E X X X X Required E = PSL or PTN Training may be acceptable B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool included in ERO Activation training for DCS only: D = Included in Emerg. Rad. Monitoring Autodialer JPM Manual callwut exam Simulator practice session with E-Plan events If qualified to hold shift position, Then position meets ERO qualification criteria END OF ATTACHMENT2

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MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 30 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUALREQUALIFICATION MATRIX (Page 1 of 9)

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REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 31 of 38 EPIP-I 2 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 2 of 9)

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E E 0 LD 0 0 e Cl 0 uj uj O O CC ilJ 0 ti K ERO N POSITION 107 TSC EM PST Rep.

108 TSC MM PST Rep. G 110 TSC OPS Coordinator TSC Dose Assessor G X X 112 TSC HP Communicator 113 TSC SP Phonetalker G 114 TSC ERDADS Op. G 115 TSC PST Leader G 116 TSC ERDADS Tech X Required F = SAMG Requal Frequency IAW ADM-11.11 B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool If qualified to hold shift position, Then position meets ERO qualification criteria

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MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 32 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 3 of 9)

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119 TSC Security Supv. G 120 TSC Coord. with OSC G 121 TSC Admin Staff G 124 TSC EC Assist/Log. X X 151 OSC HP Tech. G G X 152 OSC EM Re-Entry Supv. G OSC l&C Re-Entry Supv. G X Required F = SAMG Requal Frequency IAW ADM-11.11 8 Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool If qualified to hold shift position, Then position meets ERO qualification criteria

0 REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 33 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 4 of 9)

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0 ERO ¹ POSITION 154 OSC MM Re-Entry Supv. G G 155 OSC Chem. Supv. G G G B/G 156 OSC Electrical Chief G G 157 OSC Supervisor G 158 OSC Coord. viith TSC X 159 OSC HP Supv. X G 160 OSC Chemist G G 161 OSC Electrician G G 162 OSC Mechanic G G X Required F = SAMG Requal Frequency IAW ADM-11.11 B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H= FFD Pool If qualified to hold shift position, Then position meets ERO qualification criteria

0 REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 34 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 5 of 9) 0C O

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172 Assembly Area Supv. G X Required F = SAMG Requal Frequency IAW ADM-11.11 B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool If qualified to hold shift position, Then position meets ERO qualification criteria

0 REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 35 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 6 of 9)

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209 EOF RM OPS Adv/Log. X X 213 EOF ERDADS Op.

X Required F = SAMG Requal Frequency IAW ADM-11.11 B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool It qualified to hold shift position, Then position meets ERO qualification criteria

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: RADIOLOGICALEMERGENCY PLAN TRAINING 36 of 38 E PIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 7 of 9) 0 O

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0 tu 0 0 tu tu 0 K ERO II POSITION 216 EOF Status Board Keeper X H 230 EOF Emerg Technical Mgr X H 231 EOF Project Engineer 232 EOF Mech. Engineer X- H 233 EOF Nuclear Engineer X H 236 EOF Nuc Fuels Eng. X H X X 236 EOF Civil Engineer X H 237 EOF l&C Engineer X H EOF Electrical Engineer X H X Required F = SAMG Requal Frequency IAW ADM-11.11 8 Accident Chemistiy Considerations Module G = Training/Requai Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool It qualified to hold shift position, Then position meets ERO qualification ciiteria

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 37 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 8 of 9) 0C Oi C

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00 E UJ rJ UJ Cl 0 IJ. K ERO ¹ POSITION 240 EOF HP Manager 245 EOF Dose Assessor/FMT 246 EOF HP Tech Support 247 EOF Rad Stat Bds Keeper EOF Nuc. Uc. Mgr.

255 EOF Communicator 260 Emerg. Security Mgr.

270 EOF Emerg Info Mgr.

271 NDDO X X X Required F = SAMG Requal Frequency IAW ADM-11.11 B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool If qualified to hold shift position, Then position meets ERO qualification criteria

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: RADIOLOGICALEMERGENCY PLAN TRAINING 38 of 38 EPIP-12 ST. LUCIE PLANT ATTACHMENT3 ERO ANNUAL REQUALIFICATION MATRIX (Page 9 of 9) b 01 C

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ERO ff POSITION 273 EIM/ENC Tech Advisor X H 280 EOF Admin Supeivisor X H 281 EOF Admin Staff X H 291 Govemol's Advisor 294 St. Lucie Co Tech Advisor X H 295 Martin Co Tech Advisor X H Emergency Control Officer E H X X X Required F = SAMG Requal Frequency IAW ADM-11.11 B Accident Chemistry Considerations Module G = Training/Requal Frequency IAW other Plant Procedures C Respirator Only H = FFD Pool E PSL or PTN Training May be Acceptable If qualified to hold shift position, Then position meets ERO qualification criteria END OF ATTACHMENT3

Procedure No.

ST. LUCIE PLANT Eptp-13 EMERGENCY PLAN Current Rev. No.

FPL IMPLEMENTING PROCEDURE 3 SAFETY RELATED Effective Date:

07/06/99

Title:

MAINTAININGEMERGENCY PREPAREDNESS-EMERGENCY EXERCISES, DRILLS, TESTS AND EVALUATIONS Responsible Department: EMERGENCY PLANNING Revision Summary Revision 3 - Changed responsibility for EP from Training Manager to Protection Services Manager. Improved definition for drill per E-Plan. Corrected eval. exercise frequency from annual to biennial per E-Plan. Corrected recovery plan review frequency. Corrected review of annual training. Corrected procedure number and title of upgraded E-Plan chemistry procedures. Corrected ex critique review from Training Manager to FRG per E-Plan. Made editorial and administrative changes. (J. R. Walker, 06/17/99)

,Revision 2 - Minor Corrections page 18, C-110 changed to COP-06.06 and C-111 changed to COP-06.11. (Russ Cox, 06/01/99)

PSL PROCEOUAE PRODUCTION Revision FRG Review Date Approved By Approval Date S OPS DATE 0 12/15/97 J. Scarola 12/15/97 DOCT PROCEDURE Plant General Manager DOCN EPIP-13 Revision FRG Review Date SYS Approved By Approval Date COMP COMPLETED 06/17/99 R. G. West 06/17/99 ITM 3 Plant General Manager

fl

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E I

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 2 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1 o0 PURPOSE o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS 3 2..1 References ................. ~.............. ~ . ~... 3

~............ ~......

~

2.2 Records Required .. ~..... . ~... 4

~............

~

2.3 Commitment Documents .... ~ ~... ~.... ~ . 4 3.0 RESPONSIBILITIES .. ~...... ~....... ~.............. ..

~ ~ 4 4.0 DEFINITIONS ~ . ~ . ~ ~....... ~...., ~.... ~...............

~ 6 5.0 INSTRUCTIONS ................. ~ ., ~...., . ~ .. 9 5.1 Protection Services Manager Instructions......... 9 /R3 5.2 Emergency Preparedness Supervisor ........... 11 DATA SHEETS DATA SHEET 1 EP PROGRAM MAINTENANCECHECKLIST........ 13 DATA SHEET 2 EMERGENCY PLAN 6 YEAR ELEMENT DEMONSTRATION ~ ~............. ~ . 16 DATA SHEET 3 EPIP BIENNIAL REVIEW ...................... 17 DATA SHEET 4 EP EXERCISE CHECKLIST ...... ~............

~ 19 /R3 ATTACHMENT J

S ATTACHMENT 1 EP PROGRAM SCHEDULE........... ~ ~ ~ ~ ~ ~ ~ 20

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 3 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT 1.0 PURPOSE This procedure provides instructions for:

Periodic exercises and drills conducted in order to test the state of emergency preparedness by FPL personnel, support organizations and off-site governmental agencies. /R3 Periodic tests'and reviews of components of the Emergency Planning Program (e.g. facilities, equipment, Emergency Plan and Emergency Plan Implementing Procedures, etc.) conducted to ensure availability, operability and reliability.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS

-'NOTE One or more of the following symbols may be used in this procedure:

g Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

Indicates a management directive, vendor recommendation, plant practice or other non-regulatoIy commitment that should NOT be revised without consultation with the plant staff.

2.1 References

1. St. Lucie Plant Radiological Emergency Plan (E-Plan)

U

2. Ql 1-PR/PSL-1, Site Organization

3. QI-1-PSL-15, Protection Services Organization /R3

4. Ql-5-PSL-1, Preparation, Revision, Review/Approval of Procedures. /R3

5. QI-17-PSL-1, Quality Assurance Records /R3

6. NBS-NPS-EP-WP-001, Public Alert and Notification System Testing, Maintenance and Engineering

REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 4 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS (continued) 2.2 Records Required

1. The following records are maintained in accordance with Ql-17-PSL-1 Quality Assurance Records: /R3

2. Data Sheet 1, EP Program Maintenance Checklist

3. Data Sheet 2, Emergency Plan 6 Year Element Demonstration /R3

4. Data Sheet 3, EPIP Biennial Review

5. Data Sheet 4, EP Annual Exercise Checklist

6. Attachment 1, EP Program Schedule 2.3 Commitment Documents 1 ~ 10 CFR 50, Domestic Licensing of Production and Utilization Facilities

2. PMAI ¹96-02-237, Evaluation of Continuous Emergency Response

3. NOV Response L-97-20, Violation II ~ A, Part 4.D.

4. St. Lucie Plant General Policy PSL-110, Emergency Response 3.0 RESPONSIBILITIES 3.1 The Protection Services Manager is responsible for: /R3

1. Planning, scheduling, and coordinating emergency exercises involving off-site agencies. /R3

2. Reviewing Attachment 1, EP Program Schedule, upon completion.

3. Reviewing results of exercises and major drills.

REVISION No.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 5 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.2 The Protection Services Manager, in conjunction with plant management, is responsible for ensuring that adequate resources are made available to support and conduct emergency preparedness activities including: /R3 Exercise and drill scenario development and control /R3

2. Exercise and drill participation /R3

3. Support for maintenance of emergency facilities and equipment g, 3.3 The Facility Review Group (FRG) is responsible to review the following:

1 ~ Revisions to the St. Lucie Plant Radiological Emergency Plan and Emergency Plan Implementing Procedures (EPIPs)

2. Biennial Exercise Critique Report. /R3 3A The Emergency Preparedness (EP) Supervisor is responsible for:

1. Maintaining awareness of EP activities.

2. Ensuring coordination of EP drills and exercises in accordance with this procedure.

3. Ensuring documentation of EP program maintenance in Attachment 1, EP Program Schedule.

4. Ensuring documentation of major element demonstration as indicated on Data Sheet 2, Emergency Plan 6 Year Element Demonstration.

5. Ensuring critiques of exercises, drills, and actual events are conducted, documented, and that deficiencies are addressed in accordance with plant corrective action practices. /R3

REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS PROCEDURE No. EMERGENCY EXERCISES, DRILLS, TESTS 6of31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT 3.0 RESPONSIBILITIES (continued) 3.4 The Emergency Preparedness (EP) Supervisor is responsible for:

(continued)

6. Ensuring that EPIPs are reviewed through feedback from the following sources:

A. Daily use B. Drills and,exercises C. Actual events D. Training E. Biennial EPIP review as indicated on Data Sheet 3, EPIP Biennial Review

7. Ensuring biennial review of the Recovery Plan.

4.0 DEFINITIONS 4.1 Annual - Annual is defined as once per calendar year (January 1 through December 31) ~

4.2 Biennial - Biennial is defined as once per two calendar years.

4.3 Drill

1. Communications Tests and Drills - Communications tests involve the use of emergency communications equipment to verify operability. Communications drills involve use of emergency communications equipment to notify and transfer simulated emergency information to off-site governmental agencies.

2. Health Physics Drills - Health Physics drills test various tasks employed by that department during an emergency condition.

Health Physics drills are conducted semi-annually and one of the semi-annual drills may be incorporated into the radiological monitoring drill.

/R3

REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 7of31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4.3 Drill (continued)

Medical Emergency Drill - A medical emergency drill involves a simulated contaminated individual, with provisions for activation of the plant First Aid/Personnel Decontamination Team. Participation by local support services (i.e., ambulance and off-site medical treatment facility) is tested separately once per year or as part of the. annual medical drill. Medical Emergency Drills are conducted at least once every calendar year.

4. Radiological Monitoring Drill - Radiological monitoring drills include collection and analysis of air samples, testing of communications, and understanding of messages between Health Physics supervision and the off-site monitoring teams. A radiological monitoring drill will be conducted at least once every calendar year.

5. Emergency Response Facility (ERF) Drill - An ERF Drill demonstrates various emergency response capabilities including management and coordination of emergency response, accident assessment, protective action decision-making, and plant system repair and corrective action involving all or certain Emergency Response Facilities [Control Room, Technical Support Center (TSC), Operational Support Center (OSC), Emergency Operations Facility (EOF), and/or Emergency News Center (ENC)]. These drills are conducted at least four (4) times per calendar year and should be conducted approximately once each calendar quarter.

One of these drills is designed to satisfy the requirements of an exercise as defined below. /R3 Non-exercise drills provide an opportunity to consider accident management strategies. Supervised instruction can be permitted for these drills, with operating staff having the opportunity to resolve problems (success paths) rather than have controllers intervene.

Additionally, non-exercise drills may focus on on-site training objectives. /R3

k REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 8 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4A Exercise - An exercise is an event that tests the integrated capability of a major portion of the basic elements existing within the St. Lucie Plant Radiological Emergency Plan. An exercise is required biennially per 10 CFR 50. Off-site agency participation is required biennially.

Exercises are developed, scheduled, and conducted in a manner consistent with the regulations and guidance of 10 CFR 50 Appendix E, NUREG 0654, and other appropriate regulatory documents. Biennial exercises involving off-site agencies shall be conducted as a Site Area Emergency and should escalate to General Emergency. The exercise scenarios are varied such that all major elements of the Plan are tested at least every six (6) years. /R3 4.5 Letter of Agreement (LOA) - Support or assistance from outside agencies is established and maintained through Letters of Agreement or, in some instances, purchase orders/contracts.

Letters of Agreement are confirmed annually through correspondence, direct contact, or by telephone. Each agreement is renewed at least every three (3) years. Purchase orders/contracts are renewed as required.

4.6 Monthly - Monthly is defined as at least once each calendar month, being the first day of each month until the last unless otherwise specified.

4.7 Quarterly - Quarterly is defined as once per calendar quarter, with the quarters being January through March, April through June, July through September and October through December.

4.8 Semi-annual - Semi-annual is defined as twice per calendar year, with one time from January 1 to June 30 and one from July 1 to December 31.

4 REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: EMERGENCY EXERCISES, DRILLS, TESTS 9 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Protection Services Manager Instructions /R3

1. Review completed documentation of Attachment 1, EP Program Schedule, on an annual basis.

2. Ensure that State and County Emergency Management officials are

, made aware of non-emergency events that have a potential for media interest, A. Inform Emergency Planning (EP) of event B. Verify that EP has informed appropriate Emergency Management officials.

3. Ensure that State and County Emergency Management officials are made aware of the following on an annual basis:

A. Significant changes to the Emergency Plan/EPIPs.

B. Emergency Action Levels (EALs)

4. Maintain awareness of the status of the Alert and Notification System (ANS) operability.

A. Ensure that EP updates this information on the Plant Daily Status Report.

B. Ensure that degradations of the ANS are promptly addressed.

The Manager, Plant Services is responsible to maintain operability of the ANS per NBS-NPS-EP-WP-001, Alert and Notification System Testing, Maintenance and Engineering.

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: EMERGENCY EXERCISES, DRILLS, TESTS 10 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 Protection Services Manager Instructions (continued) /R3

5. Ensure the following is performed in support of exercises:

A. Schedule a date for the exercise in coordination with the primary State and County emergency response agencies.

B. Provide the opportunity for State and County response agencies to participate in an exercise.

C. Coordinate FPL efforts with other participating personnel, organizations, and agencies.

If the Federal Emergency Management Agency (FEMA) is evaluating State and County emergency response, Then ensure that the exercise scenario is developed within the timeframes specified by the regulations, as defined in Data Sheet 4, EP Annual Exercise Checklist.

D. Discuss and evaluate annual exercise performance with plant management, FPL controller/evaluators and principal participants.

END OF SECTION 5.1

REVISION NO.: PROCEDURE TITLE: PAGE:

3 IVIAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: EMERGENCY EXERCISES, DRILLS, TESTS 11 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Emergency Preparedness Supervisor

1. At the beginning of each calendar year:

A. Schedule the items on Data Sheet 1, EP Program Maintenance Checklist.

B. Record on Data Sheet 2, Emergency Plan 6 Year Element Demonstration, the data of the most recent performance.

1 ~ Ensure the year last performed date is less than 6 years from the current year. /R3 C. Schedule additional elements to be performed this year as necessary on Attachment 1, EP Program Schedule (Item 7).

D. Schedule procedure reviews from Data Sheet 3, EPIP Biennial Review on Attachment 1, EP Program Schedule.

2. Maintain awareness of status of completion of Attachment 1, EP Program Schedule.

A. Response actions performed as part of actual plant emergencies may be credited towards the following drills or tests:

integrated facility activation drill call out phone test/drill HP drill off-site agency communications drill medical drill B. Evolutions incorporated within a multiple scope drill/exercise may count as drill or test completion, as example:

HP drill, medical drill, or off-site communications drill as part of quarterly integrated facility activated drill or annual exercise.

REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 12 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.2 Emergency Preparedness Supervisor (continued)

3. Ensure the completion of the items on Data Sheet 2, Emergency Plan 6 Year Element Demonstration.

4. Ensure the completion of the items on Data Sheet 3, EPIP Biennial Review.

5. Ensure the completion of the items on Data Sheet 4, EP Annual Exercise Checklist.

/R3 END OF SECTION 5.2

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 13 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT DATA SHEET 1 EP PROGRAM MAINTENANCECHECKLIST (Page 1 of 3)

(YEAR)

Semi-Annual/Annual/Biennial EP Maintenance Items: INITIAL/ DATE g, 1. HP Drill (Semi-Annual)

A. (Jan-Jun) Date~~

B. (Jut-Dec) Date~~

2. Radiological Monitoring Drill (Annual)

A. Date~~

Biennial Exercise (Include Data Sheet 4, EP Exercise Checklist) /R3 A. Date~~

B. FEMA Evaluated (Even Years Only) Yes / No g, 4. Annual Offsite Agencies Communications Drill /R3 A. Date~~

5. Annual Unannounced Communications Drill /R3 A. Date~~

6. Annual Medical Drill /R3 A. Date~~

S OPS DATE DOCT CHECKLIST DOCN EPIP-13 sYs

'OMP COMPLETED ITM REV

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 14 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT DATA SHEET 1 EP PROGRAM MAINTENANCE CHECKLIST (Page 2 of 3)

(YEAR)

Two-Year/Annual/Semi-Annual EP Maintenance Items (continued): INITIAL/ DATE g, 7. Emergency Plan Review:

A. Emergency Plan Review (Annual)

B. Letters of Agreement Certification (Annual Confirmation/Triennial Renewal)

C. EPIP Review (Even years only)

(Include Data Sheet 3, EPIP Biennial Review)

8. Media Day (Annual)

9. Public Information Brochure (Annual)

10. Review and update Six Year Plan (Annual)

(Include Data Sheet 2, Emergency Plan 6 Year Element Demonstration) g, 11. Significant Emergency Plan/EPIP Changes, Emergency Action Levels (EALs) Meeting with State/County Emergency Management (Annual)

12. Hospital Training (Annual) g, 13. Off-site Training (Annual)

14. Recovery Plan Review (Biennial) /R3

k REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: EMERGENCY EXERCISES, DRILLS, TESTS 15 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT DATA SHEET 1 EP PROGRAM MAINTENANCECHECKLIST (Page 3 of 3)

(YEAR)

Two-Year/Annual/Semi-Annual EP Maintenance Items (continued): INITIAL/ DATE

15. Annual training review of ERO A. Solicit verification of annual ERO training completion from the Training Department.

B. Review training completion feedback and remove any ERO members not qualified.

16. EP Program Monthly Schedule (Attachment 1, EP Program Schedule)

Completed by Emergency Preparedness Supervisor Reviewed by Protection Services Manager

/R3 END OF DATA SHEET 1

l r

REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 16 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT DATA SHEET 2 EMERGENCY PLAN 6 YEAR ELEMENT DEMONSTRATION YEAR Year Last Year Next Date Completed/

Element Performed Scheduled initial Off hours staffing (6 P.M. - 4 A.M.)

Activation of Emergency News Center Use of fire control teams Use of medical support personnel Use of Security personnel for prompt access to,emergency equipment or support Use of one or more portions of backup communications for notification Field monitoring Capability for determining the magnitude and impact of the particular components of a release Capability for post-accident coolant sampling and analysis Assembly and accountability Initial recovery planning activities END OF DATA SHEET 2

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 17 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT DATA SHEET 3 EPIP BIENNIAL REVIEW (Page 1 of 2)

(YEAR)

I. Emergency Plan Implementing Procedures (Biennial)

PCR Revision No. Date Reviewed Y/N EPIP-00 Discovery and Identification of an Emergency Condition (including Chemical, Fire and Natural Emergencies)

EPIP-01 Classification of Emergencies EPIP-02 Duties and Responsibilities of the Emergency Coordinator EPIP-03 Emergency Response Organization Notification/Staff Augmentation EPIP-04 Activation and Operation of the Technical Support Center EPIP-05 Activation and Operation of the Operational Support Center EPIP-06 Activation and Operation of the Emergency Operations Facility EPIP-07 Conduct of Evacuations/Assembly EPIP-09 Offsite Dose Calculations EPIP-10 Off-Site Radiological Monitoring EPIP-11 Core Damage Assessment EPIP-12 Maintaining Emergency Preparedness-Radiological Emergency Plan Training EPIP-13 Maintaining Emergency Preparedness-Emergency Exercises, Drills, Tests and Evaluations HP-90 Emergency Equipment HP-200 HP Emergency Organization HP-201 Emergency Personnel Exposure Control

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRiLLS, TESTS 18 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT DATA SHEET 3 EPIP BIENNIALREVIEW (Page 2 of 2)

(YEAR)

I. Emergency Plan Implementing Procedures (Biennial) (continued)

I PCR Revision No. Date Reviewed Y/N HP-202 Environmental Monitoring During Emergencies HP-203 Personnel Access Control During Emergencies HP-204 In Plant Radiation and Contamination Surveys during Emergencies HP-205 Emergency Inplant Air Sampling HP-206 Analysis of Emergency Inplant Air Samples HP-207 Monitoring Evacuated Personnel During Emergencies HP-208 Personnel Decontamination During Emergencies COP-06.06 Guidelines for Collecting Post Accident Samples COP-06.11 Establishing Remote Laboratory for Analysis of Accident Samples

/R3 END OF DATA SHEET 3

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: EMERGENCY EXERCISES, DRILLS, TESTS 19 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT DATA SHEET 4 EP EXERCISE CHECKLIST /R3 (YEAR)

Exercise Items: INITIAL/ DATE Exercise Date Selection:

~~

1.

A. Evaluated Date

2. ERO Participant Notification

3. Scenario Development Personnel Assigned

4. Controllers/Evaluators Assigned

5. Exercise Objectives A. Protection Services Manager Approval /R3 B. Submitted to Licensing (75 Day NRC Submittal, Even years only)

6. Exercise Scenario A. Provided to Florida DEM (60 Day FEMA Submittal, Even years only)

B. Submitted to Licensing (45 Day NRC Submittal, Even years only)

7. Post Exercise Critique Date:~~

t'r, 8. Facility Review Group (FRG) Critique Report Review /R3 END OF DATA SHEET 4

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 20 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 1 of 12)

JANUARY (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

B.

C.

D.

F.

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 21 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 2 of 12)

FEBRUARY (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

C.

D.

F.

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No.: EMERGENCY EXERCISES, DRILLS, TESTS 22 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT ATTACHMENT1 EP,PROGRAM SCHEDULE (Page 3 of 12)

MARCH (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Quarterly Alert and Notification Status (Manager, Plant Services Report)

Quarter % Availability

3. Quarterly Emergency Response Directory Verification and Update

4. Quarterly Integrated Facility Activation Drill Drill Date

5. Quarterly Off-Hours Call Out Drill Drill Date

6. Quarterly Self-Assessment

7. Other Surveillances/Drills/Evolutions

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 23 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 4 of 12)

APRIL (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

B.

C.

D.

E.

F.

REVISION No.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 24 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 5 of 12)

, MAY (YEAR)

INITIAL/ DATE Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

C.

D.

E.

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 25 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 6 of 12)

JUNE (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Quarterly Alert and Notification Status (Manager, Plant Services Report)

Quarter % Availability

3. Quarterly Emergency Response Directory Verification and Update

4. Quarterly Integrated Facility Activation Drill Drill Date

5. Quarterly Off-Hours Call Out Drill Drill Date

6. Quarterly Self-Assessment

7. Other Surveillances/Drills/Evolutions

I

,I

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No. EMERGENCY EXERCISES, DRILLS, TESTS 26 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 7 of 12)

JULY (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

B.

D.

F.

l REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE No EMERGENCY EXERCISES, DRILLS, TESTS 27 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATIACHMENT 1 EP PROGRAM SCHEDULE (Page 8 of 12)

AUGUST (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

B.

C.

D.

E.

F.

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 28 of 31 AND EVALUATIONS E PIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 9 of 12)

SEPTEMBER (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Quarterly Alert and Notification Status (Manager, Plant Services Report)

Quarter % Availability

3. Quarterly Emergency Response Directory Verification and Update

4. Quarterly Integrated Facility Activation Drill Drill Date

5. Quarterly Off-Hours Call Out Drill Drill Date

6. Quarterly Self-Assessment

7. Other Surveillances/Drills/Evolutions

REVISION NO.: PROCEDURE TITLE: PAGE:

3 MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 29 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATTACHMENT1 EP.PROGRAM SCHEDULE (Page 10 of 12)

OCTOBER (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

C.

D.

E.

F.

t 4'

REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO. EMERGENCY EXERCISES, DRILLS, TESTS 30 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATTACHMENT1 EP PROGRAM SCHEDULE (Page 11 of 12)

NOVEMBER (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Other Surveillances/Drills/Evolutions:

A.

B.

C.

D.

E.

F.

t REVISION NO.: PROCEDURE TITLE: PAGE:

MAINTAININGEMERGENCY PREPAREDNESS-PROCEDURE NO.: EMERGENCY EXERCISES, DRILLS, TESTS 31 of 31 AND EVALUATIONS EPIP-13 ST. LUCIE PLANT ATIACHMENT 1 EP PROGRAM SCHEDULE (Page 12 of 12)

DECEMBER (YEAR)

INITIAL/ DATE

1. Emergency Response Facility Surveillance:

Date TSC OSC EOF

2. Quarterly Alert and Notification Status (Manager, Plant Services Report)

Quarter % Availability

3. Quarterly Emergency Response Directory Verification and Update

4. Quarterly Integrated Facility Activation Drill Drill Date

5. Quarterly Off-Hours Call Out Drill Drill Date

6. Quarterly Self-Assessment

7. Other Surveillances/Drills/Evolutions END OF ATTACHMENT1

Procedure No.

ST. LUCIE PLANT EPIP-02 EMERGENCY PLAN Current Rev. No.

FPL IMPLEMENTING PROCEDURE 4 SAFETY RELATED Effective Date:

11/08/99 Title DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ~ 8~

Responsible Department EMERGENCY PLANNING ~WIPdg Revision Summary Revision 4- Clarified records required, revised EC turnover process, changed "at the site" to "within the Owner Controlled Area", clarified use of field monitoring data for PARs, added guidance for completing the NRC notification form, and made editorial changes.

(J. R. Walker, 11/02/99)

Revision 3 - Added instruction (signoff) to ensure operators pick up emergency dosimetry (DRDs). (M. Gilmore, 09/08/99)

Revision 2 - Removed reference to the rotating maintenance shift supervisor from discussion/information related to the duty call supervisor. (J. R. Walker, 07/01/99)

PSL 0A0 PRGCEDtlRE PRODUCTION Revision FRG Review Date Approved By Approval Date S OPS DATE 12/1 5/97 J. Scarola 12/15/97 DOCT PROCEDURE Plant General Manager DOCN EPIP-02 SYS Revision FRG Review Date Approved By Approval Date COMP COMPLETED 11/02/99 ITM 4 11/02/99 R. G. West Plant General Manager N/A Designated Approver

f REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 2 of 65 E PIP-02 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ~ ~ ~ ~ 4

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS . 4 3.0 RESPONSIBILITIES 6 3.1 Nuclear Plant Supervisor ~ ~ 6 3.2 Emergency Coordinator . 6 4.0 DEFINITIONS ...

5.0 INSTRUCTIONS .......... 9 5.1 General Overview 9 5.2 Emergency Declaration Checklist 16 5.3 Unusual Event Checklist 18 5.4 Alert Checklist ........ ~....... ~ ~ . 23 5.5 Site Area or General Emergency Checklist 30 ATTACHMENTS ATTACHMENT 1 Initial Notification Flow . 39 ATTACHMENT2 State of Florida Notification Message Form for Nuclear Power Plants . 40 ATTACHMENT3 Directions for Completing the State of Florida Notification Message Form for Nuclear Power Plants .......... 41 ATTACHMENT4 Determination of Sectors Affected and Stability Class . 45 ATTACHMENT5 Determination of Protective Action Recommendations (PARS) o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 46 ATTACHMENT6 Protective Action Recommendations 52 ATTACHMENT7 NRC Event Notification Worksheet 53 ATTACHMENT7A Guidelines for Completing the NRC Event Notification Worksheet 55 /R4 ATTACHMENT8 Criteria for Evacuation 57

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 3 of 65 E PIP-02 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE ATTACHMENTS (continued)

ATTACHMENT9 Turnover Guidelines 58 ATTACHMENT 10 Re-entry Guidelines 60 ATTACHMENT 11 Basis for Exposure Limits for Emergency Response Personnel .. ~ 63

REVISION No.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 4of 65 EPIP-02 ST. LUCIE PLANT 1.0 PURPOSE This procedure provides guidance and instructions to be followed by the Emergency Coordinator when an emergency occurs that requires the implementation of the Radiological Emergency Plan for St. Lucie Plant.

NOTE One or more of the following symbols may be used in this procedure:

g Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, etc., and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENTDOCUMENTS 2.1 References

1. St. Lucie Plant Updated Final Safety Analysis Report (UFSAR)

Unit 1 and Unit 2 (Section 9.5.A.7.2)

2. St. Lucie Plant Radiological Emergency Plan (E-Plan)

3. St. Lucie Plant Physical Security Plan

4. St. Lucie Plant Safeguards Contingency Plan

5. E-Plan Implementing Procedures (EPIP 00-13)

6. 10 CFR 50, Domestic Licensing of Production and Utilization Facilities.

7. NUREG/BR-0150, Vol. 1, Response Technical Manual (USNRC).

8. NUREG-0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

REVISION No.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 5 of 65 E PIP-02 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS (continued) 2.1 (continued)

9. EPA 400-R-92-001, Manual of Protective Actions Guides and Protective Actions for Nuclear Incidents, October, 1991.

10. St. Lucie Plant General Policy PSL-110, Emergency Response.

2.2 Records Required A copy of the checklists or data generated by this procedure shall be maintained in the plant files in accordance with QI-17-PSL-1, Quality Assurance Records. Records include: /R4 1 ~ Emergency Class Checklists /R4

2. State Notification Form /R4

3. NRC Notification Form /R4

4. Protective Action Recommendation Worksheet /R4 2.3 Commitment Documents PMAI PM96-04-165, "ITR 96-006" (Unusual Event Declared Due to Dropped Rod)

2. NRC Inspection Report 91-01, Closure of IFls 89-31-03 and 89-31-01

3. PMAI PM96-09-185, Condition Report CR-96-1750 (Off-site Notification Using Commercial Phone)

/R4

4. PMAI PM96-05-233, (Off-site Notification Process).

5. Condition Report CR 96-2389, (Off-site Dose Calculations).

6. Condition Report CR 98-1536 (EC Responsibilities Remain in the Control Room).

~ )

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 6of65 E PIP-02 ST. LUCIE PLANT

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS (continued) 2.3 (continued)

7. PMAI PM98-09-006 (Control of NLOs Under E-Plan).

8. Condition Report CR 99-1406 (Field Operator Dosimetry Under E-Plan).

9. PMAI PM99-10-191, Condition Report CR 99-1656 (Quality Records, Downpower Guidance Due to Hurricanes). /R4

10. PMAI PM99-10-142, Condition Report CR 99-1647 (EC Turnover). /R4

11. PMAI PM99-09-016, (PARs Based on FMT Data, Completion of NRC Notification Form). /R4 3.0 RESPONSIBILITIES 3.1 The Nuclear Plant Supervisor (NPS) and the shift operating staff represent the first line of response to any developing emergency condition. The primary responsibility of the NPS is to control the condition as well as possible.

3.2 The NPS upon declaration of an emergency classification becomes the Emergency Coordinator (EC). The NPS remains the EC until the position is turned over.

Specific Responsibilities of the EC are:

Direction of the on-site emergency organization to bring the emergency under control.

Notification of off-site agencies within specific time limits as mandated by regulations.

Changes in Emergency Classification based on changing conditions.

Protective Action Recommendations (PARs) until turnover to the Recovery Manager.

Interfaces with the Nuclear Regulatory Commission (NRC) Reactor Safety Operations Coordinator (RSOC) when the NRC site team arrives at the TSC.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 7 of 65 EPIP-02 ST. LUCIE PLANT 4.0 DEFINITIONS 4.1 Owner Controlled Area Evacuation (= Site Evacuation) - The evacuation from the owner controlled area of all personnel except those required to place the plant in a safe condition, the Emergency Response Organization (ERO), and Security personnel to fulfill responsibilities for evacuation. /R4 4.2 Release (during any declared emergency)

1. Any effluent monitor increase of (approximately) 10 times or one decade above pre-transient values.

OR

2. Health Physics detecting airborne radioactivity levels in excess of 25% derived air concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

4.3 Notification Process - defined to include the following steps:

1. Declaration of the Emergency Class by the Emergency Coordinator.

2. Completion of the notification forms with the required information consistent with the declared Emergency Class.

3. Approval of the information by the Emergency Coordinator.

4. Transmission of the information on the notification forms within the time limits mandated by the regulations.

A. State and local agencies - within about 15 minutes of Declaration of the Emergency classification.

REVISION No.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 8 of 65 EPIP-02 ST. LUCIE PLANT 4.0 DEFINITIONS (continued) 4d3 (continued)

4. (continued)

NOTE N ~ i i d Nddi d d~iCh i It ~ i id and local agencies. The one hour time limit in 10 CFR 50.72 (a)(3) is to ensure timely NRC notification in cases where notification of State and local agencies is delayed or prolonged.

B. NRC - the licensee shall notify the NRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes (10 CFR 50.72 (a)(3)).

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 9of65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 General Overview

1. Upon Declaration of an emergency classification the NPS becomes the EC.

To ensure access to the EC for direction and control decisions and so that the responsibilities of the position can be, successfully completed, the EC position shall remain, initially in the affected Control Room and then in the Technical Support Center (TSC),

when it goes operational.

Prior to the TSC being operational, the duties and responsibilities of the EC, while a Control Room position, may be turned over to another qualified EC:

~ If both Units are in classified events, the EC should locate in the Unit's Control Room with the highest classified event. If the site is in a dual Unit event, the EC should locate in the Unit 1 Control Room (due to proximity to the TSC).

If the TSC is activated, Then the EC position is turned over to an EC qualified member of plant management and the position relocated to the TSC. The prospective EC receives a turnover (refer to Attachment 9, Turnover Guidelines) from the Control Room EC and then reports to the TSC. Following verification of TSC operational readiness, the prospective EC accepts EC responsibility from the Control Room EC. The TSC EC may temporarily turnover responsibility to the TSC OPS Coordinator as the need arises.

2. To meet the above responsibilities, plus others described in this procedure, the EC will likely need to delegate many tasks.

Although delegated, the completion of these tasks is still the responsibility of the EC.

IR4

REVISION NO.: PROCEDURETITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 10 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 General Overview

2. (continued)

The EC shall not dele ate the following responsibilities prior to Emergency Operations Facility (EOF) being declared operational:

A. Classification of the emergency.

B. The decision to notify state and local authorities and the content of those notifications.

C. Recommendation of protective actions for the public.

Once the EOF is operational and proper turnover has been conducted, the Recovery Manager (RM) will assume responsibility for off-site notifications to the state and local authorities and for recommending protective actions.

3. Order of Succession If the NPS is incapacitated, Then the EC shall be (in order of succession):

A. Assistant Nuclear Plant Supervisor (ANPS) (from the affected unit)

B. Nuclear Watch Engineer (NWE)

C. Any other member of the plant staff with an active SRO license.

REVISION No.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 11 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 General Overview (continued)

4. Off-site Notification A. If due to rapidly degrading conditions, Emergency Class escalation is known to be necessary, prior to completion of the notification process, Then:

Provide the state and local authorities with the initial notification information by, completing steps 1-5 of the State of Florida Notification Message Form.

Terminate the phone call by informing the state and local authorities that a new notification form will be transmitted within 15 minutes.

OR Begin transmitting the new notification form describing the conditions associated with the upgraded Emergency Class.

Ensure that the NRC is informed following notification of the state and local authorities but no later than 60 minutes from the initial Emergency Class declaration (an open line will be established with the NRC at an Alert or higher Emergency

Class).

B. If one unit is in a classified event and the same or the other unit enters into an event where the same or lesser emergency class would apply, a new classification should NOT be declared. The event should be issued as an update at the earliest practical time.

C. If one unit is in a classified event and the other unit enters into a more severe event in which a higher emergency class would apply, the new classification would be declared and promptly, within the regulatory time limits, issued to the state, counties and NRC.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 12 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 General Overview (contiriued)

5. Off-site Communication Content During initial notification, the information provided in describing the emergency should be brief yet descriptive enough for the off-site authorities to gain an understanding of the event. It should be clear from the incident description which Emergency Action Level (EAL) has necessitated the emergency declaration. Wording should be as non-technical as possible with no abbreviations (e.g.,

reactor coolant pump instead of RCP). Potential for degradation of plant conditions is always of interest to the off-site authorities.

Proper, accurate information will preclude the need for follow-up information or numerous questions from off-site authorities.

6. Off-site Communication Updates Updates to off-site authorities may be more detailed than initial notifications, but should remain in layman's terms. The state and local authorities should be updated upon any significant change in plant status (e.g., start or termination of a release, loss of major plant equipment, loss of off-site or on-site power, etc.) in addition, routine updates should be made every 60 minutes for an Alert or higher emergency declaration. The update frequency may be changed if agreed to by off-site authorities and FPL, in advance.

Long, detailed explanations of plant systems or reactor theory should be avoided. If prompted for this kind of information by the State Duty Officer, refer him to the Nuclear Division Duty Officer (NDDO). /R4 If erroneous information is transmitted to off-site authorities and the error is discovered prior to event termination, a correction should be provided in an update. The need for and urgency of providing the update is dependent upon the importance of the error.

If erroneous information is transmitted to off-site authorities, and the error is discovered after event termination, the Licensing Department should be consulted on the need and method for contacting the off-site authorities with corrected information.

REVISION No.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 13 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 General Overview (continued)

7. Emergency Follow-Up Information All incoming calls should come via the State Warning Point (SWP) over the HOT RING DOWN (HRD) phone. If the HRD is inoperable, the SWP may use commercial telephone or ESATCOM.

If an off-site authorities contacts the Plant without going through the SWP, request that they contact SWP. SWP shall verify that the agency calling is a risk county or the Department of Health (DOH) and shall notify other county and state authorities of the updated information, thus reducing the number of calls that may be directed to the Plant.

8. Protective Action Recommendations Protective Action Recommendations (PARs) should be made utilizing all of the available data. This includes plant status and/or off-site dose projections. The most conservative recommendations should be made.

9. General Emergency - Minimum PARs In any case where a GENERAL EMERGENCY has been declared, the minimum PAR shall be: Shelter all people within a 2 mile radius and out to 5 miles in the downwind sectors.

10. Security Event A. Site security and Local Law Enforcement (LLEA) will take the lead in response to a Security Event in accordance with the Security Plan.

B. Based on the nature of the Security Event and as conditions warrant, the Emergency Coordinator may delay, postpone or institute special arrangements concerning, but not limited to:

Emergency Response Facility (ERF) activation Local or Site Evacuation Site or Radiation Controlled Area (RCA) access Operator field activities Unit shutdown

1 REVISION No.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 14 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 General Overview (continued)

10. Security Event (continued)

C. Intruder General Emergency - minimum PARs If the GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum PAR shall be: Evacuate all people within a 2 mile radius from the plant and out to 5 miles in the downwind sectors. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.

D. Watch Relief The EC shall grant permission for watch relief, including his own, only when it is safe in his judgement to do so.

11. Severe Weather Considerations VI0 If a hurricane warning is in effect, and either one or both Unit(s) is/are in Mode 1, 2 or 3, Then use the following criteria for unit shutdown: /R4 A. For storms projected to reach a Category 1 or 2, the unit(s) shall be placed in HOT STANDBY (Mode 3) or below at least two (2) hours before the projected onset of sustained hurricane force winds within the Owner Controlled Area and both units shall remain off-line for the duration of the hurricane force winds (or restoration of reliable offsite power). /R4 B. For storms projected to reach Category 3, 4 and 5 prior to landfall, the units shall be shut down to a temperature less than 350 degrees T ave. at least two (2) hours before the projected onset of sustained hurricane force winds within the Owner Controlled Area and both units shall remain off-line for the duration of the hurricane force winds (or restoration of reliable offsite power). /R4 C. Establish an acceptable update frequency with state and local officials.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 15 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) 5.1 General Overview (continued)

12. Drill Messages During exercises, drills, or tests, ALL MESSAGES shall begin and end with THIS IS A DRILL or THIS IS AN EXERCISE or THIS IS A TEST.

END OF SECTION 5.1

I REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 16 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.2 Emergency Declaration Checklist CAUTION State and/or local authorities shall be notified within 15 minutes of declaration of the emergency classification.

NOTE Steps should be performed in the order presented. When conditions warrant, steps may be performed out of sequence. PA announcements are provided as a guideline. Actual announcements may vary from the text provided.

1. The NPS shall declare the emergency to the Control Room staff and formally announce that he/she is the Emergency Coordinator (EC).

2. Notify plant personnel using Gai-tronics and boost function.

Slit T h i Supervisor report to the Control lAdi Room idO "Attention all plant personnel, Unit ~1~2 has declared lyC immediately.

I~I All other plant personnel be aware and listen for further instructions. Limit radio and phone use until further notice."

REVISION NO.: PROCEDURE TITLE: PAGE:

,4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 17 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.2 Emergency Declaration Checklist (continued)

NOTE The Duty Call Supervisor (DCS) a specifically designated and trained is supervisor responsible for assisting the Emergency Coordinator (EC) in making notifications and calls to the Emergency Response Organization (ERO).

3. Complete the appropriate Emergency Classification Section Checklist (attached):

A. Section 5.3 (Notification of) Unusual Event Checklist B. Section 5.4 Alert Checklist C. Section 5.5 Site Area or General Emergency Checklist END OF SECTION 5.2

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 18 of 65 PROCEDURE NO.:

EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.3 Unusual Event Checklist Message Date

¹

~~

I NOTE

~ Complete a new checklist for each notification made during an Unusual Event emergency.

~ The terms "release" and "notification" have specific definitions in

'ection 4.0 of this procedure.

1. If a radioactive release has occurred or is in progress, Then notify Chemistry to promptly perform off-site dose calculations per EPIP-09, Off-site Dose Calculations, and report results to the EC. If Chemistry is unavailable, Then have the DCS call out a TSC Dose Assessor.

2. If evacuation of an area is necessary, Then initiate a local evacuation in accordance with EPIP-07, Conduct of Evacuations/Assembly. (Refer to Attachment 8, Criteria for Evacuation.)

3. Mobilize emergency response personnel to respond as required using Gai-tronics and boost function.

NOTE Attachment 3, Directions for Completing the State of Florida Notification Message Form for Nuclear Power Plants, may be helpful in performing the following step. The Duty Call Supervisor (DCS) may perform this step.

4. Prepare the State of Florida Notification Message Form (Attachment 2) including Protective Action Recommendations.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 19 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.3 Unusual Event Checklist (continued)

/R4 NOTE If Emergency Class escalation is known to be necessary, Then terminate the notification after line 5 of the State of Florida Notification Message Form.

OR Begin transmitting the information from the new notification form describing the conditions associated with the upgraded emergency class.

5. Notify State Warning Point (SWP) within 15 minutes of the declaration of the emergency. This may be accomplished by the DCS.

A. Using the State HOT RING DOWN (HRD)

Phone, dial 100.

B. When the State answers, provide the information from the State of Florida Notification Message Form.

C. If the HRD is inoperable, Then go to the Alternate Notification Methods at the end of this checklist.

6. Ensure notification of Plant Management, Security and the Nuclear Division Duty Officer (NDDO). This may be accomplished by the DCS.

7. Prepare the NRC Event Notification Worksheet.

8. Notify the NRC via the Emergency Notification System (ENS) phone immediately after notification of the state and counties. This shall be accomplished within one hour. This may be accomplished by the DCS.

/

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 20 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.3 Unusual Event Checklist (continued)

/R4

9. Reassess corrective and protective actions. Verify assigned activities are under way and proper progress is being made. Reassign personnel and emergency teams as necessary.,

10. Continue to assess conditions and review any changes against the Emergency Action Levels (EALs) in EPIP-01, Classification of Emergencies.

11. Reclassify the event as necessary and follow instructions in the appropriate checklist.

NOTE New notification forms shall be completed for all updates.

12. If the classification is unchanged but a significant change in plant conditions has occurred, Then start a new Unusual Event Checklist, prepare notification forms and make the appropriate notifications as soon as possible.

13. If the event can be terminated, Then complete the notification forms (State, NRC) and notify the following:

State Warning Point Plant Management Security NDDO NRC

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 21 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.3 Unusual Event Checklist (continued)

/R4

14. Alternate Notification Methods (recommended format): /R4 NOTE Use of the commercial telephone as an alternate notification method requires callback verification from the State Warning Point. Use of ESATCOM or Local Government Radio as an alternate notification method should include a callback verification number if available (e.g., cellular phone).

A. Alternate 1 - Commercial phone Call the State Warning Point using the phone number in the St. Lucie Plant Emergency Response Directory (ERD). Announce "This is St. Lucie Unit Nuclear Plant with an emergency declaration. IV!y callback number is Hang up the phone and standby for the callback.

When the State Warning Point gives the go-ahead, provide the information from the State of Florida Notification Message Form.

Request callback to verify that State Warning Point has notified St. Lucie and Martin Counties and the Bureau of Radiation Control.

B. Alternate 2 - ESATCOM Hold down the button on the handset and wait 3-5 seconds to hear a beep before you start talking.

This must be done each time you talk.

Announce "State Warning Point, this is St. Lucie Unit," then release the button in order to listen.

When the State Warning Point acknowledges, announce "State Warning Point, this is St. Lucie Ui .~11 i p

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 22 of 65 E PIP-02 ST. LUCIE PLANT 5d0 INSTRUCTIONS (continued) TIME / INIT 5.3 Unusual Event Checklist (continued)

/R4

14. Alternate Notification Methods (recommended format): (continued)

B. Alternate 2 - ESATCOM (continued)

When the State Warning Point gives the go-ahead, provide the information from the State of Florida Notification Message Form.

Announce "St. Lucie clear" at the end of the conversation.

C. Alternate 3 - Local Government Radio (LGR) communication to St. Lucie and Martin County Emergency Operations Centers (EOCs) with relay to the State Warning Point.

On channel 2, contact the county EOCs by depressing the transmit button and announcing "St. Lucie County EOC, this is St. Lucie Nuclear Unit . Over."

When St. Lucie County replies, direct them to standby while you contact Martin County.

When both counties are online, announce "Martin and St. Lucie County EOCs, this is St. Lucie Nuclear Unit

~ i i ~ ~I'll d i

ggg d

ig Florida Notification Message Form information when you are ready to copy. Over."

When the counties give the go-ahead, provide the information from the State of Florida Notification Message Form.

End the conversation by announcing "This is St. Lucie Unit, KNGR 874, over and out."

END OF SECTION 5.3

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 23 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.4 Alert Checklist Date Message 4

~~

NOTE

~ For assistance with control of Non-licensed Operators (NLOs), refer to:

Attachment 10, Re-entry Guidelines.

a Attachment 11, Basis for Exposure Limits for Emergency Response Personnel.

~ Complete a new checklist for each notification made during an Alert emergency.

~ The terms "release" and "notification" have specific definitions in Section 4.0 of this procedure.

1. If a radioactive release has occurred or is in .

progress, Then notify Chemistry to promptly perform off-site dose calculations per EPIP-09, Off-site Dose Calculations, and report results to the EC. If Chemistry is unavailable, Then have the DCS call out a TSC Dose Assessor.

2. If evacuation of an area is necessary, Then initiate a local evacuation in accordance with EPIP-07, Conduct of Evacuations/Assembly. (Refer to Attachment 8, Criteria for Evacuation.)

3. Notify plant personnel of the emergency declaration using Gai-tronics and boost function (N/A for updates).

"Attention all plant personnel, Unit ~1/ 2 has declared an ALERT."

"All emergency response organization personnel report at once to your assigned emergency response facility."

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 24 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.4 Alert Checklist (continued)

/R4

3. (continued)

"All non-emergency response organization personnel report to your normal work location or contact your supervisor."

Repeat the announcement.

4. If a release is in progress, Then review personnel access with Health Physics personnel and notify Security personnel with any special instructions (N/A for updates).

5. Notify the DCS to initiate staff augmentation in accordance with EPIP-03, "Emergency Response Organization Notification/ Staff Augmentation." (N/A for updates.)

NOTE Attachment 3, Directions for Completing the State of Florida Notification Message Form for Nuclear Power Plants, may be helpful in performing the following step. The DCS may perform this step.

6. Prepare the State of Florida Notification Message Form (Attachment 2) including Protective Action Recommendations.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 25 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.4 Alert Checklist (continued)

/R4 NOTE If Emergency Class escalation is known to be necessary, Then terminate the notification after line 5 of the State of Florida Notification Message Form.

OR Begin transmitting the information from the new notification form describing the conditions associated with,the upgraded emergency class.

7. Notify State Warning Point (SWP) within 15 minutes of declaration of the emergency. This may be accomplished by the DCS.

A. Using the State HOT RING DOWN (HRD)

Phone, dial 100.

B. When the State answers, provide the information from the State of Florida Notification Message Form.

C. If the HRD is inoperable, Then go to the Alternate Notification Methods at the end of this checklist.

8. Verify notification of Plant Management, Security and the NDDO. This may be accomplished by the DCS.

9. Prepare the NRC Event Notification Worksheet.

10. Notify the NRC via the Emergency Notification System (ENS) phone immediately after notification to the State and counties. This shall be accomplished within one hour. This may be accomplished by the DCS.

REVISION No.: PROCEDURE TITLE:

DUTIES AND RESPONSIBILITIES OF

'AGE:

PROCEDURE NO THE EMERGENCY COORDINATOR 26 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.4 Alert Checklist (continued)

/R4

11. Initiate the Operations Department Accountability Aid for both Unit 1 and Unit 2 and provide this list to the TSC when requested (N/A for updates).

12. Ensure Operations field personnel have returned to the Control Room to obtain emergency Electronic Personal Dosimetry (EPD) from the HP Kit. /R4

13. Reassess corrective and protective actions. Verify assigned activities are under way and proper progress is being made. Reassign personnel and emergency teams as necessary.

14. Continue to assess conditions and review any changes against the Emergency Action Levels (EALs) in EPIP-01, Classification of Emergencies.

15. Reclassify the event as necessary and follow instructions in the appropriate checklist.

NOTE New notification forms shall be completed for all updates.

16. If the classification is unchanged but a significant change in plant conditions has occurred, Then start a new Alert Checklist, prepare notification forms and make the appropriate notifications as soon as possible.

17. If a State/Local notification has not been completed in the last 60 minutes, Then provide a routine update. Start a new notification form and make the appropriate notifications.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 27 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.4 Alert Checklist (continued)

/R4

18. If the event can be terminated, Then complete the notification forms (State, NRC) and notify the following:

State Warning Point Plant Management Security NDDO NRC

19. Alternate Notification Methods (recommended format): /R4 NOTE Use of the commercial telephone as an alternate notification method requires callback verification from the State Warning Point. Use of ESATCOM or Local Government Radio as an alternate notification method should include a callback verification number if available (e.g., cellular phone).

A. Alternate 1 - Commercial phone Call the State Warning Point using the phone number in the St. Lucie Plant Emergency Response Directory (ERD). Announce "This is St. Lucie Unit Nuclear Plant with an emergency declaration. My callback number is Hang up the phone and standby for the callback.

When the State Warning Point gives the go-ahead, provide the information from the State of Florida Notification Message Form.

Request callback to verify that State Warning Point has notified St. Lucie and Martin Counties and the Bureau of Radiation Control ~

REVISION No.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE No THE EMERGENCY COORDINATOR 28 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continIjed) TIME / INIT 5.4 Alert Checklist (continued)

/R4

19. Alternate Notification Methods (recommended format): (continued)

B. Alternate 2 - ESATCOM Hold down the button on the handset and wait 3-5 seconds to hear a beep before you start talking.

This must be done each time you talk.

Announce "State Warning Point, this is St. Lucie Unit," then release the button in order to listen.

When the State Warning Point acknowledges, U ~li announce "State Warning Point, this is St. Lucie I i . p ~i1t When the State Warning Point gives go-ahead, provide the information from the State of Florida Notification Message Form.

Announce "St. Lucie clear" at the end of the conversation.

C. Alternate 3 - Local Government Radio (LGR)

, communication to St. Lucie and Martin County Emergency Operations Centers (EOCs) with relay to the State Warning Point.

On channel 2, contact the county EOCs by depressing the transmit button and announcing "St. Lucie County EOC, this is St. Lucie Nuclear Unit . Over." When St. Lucie County replies, direct them to standby while you contact Martin County.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 29 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.4 Alert Checklist (continued)'9.

/R4 Alternate Notification Methods (recommended format): (continued)

C. (continued)

When both counties are online, announce "Martin and St. Lucie County EOCs, this is St. Lucie Ui

~

d I

I kg~IN Cihgty transmit State of Florida Notification Message Form information when you are ready to copy.

Over."

When the counties give the go-ahead, provide the information from the State of Florida Notification Message Form.

End the conversation by announcing "This is St. Lucie Unit, KNGR 874, over and out."

END OF SECTION 5.4

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 30 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist Message Date

¹

~ /

NOTE

~ For assistance with control of Non-licensed Operators (NLOs), refer to:

~ Attachment 10, Re-entry Guidelines a Attachment 11, Basis for Exposure Limits for Emergency Response Personnel

~ Complete a new notification form for each notification made during a Site Area Emergency or General Emergency.

~ The terms "release" and "notification" have specific definitions in Section 4.0 of this procedure.

If a radioactive release has occurred or is in progress, Then notify Chemistry to promptly perform off-site dose calculations per EPIP-09, Off-site Dose Calculations, and report results to the Emergency Coordinator. If Chemistry is unavailable, Then have the DCS call out a TSC Dose Assessor.

2. If a radioactive release has occurred or is in progress, Then identify wind direction.

NOTE When the EOF is declared operational AND the Recovery Manager has assumed responsibility, Then notifications and PARs will be performed from the EOF.

3. If a release is in progress, Then review personnel access with Health Physics personnel and notify Security personnel with any special instructions (N/A for updates).

4. If the site is NOT evacuated, Then sound the Site Evacuation Alarm.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 31 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4 NOTE To provide a clear announcement, the following step should be read and the content of the announcement determined prior to starting the announcement.

5. Make the necessary plant announcement using Gai-tronics and boost function:

A. Announce the following (N/A for updates):

"Attention all plant personnel, ~Unit 1 1 2 ttas declared a SITE AREA EMERGENCY /

GENERAL EMERGENCY ."

B. If the Technical Support Center, Operational Support Center and Emergency Operations Facility are NOT activated, Then announce the following:

"AII emergency response organization personnel report at once to your assigned emergency response facility."

NOTE An alternate off-site Assembly Area at the Jensen Beach parking area is available if the wind direction is from 146'o 270'.

C. If the site is NOT evacuated and there is NOT or has NOT been a radiological release, Then announce the following:

"All non-emergency response organization personnel are to commence evacuation of the Owner Controlled Area, report to your vehicle and proceed to your homes."

OR

REVISION No.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 32 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4

5. (continued)

C. (continued)

If the site is NOT evacuated and there is or has been radiological release, Then announce the following:

"All non-emergency response organization personnel are to commence evacuation of the Owner Controlled Area. Persons leaving the site are to proceed

~NhlS h yt 1 p~l Ja cee Park / Jensen Beach Parkin Area for contamination check, accountability and further instructions."

6. REPEAT steps 4 and 5 above.

7. If the site is NOT evacuated, Then order Security to ensure evacuation of the Owner Controlled Area and to report personnel accountability as soon as possible.

8. If the TSC and OSC are NOT activated, Then notify the DCS to initiate staff augmentation in accordance with EPIP-03, Emergency Response Organization Notification/Staff Augmentation (N/A for updates).

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 33 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4 CAUTION PARs are always required for General Emergencies and may be required for lesser emergencies.

NOTE Attachment 3, Directions for Completing the State of Florida Notification Message Form for Nuclear Power Plants, may be helpful in performing the following step. The DCS may perform this step.

9. Prepare the State of Florida Notification Message Form (Attachment 2).

A. Include PARs.

B. If the site has been evacuated since the last notification, Then include the evacuation route and offsite Assembly Area location (if utilized) in the incident description.

NOTE If Emergency Class escalation is known to be necessary, Then terminate the notification after line 5 of the State of Florida Notification Message Form.

OR Begin transmitting the information from the new notification form describing the conditions associated with the upgraded emergency class.

10. Notify State Warning Point (SWP) within 15 minutes of declaration of the emergency. This may be accomplished by the DCS.

A. Using the State HOT RING DOWN (HRD)

Phone, dial 100.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 34 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4

10. (continued)

B. When the State answers, provide the information from the State of Florida Notification Message Form.

'. If the HRD is inoperable, Then go to the Alternate Notification Methods at the end of this checklist.

11. Verify notification of Plant Management, Security and NDDO. This may be accomplished by the DCS.

12. Prepare the NRC Event Notification Worksheet.

13. Notify the NRC via the Emergency Notification System (ENS) phone immediately after notification of the State and counties. This shall be accomplished within one hour. This may be accomplished by the DCS.

14. Initiate the Operations Department Accountability Aid for both Unit 1 and Unit 2 and provide this list to the TSC when requested (N/A for updates).

15. Verify with Security that the evacuation of the Owner Controlled Area has been completed and all personnel have been accounted for (N/A for updates).

16. Complete notification forms and make notification to State Warning Point and NRC when the evacuation is complete (N/A for updates) ~

17. Ensure Operations field personnel have returned to the Control Room or OSC to obtain emergency Electronic Personal Dosimetry (EPD). /R4

t REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE No THE EMERGENCY COORDINATOR 35 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4

18. Direct that all Non-licensed Operators (NLOs), from both Units, report to the OSC (when operational) following evacuation of the Owner Controlled Area (N/A for updates).

19. Reassess corrective and protective actions. Verify assigned activities are under way and proper progress is being made. Reassign personnel and emergency teams as necessary.

20. Continue to assess conditions and review any changes against the Emergency Action Levels (EALs) in EPIP-01, Classification of Emergencies.

21. Upgrade to a General Emergency, as necessary.

Start new checklist upon upgrading.

22. If the classification is unchanged but a significant change in plant conditions has occurred AND the EOF is NOT operational, Then start a new Site Area or General Emergency Checklist, prepare notification forms and make the appropriate notifications as soon as possible.

CAUTION Only the Recovery Manager (RM) can authorize the downgrading of emergency classifications from Site Area or General Emergency.

NOTE If the EOF is not operational at this time, contact Recovery Manager for information concerning turnover of notification and PAR responsibilities.

23. If the event can be downgraded or terminated, Then discuss with Recovery Manager.

REVISION No.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 36 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4 NOTE New notification forms shall be completed for all updates.

24. If an off-site notification has not been completed in the last 60 minutes AND the EOF is NOT operational, Then provide a routine update. Start a new notification form and make the appropriate notifications.

25. Alternate Notification Methods (recommended format): /R4 NOTE Use of the commercial telephone as an alternate notification method requires callback verification from the State Warning Point. Use of ESATCOM or Local Government Radio as an alternate notification method should include a callback verification number if available (e.g., cellular phone).

A. Alternate 1 - Commercial phone Call the State Warning Point using the phone number in the St. Lucie Plant Emergency Response Directory (ERD).

Announce "This is St. Lucie Unit Nuclear Plant with an emergency declaration. My callback number is Hang up the phone and standby for the callback. When the State Warning Point gives the go-ahead, provide the information from the State of Florida Notification Message Form.

Request callback to verify that State Warning Point has notified St. Lucie and Martin Counties and the Bureau of Radiation Control.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 37 of 65 EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4

25. Alternate Notification Methods (recommended format): (continued)

B. Alternate 2 - ESATCOM Hold down the button on the handset and wait 3-5 seconds to hear a beep before you start talking. This must be done each time you talk.

Announce "State Warning Point, this is St. Lucie Unit," then release the button in order to listen.

When the State Warning Point acknowledges, announce "State Warning

~lp Point, this is St. Lucie Unit p

When the State Warning Point gives go-ahead, provide the information from the State of Florida Notification Message Form.

Announce "St. Lucie clear" at the end of the conversation.

C. Alternate 3 - Local Government Radio (LGR) communication to St. Lucie and Martin County Emergency Operations Centers (EOCs) with relay to the State Warning Point.

On channel 2, contact the county EOCs by depressing the transmit button and announcing "St. Lucie County EOC, this is St. Lucie Nuclear Unit . Over." When St. Lucie County replies, direct them to standby while you contact Martin County.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 38 of 65 E PIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS (continued) TIME / INIT 5.5 Site Area or General Emergency Checklist (continued)

/R4

25. Alternate Notification Methods (recommended format): (continued)

C. (continued)

When both counties are online, announce "Martin and St. Lucie County EOCs, this is St. Lucie Nuclear Unit declaring a

~ i p I am standing by to transmit State of Florida Notification Message Form information when you are ready to copy. Over."

When the counties give the go-ahead, provide the information from the State of Florida Notification Message Form.

End the conversation by announcing "This is St. Lucie out."

Unit, KNGR 874, over and END OF SECTION 5.5

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 39 Of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT1 INITIALNOTIFICATION FLOW (Page 1 of 1)

EMERGENCY COORDINATOR STATE OF FLORIDA DUTY PLANT DIVISION OF CALL GENERAL EMERGENCY SUPERVISOR MANAGER MANAGEMENT STATE OF FLORIDA FPL EMERGENCY DOH BUREAU OF (1)

RESPONSE

RADIATION (5) ORGANIZAT(ON CONTROL EPZ COUNTIES EMERGENCY

RESPONSE

DIRECTORS USNRC (2)

OPERATIONS CENTER (5)

LOCAL SUPPORT (3) (4) ON-SHIFT

1. FIRE/AMBULANCE EMERGENCY (5) RESPONSE

2. MEDICAL ORGANIZATION (1) Vla State Hot Ring Down Telephone (HRD)

Legend:

Primary Notification Pathway (2) Via Emergency Notification System (ENS)

Alternate

~ Notification Pathway (3) Medical & Rre Emergencies Only, As Needed (4) Via Plant Public Address System (PA)

(5) May be performed by the Duty Call Supervisor.

(EPIP-024. WPG)

END OF ATTACHMENT1

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 40 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT2 STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 1 of 1) 0 THIS IS A DRILL 0 THIS IS AN ACTUALEMERGENCY A. Time/Date: (Initiated) B. Reportedby: (Name/litle)

C. Message Number: D. From: 0 Control Room CI TSC CI EOF SITE: CI ST. LUCIE UNIT 1 0 ST. LUCIE UNIT2 ACCIDENT CLASSIFICATION 0 Notification of Unusual Event 0 Site Area Emergency 0 Alert 0 General Emergency

4. CURRENT EMERGENCY DECLARATION

5. INCIDENT DESCRIPTION OR UPDATE'ime:

INJURIES A.CI Contaminated B. 0 Non~ntaminated RELEASE STATUS:

A. 0 No release(Go toltem11) C. Cl AReleaseisoccurring-expectedduration B. Cl Potential (Possible) Release D. Cl A Release occurred, but stopped-duration RELEASE RATE (calculated as per EPIP49)

A. 0 NOBLE GASES: Curies per second 0 Measured 0 Default B. 0 IODINES: Curies per second D Measured 0 Default C. 0 Release within normal operating limits g

If TYPE OF RELEASE (Blanks are for specific IS nuctides, if available, i.e, l-131, Cs-137, etc.)

A. 0 Radioactive gases C. 0 Radioactive liquids B. Cl Radioactive airborne particulates D. 0 Other 10."* PROJECTED OFFSITE DOSE RATE (calculated as per EPIP.09)

DISTANCE THYROID DOSE RATE (CDE) TOTAL DOSE RATE (TEDE) 1 Mile (Site boundary) mrem/hr mr em/hr 2 Miles mrem/hr mr em/hr 5 Miles mrem/hr mrem/hr 10 Miles mrem/hr mrem/hr METEOROLOGICAL DATA (at 10 meters)

A. Wind direction (from) degrees C. Wind speed mph B. Sectors affected D. Stability class (from Attachment 4) (from Attachment 4) 12 UTILITYRECOMMENDED PROTECTIVE ACTIONS (from EPIP+2)

A. 0 No recommendations at this time. If messages refer to 360'adius, B. 0 Notify the public to take the following protective actions:

use the word AU under sectors.

MILES NO ACTION SHELTER/SECTORS EVACUATE/SECTORS 0-2 2-5 5-10 13.

14.

15.

HAS EVENT BEEN TERMINATEDV A.

EC Approval:

MESSAGE RECEIVED BY Name:

0 NO B. 0 YES Time:

Time:

Return to applicable checklist (UE, ALERT, SITE AREA/GENERAL) and start from last completed step.

Date:

~~

If Emergency Class escalation is knovm to be necessary, Then add, A new notification form will be transmitted within 15 minutes; go to Une 14.

"This information may not be available on initial notifications.

END OF ATTACHMENT2

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE No THE EMERGENCY COORDINATOR 41 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT3 DIRECTIONS FOR COMPLETING THE STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 1 of 4)

Starting at the top of the form, check either "THIS IS A DRILL" or "THIS IS AN ACTUAL EMERGENCY."

ITEM ENTRY 1A Time/Date - Enter the time and date when the transmission of data beceins.

1B ~Rdb ~ E <<1 dii~l ft p t ling information.

1C ~MN being made.

1 -E <<h q i~I 1 fh ~

The facility from which the notifications are being made may change as the event progresses; however, the number will remain sequential throughout the event.

1D From - Check the facility from which the notification is being made.

SITE - Check the unit that is making the emergency declaration. If both units are affected, check both blocks.

ACCIDENT CLASSIFICATION - Check the current emergency classification declared.

CURRENT EMERGENCY DECLARATION - Enter the time and date when the current emergency classification was declared.

INCIDENT DESCRIPTION OR UPDATE - Enter a brief description of the initiating conditions for the emergency classification declared and any other current information regarding significant events which have occurred since the last notification was made. The information provided should be descriptive enough for the offsite agencies to understand which Emergency Action Level (EAL) has necessitated the emergency declaration. If practical, use the wording directly from the EAL.

Wording should be non-technical, avoiding specific details such as electrical bus numbers, etc. The use of abbreviations and acronyms should be avoided. If possible, indicate if plant conditions are currently improving, stable, or degrading.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 42 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT3 DIRECTIONS FOR COMPLETING THE STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 2 of 4)

ITEM 'NTRY INJURIES - If there are no injuries, enter "none" in the blanks for 6A and 6B. If there are injuries, check the appropriate block and enter the number of contaminated people in the blank beside 6A, and number of non-contaminated people in the blank beside 6B.

RELEASE STATUS - A release (during any declared emergency) is defined as:

a. Any effluent monitor increase of (approximately) 10 times or one decade above pre-transient values, OR

b. Health Physics detecting airborne radioactivity levels in excess of 25% derived air concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

7A No Release Go to Item 11 - Check if no release is occurring, then continue at Item 11.

7B Potential Possible Release - A potential release refers to a condition where a release is probable. This is not meant as a catch-all category.

Check this block if a release is probable, then continue at Item 11.

7C A release is occurrin - ex ected duration - If a release is occurring, enter the expected duration of the release, in hours and minutes. If you cannot predict the duration of the release, then enter "Unknown" in the blank.

7D A release occurred but sto ed - duration - If a release has occurred, enter approximately how long the release lasted, in hours and minutes.

REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 43 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT3 DIRECTIONS FOR COMPLETING THE STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 3 of 4)

ITEM ENTRY NOTE Items 8, 9 and 10 may be omitted from the initial notification IF the information is not available within the 15 minute initial notification time frame. If a release has occurred, this information must be included on the next message.

RELEASE RATE - This section requires the completed results of dose assessment.

8A NOBLE GASES - Check this block for a noble gas release. Write the release rate (in curies per second) in the space. Check either "Measured" or "Default" to indicate how the release rate was determined.

8B IODINES - Check this block for an iodine release. Write the release rate (in curies per second) in the space. Check either "Measured" or "Default" to indicate how the release rate was determined.

8C Release within normal o eratin limits - Check this block if the release is below Tech Spec limits.

TYPE OF RELEASE IS - Check the type of release. If known, enter the specific nuclide(s) being released.

10 PROJECTED OFFSITE DOSE RATE - This section requires the completed results of dose assessment.

Enter the projected THYROID DOSE RATE (CDE) and the TOTAL DOSE RATE (TEDE) in mrem/hr for the site boundary, 2, 5 and 10 mile distances.

METEOROLOGICAL DATA - This information is to be included on all notifications.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 44 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT3 DIRECTIONS FOR COMPLETING THE STATE OF FLORIDA-NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 4 of 4)

ITEM ENTRY 11A Wind direction from de rees - Enter the wind direction as read from ERDADS,(or the Met Tower Indicator Panel on Unit 1).

11B Sectors affected - Enter the letters of the sectors affected, as determined from Attachment 4, using the wind direction from 11A.

11C Wind s eed MPH - Enter the wind speed as read from ERDADS (or the Met Tower Indicator Panel on Unit 1).

11D Stabilit class - Enter the stability class as determined from Attachment 4.

12 UTILITY RECOMMENDED PROTECTIVE ACTIONS - This section requires the completed results of a PAR Worksheet. This information must be approved by the Emergency Coordinator or the Recovery Manager.

13 HAS EVENT BEEN TERMINATED? - If the event has not been terminated, check block A. If the event has been terminated, check block B and enter the time and date of termination.

~ECA I-H t Et' d pp<<t t t b and provide the time and date. EC approval is required prior to transmitting the form.

14 MESSAGE RECEIVED BY - The State Warning Point will provide the name of the person who received your message, and the current time and date.

END OF ATTACHMENT3 '.

J 1

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 45 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT4 DETERMINATION OF SECTORS AFFECTED AND STABILITYCLASS (Page 1 of 1)

A. Affected Sectors

1. Using the guide below, determine the Affected Sectors and enter in line 11B of the State Notification form.

NOTE If the wind direction is directly on the edge of two sectors (e.g., 11', 33',

56', etc.), an additional sector should be added to the Protective Action Recommendation (PAR). For example, if the wind direction is from 78',

then the affected sectors for the PAR should be L, M, N and P.

Wind Affected Wind Affected Wind Affected From Sectors From Sectors From Sectors 348 - 11 HJK 123 - 146 PQR 236 - 258 CDE 11 -33 JKL 146 - 168 QRA 258 - 281 DEF 33-56 KLM 168 - 191 RAB 281 - 303 EFG 56-78 LMN 191 - 213 ABC 303 - 326 FGH 78 - 101 MNP 213 - 236 BCD 326 - 348 GHJ 101 -123 NPQ there is no 0 sector there is no I sector B. Stability Class

1. Enter Delta-T (60 meter minus 10 meter temperatures) deg. F

2. Using Delta-T (bT) and the guide below, determine the Stability Class and enter in line 11D of the State Notification form.

Stability Class hT less than or equal to -1.7

-1.7 less than bT less than or equal to -1.5

-1.5 less than dT less than or equal to -1.4

-1.4 less than bT less than or equal to -0.5

-0.5 less than hT less than or equal to +1.4

+1.4 less than dT less than or equal to+3.6

+3.6 less than b,T G END OF ATTACHMENT4

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 46 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 1 of 6)

A. Guidelines for Protective Action Recommendation (PARs) to Off-site Authorities

1. FPL is required to provide county and state governmental authorities with recommendations for protective action to be taken by the public during radiological emergencies at the St. Lucie Nuclear Power Plant.

2. The responsible authorities are the State of Florida Division of Emergency Management (DEM) and St. Lucie and Martin County Departments of Public Safety.

3. PARs should be made utilizing all of the available data. This includes plant conditions, off-site dose projections and/or field monitoring data.

The more conservative PARs should be made.

4. Due to the large political and legal ramifications of these recommendations and the potential impact on FPL, the following format and content should be used:

a. If any case where a GENERAL EMERGENCY has been declared, the minimum PAR shall be: Shelter all people within a 2 mile radius and out to 5 miles in the affected sectors. (Affected sectors are the downwind sector plus the two adjacent sectors, three in total.)

b. If a GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor .

system (as defined in the Security Plan), the minimum PAR shall be: Evacuate all people within a 2 mile radius from the plant and out to 5 miles in the downwind sectors. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.

c. If the emergency has not been classified as a GENERAL EMERGENCY and the offsite doses are LESS THAN 500 mrem Total Dose (TEDE) and 1000 mrem Thyroid Dose (CDE) at 1 mile over the projected duration of the release, no protective action is recommended. This should be reported to DEM and other outside agencies who inquire as:

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 47 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 2 of 6)

A. (continued)

4. (continued)

c. (continued)

Based on our current assessment of all the information now available to us, Florida Power & Light Company recommends that you consider taking the following protective actions (PA) - NONE.

This recommendation may change in the future, but we cannot now say when it may change or what it may change to.

B. Determining Protective Action Recommendations (PARs)

NOTE If a controlled release is necessary to stabilize plant conditions or an uncontrolled release is anticipated, determine the approximate source term and duration of the release and the projected off-site doses prior to making any PARs.

1. In determining PARs, both plant conditions AND off-site doses must be considered. However, if a release has not occurred, then deteimine PARs based on plant conditions.

2. PARs Based on Plant Conditions

a. Refer to Attachment 6, Protective Action Recommendations.

b. Begin with the General Emergency question and proceed through the flowchart answering the questions at each prompt.

c. Upon completion of the flowchart, enter the PAR table and determine the PAR for each downwind distance.

d. Enter PARs into Line 1 of the table in Section C below.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 48 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 3 of 6)

B. (continued)

'I

3. PARs Based on Off-site Dose Projections NOTE For purposes of this procedure and when discussing dose calculations, the terms projected and forecasted can be, and are used, interchangeably.

a. Refer to Attachment 6, Protective Action Recommendations.

b. PARs are based on the Thyroid Dose (line 7) and/or the Total Dose (line 18) from the Dose Calculation Worksheet in EPIP-09, Off-Site Dose Calculations. This same information is available, when using the Class A Model dose program, on the 10 Mile Standard Report in the Forecast Mode.

c. For each downwind distance, enter the PAR table at the appropriate dose level and determine the PAR for that distance.

d. Enter PARs into Lines 2a and 2b of the table in Section C below.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 49 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 4 of 6)

B. (continued)

EXAMPLE A release has occurred at the St. Lucie Plant. The wind direction is from 22 degrees and the projected off-site integrated (2 hr) Thyroid Dose (CDE) is 10,000 mrem at 1 mile, 2000 mrem at 2 miles and less than 1000 mrem at 5 miles. The plant is in a GENERAL EMERGENCY with no actual or projected core damage and no loss of physical control of the plant. The following PAR should be made:

Based on our current assessment of all the information now available to us, Florida Power & Light Company recommends that you consider taking the following protective actions:

i. Evacuate all people between a 0 and 2 mile radl'us from the plant.

ii. Shelter all people between a 2 and 5 mile radius from the plant who are in sectors J, Kand L.

iii. No protective action is recommended between a 5 and 10 mile radius from the plant.

This recommendation may change in the future, but we cannot now say when it may change or what it may change to.

4. PARs Based on Field Monitoring Data

a. Refer to Attachment 6, Protective Action Recommendations.

b. PARs are based on Thyroid Dose Rate and/or the Total Dose Rate measured in the field. Field monitoring dose rates need to be multiplied times the expected duration of the release (default value is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) in order to determine projected doses.

1. Thyroid Dose (CDE) = Field measured thyroid dose rate x expected duration of release.

2. Total Dose Rate (TEDE) = Field measured Deep Dose Equivalent (DDE) + (0.04 x Thyroid Dose'CDE)).

/R4

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 50 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 5 of 6)

B. (continued)

4. (continued)

c. Field monitoring results from near site sample locations need to be adjusted/extrapolated to the 1 mile distance. Sample results between 1 to 2 miles need to be adjusted/extrapolated to the 2 mile distance and results between 2 to 5 miles adjusted/extrapolated to the 5 mile distance.

d. For each downwind distance, enter the PAR table at the appropriate dose level and determine the PAR for that distance.

CAUTION Do NOT mix doses based on dose calculations with doses based on field measurements when determining PARs.

5. When available, both plume calculations and off-site monitoring results should be evaluated when making PARs. If significant discrepancies exist between field monitoring results and plume dispersion calculations, Then an evaluation of the discrepancy should be made, and the appropriate value should be selected in the determination of PARs.

6. PARs have been developed based on guidance in NUREG/BR-0150, Vol. 1 and EPA 400-R-92-001.

/R4

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 51 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT5 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 6 of 6)

C. Protective Action Recommendations (PARs)

NOTE Actual PARs shall be the most conservative PARs based on plant conditions or off-site doses.

1. Complete the table below:

Step 1. Determine PARs based on Attachment 6, Protective Action Recommendations, and enter into line 1.

Step 2. Determine PARs based on Attachment 6, Protective Action Recommendations, and enter into lines 2a and 2b.

Distance From Plant/Recommendation Protective Action Recommendations 0-2 Mile 2-5 Mile 5-10 Mile Line 1. Plant Conditions Line 2a. Total Dose (TEDE)

Line 2b. Thyroid Dose (CDE)

2. Choose the most conservative PARs and record in Section 12 of the State of Florida Notification Message Form.

END OF ATTACHMENT5

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 52 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT6 PROTECTIVE ACTION RECOMMENDATIONS (Page 1 of 1)

General NO Emergency o

YES Actual or Loss of 02 MSes: S (CR)

Projected Severe Physical Control 2.5 Mits: S (DW)

Core Damage of Plant?

Nots (1) Note (2) 5-10 Mess: None YES YES 0-2 Miles: E (CR)

2.5 Mites

E (DW) + S (RS) 5.10 Mites: S (CR)

Evaluate Further Protective Action Rscommendatens Based on Oifsite Dose Estimates.

Determine PAR for each NOTES:

mits value using most conservaeve dose at that (1) Severe core damage fs indicated by either.

- Loss of critical functions required for core protection (e.g., loss of injection with LOCA),

rale value. Note (3) - High core temperatures (CET > 700'F), or

- CHARM reading of > 42 Es R(Hr.

Total Dose Thyroid Dose (TEDE) (CDE) (2) Loss of physical control of Control Room or vital reactor operating areas to intruders.

fn mrem in mrern (3) See guidance for Determining PARs in Attachment 5 of EPIP-02.

0 2 Mites 2-5 Miles 5.10 Miles 10- TBD Use 1 Mile Value Use 2 Mile Value Use 5 Mile Value Use 10 Mile Value

<500mrem <1000mrsm NONE NONE NONE

?500 mrem 21000 mrem BUT BUT S (CR) S (DW) S (DW) S (DW)

<1XO nvsm <5000 mrem at000 mrem BUT

<5000 mrem

~ BUT mrem

<25000 mre E (CR)

E(DW)+

S (RS)

E(DW)+

S (RS)

E(DW)+

S (RS) 25000 rnrem 225000 mre E(DW)+ E(DW)+

E (CR) E (CR) S (RS)

S (RS)

LEGEND OF SYMBOLS & ABBREVIATlONSr

< m Less Than; 2 = Greater Than or Equal To None - No Protective Action Recommended DW - Downwind+ 2 Adjoining Sectors S- Sheltering Recommended RS - Remaining Sectors E ~ Evacuaeon Recommended CR - Complete Circle Around Plant at Specified Distance (PiKPIEPIPM Pigr&of END OF ATTACHMENT6

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 53 of 65 E PIP-02 ST. LUCIE PLANT ATIACHMENT 7 NRC EVENT NOTIFICATION WORKSHEET (Page 1 of 2)

NDDO Contact's Name:

NRC Contact's Name:

EVENT NOTIFICATION WORKSHEET Notification Time Facility or Organization Unit Caller's Name Callback ¹: ENS FPL - St. Lucie Plant or (561)

Event Time & Zone Event Date 1 Hr. Non-Emergency (v) Lost Otfsite Comms 10 CFR 50.72(b)(1)

(vi) Fire (i)(A) TS Required S/D (vi) Toxic Gas Power/Mode Before Power/Mode After (i)(B) TS Deviation (vi) Rad Release (ii) Degraded Condition (vi) Other Hampering Sate Op.

4-hr. Non.Emergency (ii)(A) Unanalyzed Condition 10 CFR 50.72(b)(2)

(ii)(B) Outside Design Basis EVENT CLASSIFICATIONS (ii)(C) Not Covered by OPs/EPs (I) Degrade While S/D General Emergency (iii) Tornado Earthquake (ii) RPS Actuation (scram)

Site Area Emergency (iTi) Rood (ii) ESF Actuation Atert (gi) Hurricane (iii)(A) Safe S/D Capability Unusual Event (iii) Ice/Hail (iii)(B) RHR Capability 50.72 Non-Emergency (iTi) Ughtning (iii)(C) Control ot Rad Release Physical Security (73.71) (gi) (iii)(D) Accident Mitigation Transportation (iTi) Other Natural Phenomenon (iv)(A) Afr Release > 2X App B 20.403 Material/Exposure (iv) ECCS Discharge to RCS (iv)(B) Uq Release > 2X App B Other (v) Lost ENS (v) Offsite Medical (v) Lost Emerg. Assessment (vi) Offsite Notification DESCRIPTION Include: Systems affected, actuaiions & their frftiating signals, causes, effect ot event on plant. actions taken or planned, etc.

Notifications Yes No Will Be Anything unusual or not understood? Yes NRC Resident (Explain above)

State(s) Did all systems function as required? Yes No (Explain above)

Local Other gov agencies Mode of operation until corrected Estimate for restart date: Additional Into on back?

Media press release

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 54 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT7 NRC: EVENT NOTIFICATION WORKSHEET (Page 2 of 2)

ADDITIONALINFORMATION Radiological releases: Check or fill in applicable items (specifiic details/explanations should be covered in event /R4 description)

Uquid release Gaseous release Unplanned release Planned release Ongoing Terminated Monitored Unmonitored Offsite release T.S. exceeded RM alarms Areas evacuated Personnel exposed or contaminated Offsite protective actions recommended State release path in description.

Release Rate Total Activity HOO Guide

% T.S. Umit HOO Guide % T.S. Umit (Ci/sec) (Ci)

Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 pCi/sec 0.01 Ci Particulate 1 pCi/sec 1 mCi Liquid (excluding tritium and 0.1 Ci 10 pCi/min dissolved noble gases)

Liquid (tritium) 0.2 Ci/min 5Ci Total Activity Plant Stack Condenser/Air Ejector Main Steam Une SG Blowdown Other RAD monitor readings:

Alarm setpoints:

% T.S. Umit (if applicable)

RCS or SG tube leaks: Check or fill in applicable items: (specific details/explanations should be covered in event description)

Location of the leak (e.g., SG ¹, valve, pipe, etc.):

Leak Rate Units: gpm/gpd T.S. Limits: Sudden or Long Term Development:

Leak Start Date: Time: Coolant Activity & Units: Primary- Secondary-ust of Safety Related Equipment Not Operational:

EVENT DESCRIPTION (Continued from front)

E. C. Approval Time:

END OF ATTACHMENT7

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 55 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT7A GUIDELINE FOR COMPLETING THE NRC EVENT NOTIFICATION WORKSHEET (Page 1 of 2)

A. Contact information - to be completed following contact

1. Name of the NDDO contacted: - should be consistent with the NDDO duty schedule.

2. NRC Contacts Name - will be provided upon contact. Also obtain the event number and notification time as received from the HOO should be recorded on the top of the worksheet.

B. Event Notification Worksheet, Page 1

1. Notification Time - enter the time contact is made.

2. Unit - enter the appropriate unit number: Enter "0" for a classification common to both units.

3. Callers Name - enter the name of the person making the call.

4. ¹ Callback - enter the number of the ENS phone that you are calling from and the commercial phone number at which you can be reached.

5. Event time and Zone - enter the military time, the zone will be "EST" for Eastern Standard Time or "EDT" for Eastern Daylight-savings Time.

6. Event Date - enter the date the event is occurring.

7. Power/Mode Before 8 Power/Mode After - enter the power in percent and the mode number (1-6) before and after the event.

8. Event Classifications - check one of the four blocks for General Emergency, Site Area Emergency, Alert, or Notification of Unusual Event.

/R4

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 56 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT7A GUIDELINE FOR COMPLETING THE NRC EVENT NOTIFICATION WORKSHEET (Page 2 of 2)

B. (continued)

NOTE No other blocks in the upper half of the form are required.

9. Description - provide a written description of the event.

NOTE Check the blocks in the lower portion of the form based on current conditions.

10. Mode of operation until corrected - provided if known.

11. Estimate for restart date - enter "unknown".

12. Additional info on Page 2 - enter yes or no.

C. Event Notification Worksheet, Page 2

1. Fill in as much of the information on the back of the form as is immediately available - do not create undue delay in making the notification. This information can be gained once the open line of communication is established.

IR4 END OF ATTACHMENT7A

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 57 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT8 CRITERIA FOR EVACUATION A. Criteria for Local Evacuation The need for Local Evacuation should be determined in accordance with the following criteria:

Evacuate the affected local area in which any of the following conditions occul".

1. Area Radiation Monitor Alarm.

2. Containment Evacuation Alarm.

3. Unevaluated direct radiation dose rate increase in excess of 100 mRem/hour above normal levels.

I

4. Unexpected airborne radioactivity concentration in excess of 1 x Ci/cc.

10'icro

5. Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm'eta-gamma over an area of 100 ft'.

6. Removable radioactive surface contamination in an unposted area in excess of 50 dpm/100cm'lpha over an area of 100 ft'.

7. The Emergency Coordinator determines that a situation exists for which Local Evacuation is appropriate.

B. Criteria for Owner Controlled Area Evacuation The Owner Controlled Area shall be evacuated in the following circumstances:

1 ~ Site Area Emergency

2. General Emergency

3. If the Emergency Coordinator determines that the entire Owner Controlled Area should be evacuated.

END OF ATTACHMENT8

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 58 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT9 TURNOVER GUIDELINES (Page 1 of 2)

Upon arrival at the affected Control Room, the prospective Emergency Coordinator should review the following items/issues with the Control Room Emergency Coordinator (not in a particular order):

NOTE This information (1-10 below) should be reviewed with the DCS.

1. Type of accident or incident

2. Plant status

3. Equipment out-of-service

4. Operator actions underway

5. Radiological conditions

6. Meteorological conditions

7. Procedure status

8. Emergency Plan activities underway, including any on-site or off-site protective actions

9. Conditions and/or trends of concern

10. Personnel injuries or radiation exposures Prior to leaving Control Room verify the status of the following:

J

1. Emergency classification

2. Off-site notifications

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO THE EMERGENCY COORDINATOR 59 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT9 TURNOVER GUIDELINES (Page 2 of 2)

Bring the following items to the Technical Support Center:

1. Copy of RCO log (entries from start of the event)

2. Completed notification forms (State and NRC)

3. Operations Accountability Aid (only if completed)

END OF ATTACHMENT9

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 60 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT10 RE-ENTRY GUIDELINES (Page 1 of 3)

CAUTION As specified in ADM-17.09, Invoking 10 CFR 50.54(x), the Emergency Coordinator (EC) may (with the concurrence of a licensed senior operator) waive re-entry requirements to place the plant in a safe shutdown condition or mitigate a release, if this immediate action is needed to protect the public health and safety.

1. Prior to evacuation and with the Operational Support Center (OSC) NOT operational.

Re-entry guidelines do not apply.

2. Prior to evacuation and with the OSC operational.

a. Operators in the field should return to the Control Rooms and obtain an Electronic Personal Dosimeter (EPD) from the Health Physics Emergency Kit prior to returning to field.

Since terms may be dispatched from the OSC prior to evacuation of any plant areas, the OSC Supervisor and Health Physics Supervisor in the OSC (HPOSC) should evaluate the event in progress and determine the most likely trends in radiological conditions. If the event is likely to result in evacuation(s), due to radiological concerns, the teams should be dressed, equipped, and briefed, similarly to Re-entry Teams.

3. Evacuation ordered and with the OSC NOT operational.

Operator actions in the field must be viewed as re-entry activities. Operators shall return to the Control Rooms following the evacuation order. Operator shall obtain an Electronic Personal Dosimeter (EPD) from the Health Physics Emergency Kit, if not done previously. Re-entry into the plant requires:

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 61 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT 10 RE-ENTRY GUIDELINES (Page 2 of 3)

3. (continued)

a. The EC (initially the NPS) authorize the entry.

b. A team of at least two individuals be formed (one person should be knowledgeable in the principles of radiation protection, (e.g., Health Physics Technician, Chemist, or Non-licensed Operator (NLO)).

c. Maintenance of appropriate radiological and safety measures.

d. Tracking the whereabouts of the team.

NLOs, from both Units, are to report to the OSC once it goes operational.

4. Evacuation ordered and with the OSC operational

a. All field activities are re-entries and shall be coordinated and controlled by the OSC.

b. Re-entry into an evacuated area shall be made only when authorized by the EC and under the direction of the TSC HP Supervisor (TSCHPS) and the HPOSC for one or more of the following reasons:

1. To ascertain that all personnel who were in the affected area have been evacuated and to search for unaccounted for personnel.

2. To assist in evacuating injured or incapacitated personnel from the affected area.

3. To perform operations which mitigate the effect of the emergency or hazardous condition.

4. To determine the nature and extent of the emergency and/or radiological conditions.

5. To establish definite personnel exclusion area boundaries.

i ~

J REVISION NO.: PROCEDURE TITLE: PAGE:

DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 62 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT10 RE-ENTRY GUIDELINES (Page 3 of 3)

5. The Re-entry Team members should be selected based on appropriate qualifications relevant to the purpose for the entry.

6. A Re-entry Team shall consist of at least two qualified persons, one of whom shall be knowledgeable in Health Physics procedures.

7. The most qualified (relative to the entry) person should be selected to serve as the Re-entry Team Leader. He/she should be fully briefed concerning the nature of the emergency and the expectations for the entry.

8. All Re-entry Team members shall wear protective clothing, dosimeters, respiratory devices, and other protective devices as specified by the HPOSC.

9. A contingency Re-entry Team should be developed consisting of representatives from each of the maintenance disciplines and Health Physics. This team anticipates the need for a high priority, rapid response request from the EC/TSC.

END OF ATTACHMENT10

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4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 63 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT11 BASIS FOR EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 1 of 3)

Exposure to emergency response personnel should be maintained As Low As Reasonably Achievable (ALARA). Actions taken during an emergency should take into consideration the amount of exposure required to accomplish the task versus the potential benefit to the public health and safety.

Conditions may warrant re-entry into high radiation areas leading to exposure in excess of the regulatory limit. Except for rescue of personnel (life-saving only),

authorization must be given in advance by the Emergency Coordinator (EC) in consultation with the TSC Health Physics Supervisor (or alternate). If time permits, the EC should obtain concurrence from the Recovery Manager if the EOF is operational. In any case, where regulatory limits have been exceeded the EC shall notify the RM of the event.

For those remote circumstances involving an event in progress and obtaining EC approval will result in leaving the accident scene or decrease the victim(s) chance of survival, lifesaving actions may be performed without obtaining EC approval.

The EC shall be notified immediately following the rescue operation.

Re-entry personnel that have been selected/chosen to exceed regulatory exposure limits should be volunteers"', broadly familiar with the risks involved (radiosensitivity of fetuses, effects of acute exposures, etc.), whose normal duties have trained them for such missions.

EPA 400 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA 400-R-92-001 states that "To assure adequate protection of minors and the unborn during emergencies, the performance of emergency services should be limited to non-pregnant adults". FPL endorses this guidance; however, FPL recognizes that it is the right of the worker to make the decision to perform as an on-site emergency worker, understanding the potential risks involved.

Since, by their very nature, emergency exposures requiring immediate action are not planned, they are not controlled as a Planned Special Exposure. Dose received from exposure under emergency conditions will be added to the dose received during the current year, prior to the emergency, to determine compliance with the occupational dose limits in 10 CFR 20.

REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE NO.: THE EMERGENCY COORDINATOR 64 of 65 E PIP-02 ST. LUCIE PLANT ATTACHMENT11 g, BASIS FOR EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 2 of 3)

Doses above regulatory limits will require reporting pursuant to 10 CFR 20.2202 and 20.2203. Any dose in excess of the annual limits specified in Section 20.1201(a) will be accounted for in accordance with 10 CFR 20.1206(e). If an individual exceeds any of these limits, then the individual will not be available for additional dose under 20.1201(a).

NOTE

1. Both Total Dose (TEDE) and Thyroid Dose (CDE) should be used for purposes of controlling exposure.

Protective clothing, including respirators, should be used where appropriate.

For the following missions, the exposure limit is"': Total Dose"'HYROID"'TEDE)

(CDE)

Performance of actions that would not directly 5 REM 50 REM mitigate the event, minimize escalation, or minimize effluent releases.

Performance of actions that mitigate the escalation 10 REM 100 REM to the event, rescue persons from a non-life threatening situation, minimize exposures or minimize effluent releases.

Performance of actions that decrease the severity 25 REM 250 REM of the event or terminate the processes causing the event in an attempt to control effluent releases to avoid extensive exposure of large populations.

Al . tp situation.

R tp R ~tit .P (5) (5)

(Volunteers'"'hould be above the age of 45.)

f REVISION NO.: PROCEDURE TITLE: PAGE:

4 DUTIES AND RESPONSIBILITIES OF PROCEDURE No.: THE EMERGENCY COORDINATOR 65 of 65 EPIP-02 ST. LUCIE PLANT ATTACHMENT11 g, BASIS FOR EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 3 of 3)

(1) Exposure limits to the lens of the eye are 3 times the Total Dose (TEDE) values listed.

(2) Total Dose (TEDE) is the total whole body exposure from both external and internal (weighted) sources - Total Effective Dose Equivalent.

(3) Thyroid Dose (CDE) commitment from internal sources - Committed Dose Equivalent. The same dose limits also apply to other organs (CDE), skin (Shallow Dose Equivalent) and extremities (Extremity Dose Equivalent).

(4) Volunteers with full awareness of risks involved including numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects.

(5) No upper limit for Total Dose (TEDE) and/or Thyroid Dose (CDE) exposure has been established because it is not possible to prejudge the risks that one person should be allowed to take to save the life of another. Also, no specific limit is given for thyroid exposure since in the extreme case, complete thyroid loss might be an acceptable sacrifice for a life saved.

This should not be necessary if respirators and/or thyroid protection for rescue personnel are available as the result of adequate planning.

END OF ATIACHMENT11

l',

I

Procedure No.

ST. LUCIE PLANT HP-202 HEALTH PHYSICS Current Rev. No.

FPL PROCEDURE 25 SAFETY RELATED Effective Date:

09/28/99

Title:

ENVIRONMENTALMONITORING DURING EMERGENCIES Responsible Department: HEALTH PHYSICS Revision Summary Revision 25 - Added Red Team survey points. (Don Reisinger, 09/16/99)

PSL 0 O I O K

O O

PrtOCEDURE PRODUCTION Revision FRG Review Date Approved By Approval Date S OPS DATE 07/07/81 C. M. Weth 07/1 3/81 DOCT PROCEDURE Plant General Manager DOCN HP-202 SYS Revision FRG Review Date Approved By Approval Date COMP COMPLETED 09/1 6/99 R. G. West 09/1 6/99 ITM 25 25 Plant General Manager N/A Designated Approver

I Page 2 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES

1.0 TITLE

ENVIRONMENTALMONITORING DURING EMERGENCIES 2.0 REVIEW AND APPROVAL:

See cover page

3.0 PURPOSE

To provide a method for the determination of radioiodine concentrations and dose rates in the environment due to releases of radioactive materials from the plant under accident conditions.

3.1 The off-site Field Monitoring Teams monitor releases in the Emergency Planning Zone (EPZ) from the plant out to a distance of approximately 10 miles. /R25 3.2 The on-site Field Monitoring Team monitors releases outside the plant PROTECTED AREA but within the OWNER-CONTROLLED AREA. /R25 4.0 LIMITS AND PRECAUTIONS:

4.1 Off-site monitoring within the Plume Exposure Pathway EPZ shall be performed by St. Lucie Field Monitoring Teams. /R25 4.2 Field Monitoring Teams shall be under the direction of the TSC HP Supervisor (TSCHPS) in the Technical Support Center (TSC).

4.3 One member of each Field Monitoring Team shall be a qualified Health Physics Technician (HPT).

4.4 All Field Monitoring Team members shall wear personal dosimetry while doing monitoring.

4.5 Field Monitoring Teams should obtain FPL vehicles equipped with a cigarette lighter (power supply for portable radio) to use for transportation. Vehicles should have their engines on (running) and radios on during field activities.

Page 3 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES 4.0 LIMITS AND PRECAUTIONS: (continued) 4.6 The Field Monitoring Teams shall drive out of the release plume to count samples.

4.7 Respiratory protection equipment is available for each Field Monitoring Team and shall be used when the team is in the release plume.

4.8 The FPL Field Monitoring Teams shall communicate sample analysis data only to the plant unless otherwise directed by the TSCHPS.

4.9 The responsibility of the on-site Field Monitoring Team is to monitor releases on the FPL owned property. The Site Assembly Station is a principle location to monitor and other locations as directed by the TSCHPS. /R25 4.10 The TSCHPS shall deploy the Field Monitoring Teams according to the following emergency classifications:

ALERT Onsite 1 Team SITE AREA/ Onsite 1 Team (if not previously deployed) /R25 GENERAL EMERGENCY Offsite 2 Teams 4.11 Ensure all personnel using/handling the radios are familiar with the warnings/precautions contained in Appendix A to this procedure. /R25 5.0 RELATED SYSTEMS STATUS:

None

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan) 6.2 HP-200, Health Physics Emergency Organization 6.3 EPIP-10, Off-site Radiological Monitoring 6.4 FP&L Environmental Survey Team Map (10 mile EPZ)

Page 4 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES 7.0 RECORDS REQUIRED:

7.1 Field Monitoring Team Log Book 7.2 Table 1, Field Monitoring Team Check List 7.3 The following document when completed shall be maintained in the plant files in accordance with QI-17-PSL-1, "Quality Assurance Records." /R25

1. Form HP 202.1, Environmental Airborne Activity Calculation Form

Page 5 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES

8.0 INSTRUCTIONS

8.1 The TSCHPS directs the staffing and deployment of the Field Monitoring Teams. Upon the declaration of an ALERT level emergency the on-site out-of-plant Field Monitoring Team shall be activated and the off-site Field Monitoring Teams may be activated at the discretion of the Emergency Coordinator. If the classification is a SITE AREA or GENERAL EMERGENCY the on-site out-of-plant Field Monitoring Team and the off-site Field Monitoring Teams shall be activated. /R25 NOTE

1. Verify respirator qualification of all field team members - consult the Radiation Exposure Summary Report.

2. Verify vehicle has cigarette lighter.

3. SAS keys are at the North Security Building, if needed.

8.2 The HP Supervisor in the Operational Support Center (HPOSC) is responsible for the deployment of the Field Monitoring Teams and ensuring each HPT is:

1. Paired with a driver

2. Provided a vehicle

3. Red Team only

- Given a hand-held radio

- Given a pair of boltcutters (from the OSC HP Emergency kit)

NOTE The first team to complete Table 1, Field Monitoring Team Checklist, becomes the Red Team and is the first dispatched to the field.

8.3 Upon arrival at the Site Assembly Station (SAS) the Field Monitoring Teams call the Technical Support Center (TSC). The TSCHPS designates the on-site Field Monitoring Team as the Red Team, the off-site Field Monitoring Team as the Blue Team and the other off-site Field Monitoring Team as the Orange Team. /R25

Page 6 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES

8.0 INSTRUCTIONS

(continued) 8.4 Each Field Monitoring Team shall inventory their respective Emergency Kit and complete the Field Monitoring Team Checklist (see Table 1).

8.5 Equipment operability shall be verified in accordance with Appendix A, Operability Instructions.

NOTE Supplemental or replacement equipment and/or instruments are available in the spare Emergency Kit.

8.6 Following completion of inventories and equipment checks, the Field Monitoring Tearris will be given instructions on required monitoring points.

Monitoring points are designated using Emergency Planning Zone (EPZ) map coordinates, highway and road numbers/names, or the points shown in Appendix B, Preselected On-site Monitoring Points and/or Appendix C, Preselected Off-site Monitoring Points under the direction of the TSCHPS. /R25 8.7 Field Monitoring Teams will proceed to the designated monitoring points.

NOTE If a release is in progress, Field Monitoring Teams should monitor dose rates and count rates during transit and report any indications of a plume to the TSC. Ensure count rate meter is operating in cab of truck during transit.

/R25 8.8 Prior to arriving at the sampling location, place a AgX cartridge and particulate filter in the sample head. Mark the upstream face of both filters.

8.9 Upon arrival at the sampling location, the Field Monitoring Team should perform a dose rate survey in following manner. Record the time arrived at location in the blank labeled Time on Form HP 202.1, Environmental Airborne Activity Calculation Form found in this procedure.

1. Holding the survey instrument at head height with the detector upward, and beta window open, obtain a radiation reading of the overhead plume.

The beta window should be open to assist in detecting low levels in the plume. If a positive indication is observed, close the beta window and observe the gamma dose rate. Enter the dose rates on worksheet HP 202.1, line 3.

Page 7 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES

8.0 INSTRUCTIONS

(continued) 8.9 (continued)

Report the dose rates to the plant.

With the vehicle en ine runnin connect the air sampler power leads to the vehicle's battery, taking care to connect the positive and negative cables to the positive and negative battery terminals, respectively.

Start the stop watch and note the air flow rate. Run the air samples long enough to collect a 6 cubic foot sample, unless otherwise instructed.

5. During air sampling, the Field Monitoring Teams should observe the dose rate instrument for significant changes in dose rates. Report significant changes to the plant.

The Field Monitoring Team shall drive out of the release plume and count the samples.

Remove the AgX cartridge and particulate filter from the sampler head and place in separate labeled bags. Analyze the AgX cartridge per Appendix A, Step 5, save both samples as further inhouse analysis may be desired.

8.10 Air samples should be bagged, labeled and a log entry made of the following information:

Date and start time of sample Duration of sample Average flow rate of air sampler Location of sample (map coordinates, landmarks, etc.)

Field Monitoring Team name Air sampler number Ludlum 2218 Analyzer Serial Number

Page 8 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES

8.0 INSTRUCTIONS

(continued) 8.11 Communicate the data as indicated on the worksheet (HP 202.1), enter similar information in the bound logbook and standby for further instructions.

8.12 The TSCHPS may direct that a longer sampling period be used if very low release concentrations are suspected to be occurring.

Page 9 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES TABLE I FIELD MONITORING TEAM CHECKLIST 1.0 Emergency Kit (Footlocker) Inventory - verify necessary items.

NOTE

1. Magnetic-mount antenna is on top of kit.

2. If kit seal is unbroken, Then go to step 2.

1.1 TLD (2) 1.2 EPD (2) 1.3 DRD, 0 - 5 R (2) 1.4 Dosimeter Charger (1) 1.5 Full Face Respirator (2) (can be functionally checked on the spot) 1.6 Charcoal Canister (2) 1.7 AgX Cartridge (6) 1.8 Particulate Filter (6) 1.9 Stopwatch (1) 1.10 Air Sample Bag (6) 1.11 Surgical Gloves (6) 1.12 Tweezers (1) 1.13 Flashlight (1) 1.14 Calculator (1) 1.15 Portable Radio 1.16 Power Cord with Cigarette-lighter Plug 1.17 Microphone with Cable 1.18 DC Power Receptade with Battery Chips 1.19 Logbook (1) 1.20 List of TSC Phone Numbers (1) 1.21 Procedure, HP-202 (1) 1.22 HP 202.1 Forms (6) 1.23 Set of Site and Local Maps (1) 2.0 Verify Operability of Equipment (All tests in accordance with Appendix A, Operability Instructions) 2.1 High Volume Air Sampler with battery cables

1. Perform operability check IAW Appendix A.

2.2 Portable Dose Rate Instrument

1. Perform operability check IAW Appendix A.

2.3 Portable Count Rate Instrument

1. Perform operability check IAW Appendix A.

2.4 Ludlum 2218 Analyzer

1. Perform operability check IAW Appendix A.

2.5 Field Team Radio

1. Review Operating Instructions.

2. Attach magnetic-mount antenna to radio and vehide.

3. Plug radio power cord into vehicle cigarette lighter.

4. Test radio.

3.0 Prior to departing the Site Assembly Station verify the following 3.1 Radio check completed with the Plant 3.2 Dose Rate and Count Rate Instruinents In cab and on lowest scale /R25 3.3 Portable Count Rate Instrument in Emergency Kit (Footlocker) 3.4 Respirators in the cab 3.5 Field Team Members equipped with dosimetry 3.6 Maps in vehicle cab 3.7 Bolt cutters available (Red Team only)

Team Name Inventory by Date ~~

Operability Checks by Date ~~

Page 10 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 1 of 11)

1. Connect Hi Vol Air Sampler to truck battery (observe polarity) with engine running, turn air sampler on, confirm that flow is > 1.0 cfm, with collection filters and holder in place.

2. Portable Dose Rate Instrument - Check calibration sticker, battery test and response to supplied check source.

3. Portable Count Rate Instrument - Check calibration sticker, battery test (unplug line cord) and response to supplied check source.

4. Battery and Operational Checks of the Ludlum Model 2218:

NOTE Should it be necessary to use Channel 2, items contained within parentheses are settings to be used for Channel 2, see Figure 1.

Verify that the RECYCLE knob is OFF. The knob is labeled and located on the rear panel of the instrument.

4.1 Check the battery as follows:

NOTE If an instrument fails the battery check, it can be used only if it is connected to AC power and successfully passes the operational check.

A. Turn the POWER knob to BAT.

B. Unplug the AC line cord.

C. Depress the BAT testbutton.

D. Observe the condition below the RATE SCALE.

Page 11 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 2 of 11)

4. (continued) 4.1 (continued)

E. If battery condition is not within the acceptable BAT TEST range, plug in the AC line cord and turn the POWER knob to CHARGE. Attach a label to the instrument stating Instrument is charging, started charge at AM/PM on ,19 .

F. If the battery condition is acceptable, then continue with the steps below.

4.2 Set the STABILIZER toggle switch to OFF.

4.3 Ch1 (Ch2), set the ADD-OFF-SUBTRACT knob to ADD.

4.4 Ch2 (Ch1), set the ADD-OFF-SUBTRACT knob to OFF.

4.5 Ch1 and Ch2, set the ON-BYPASS toggle switch to BYPASS.

4.6 Ch1 (Ch2), set the WINDOW and the THRESHOLD dials (in accordance with) settings on the side of the 2218 cabinet.

4.7 Set the unused Channel's WINDOW and THRESHOLD dials to 10.0.

4.8 Ch1 (Ch2), set the IN-OUT toggle switch to IN.

4.9 Ch2 (Ch1), set the IN-OUT toggle switch to OUT.

4.10 Set the MINUTES knob to X1.

4.11 Set the LIVE-CLOCK toggle switch to LIVE.

4.12 Set the F-S (Fast-Slow) toggle switch to S.

4.13 Set the CH1-CH2-SCALER knob to SCALER.

Page 12 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 3 of 11)

4. (continued) 4.14 Set the MINUTES thumbwheel to 01.

4.15 Perform a source check as follows:

A. Place the Ba-133 check source in the shield under the detector.

B. Depress the COUNT-RESET button to start counting.

C. When counting stops, compare the displayed counts with the acceptance range that is located on the side of the instrument.

D. If the displayed counts are within the acceptance range, then go to Step 4.17. If the displayed counts are not within the acceptance range, then go to Step 4.16.

4.16 High Voltage (HV) adjustments are performed as follows:

A. Set the MINUTES knob to EXT.

B. Place the Ba-133 check source in the shield under the detector.

C. Depress the COUNT-RESET button to start counting.

D. Observe the COUNTS/MINUTE (Count Rate Meter) scale while making small adjustments in voltage to obtain the maximum count rate achievable.

E. Increase or decrease the voltage with the HV (High Voltage) dial ~

F. Set the MINUTES knob to X1.

G. Depress the COUNT-RESET button to start counting.

H. When counting stops, compare the displayed counts with the acceptance range that is located on the side of the instrument.

Page 13 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 4 of 11)

4. (continued) 4.16 (continued)

I. If the displayed counts are within the acceptance range, then go to Step 4.17. If the displayed counts are not within the acceptance range, then do not use the instrument.

J. Tag the instrument OUT-OF-SERVICE, give the reason.

K. Obtain another 2218 and perform the operability check.

4.17 Set the MINUTES thumbwheel to 05.

4.18 The battery and operational response checks have been successfully completed and the instrument has been set to count samples.

5. Operation of the Ludlum Model 2218:

5.1 Obtain Form HP 202.1, Environmental Airborne Activity Calculation Form.

5.2 Verify that the MINUTES thumbwheel is set to 05, adjust as necessary.

5.3 Perform a Background Count by depressing the COUNT-RESET button.

5.4 If the Background Counts are greater than 10,000 counts, then move to an area of presumed lower background. Repeat step 5.3. If the Background Counts are less than 10,000 counts, then go to the next step. If the background counts are still greater than 10,000 counts, continue and try to locate a lower background area.

5.5 Enter the number of counts in the blank labeled Background Counts on Form HP 202.1 and 5 in the blank labeled Count Time.

Page 14 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 5 of 11)

5. (continued) 5.6 Calculate the Background Counts Per Minute (BCPM) by dividing the Background Counts by the Minutes.

5.7 Calculate the MINIMUMDETECTABLE COUNT (MDCR) using the following formula:

BKG (CPM)

MDCR = BKG (CPM) + 4.66 BKG COUNT TIME (MIN) 5.8 Place the air sample cartridge in the shield under the detector so that the inlet side of the cartridge is facing the detector.

5.9 Count the sample by depressing the COUNT-RESET button.

5.10 If the Gross Counts are greater than 750,000 counts, then reduce the counting time to 1 minute by setting the MINUTES thumbwheel to 01. Repeat step 5.8.

If the Gross Counts are less than 750,000 counts, then go to the next step.

5.11 Enter the number of counts in the blank labeled Gross Counts on Form HP 202.1 and 5 or 1 (as appropriate) in the blank labeled Count Time.

5.12 Calculate the Gross Counts Per Minute (GCPM) by dividing the Gross Counts by the Minutes.

5.13 Compare sample GROSS COUNT PER MINUTE (GCPM) to the calculated MDCR.

1. If GCPM is less than MDCR (GCPM < MDCR), Then report I'" activity as less than minimum detectable activity (<MDA).

2. If GCPM is equal to or greater than MDCR (GCPM > MDCR) GO TO step 5.14.

Page 15 of 29 I ~

ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 6 of 11)

5. (continued) 5.14 Calculate the Net Counts Per Minute (NCPM) by subtracting the BCPM from the GCPM and enter in the blank labeled NCPM on Form HP 202.1.

5.15 Calculate the I-131 concentration (pCI/ml) by entering the requested values in the following formula.

I-131 pCi/ml (2.63 2+09) ( Ft'o/ume)

Background Counts per Minute= (5.6)

Gross Counts per Minute (5.12)

Net Counts per Minute (5.14)

LUtjLUM" 200 S00 X1K X100 8

0 X10 COUNTS/MINUTE X1 m>

RANGE Z ITI r-I 0+

i Oo Zw c QD,:,:.',' r. z m<

ZS 0

'0 )+ 0 ON ADD m

x ~ CO

<,Qo Qo ge ga gl OFF Gl

<<eeeoe eeeeexe '8 BYPASS I

SUBTRACT MINUTES T3 I ID (0

Q 0

-I Om I 33 C 0 CD e ON ADD Z 2",Qo OFF 0 ZU M- Z 33 ITl ITI ~

Qo SUBTRACT +X g) c~ >o B

WlNDOW THRESHOLD DETECTOR OFF ON h(ODEL 2218 0 33 g9 UNE HV BAT CAL OFF DUALANALYZER Qoo 0 ZV QM STABILIZER Z m~lM EXI. eAT 8 ee Qp (0

~

CHARGE ITl XI 33 ITl FIGURE 1 - LUDLUM2218 9<

I~i'iiei "Liied: ~He Ae usimen~ : Count Verification Operational h h11/ ~ r i n

-M- set to BAT L-set to'EXl" :.L-setto XI" 0-toggleto C- depress button to start:-e

, OFF

-Ch1to ADD, Ch2to L -set to'XI'-

n~<

': N- depress testbuttonto C - depress button to I "OFF toggle to ITl check battery condition

'A - indicates count P - adjust voltage start count :H-toggleto

, BYPASS'fcr Ch1 "LIVE'-toggleto S R~~

battery cordition B - compare counts with ard Ch2 E - set to SCALER on BAT TEST'scale A- observe maximln acceptance range for :'G - Ch1 set WINDOW ard THRESHOLD J -setto 01 fcrcheck

)

count rate the instrument in accordance with settings on side set to "05'or sample count of instrument; Ch2 set WINDOW and C- depress button to start THRESHOLD to 10.0 count

F - toggle to "IN fcr Ch1 and OUT for Ch2

Page 17 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 8 of 11)

Operating Instructions for the Motorola Spectra Radio

+a +~

ws ~i

~ ea El RIED Priority/Non.Prhrhy Irdicators

/8P40ZB. SFG)

To Turn On The Radio: Press the power switch once.

To Set Volume and Squelch: Hold [Vol] rocker down to increase or decrease volume as desired; then release. The display shows volume levels from 0 to 15. The radio is

~

ready to receive calls. On conventional modes with Private Line or Digital Private Line,

~

press [Mon] or remove the microphone from the hang-up clip to defeat the coded squelch. Press again to return to coded-squelch operation. To adjust squelch level, hold

~ ~

[Mon] until a beep sounds; use [Mode] to select squelch level. Press [Home].

To Change Modes: Press [Mode] to select desired mode, or press [Home] to access the preprogrammed home mode.

To Transmit: Press and hold the microphone PTT; when the transmit light comes on solid and no alert tones sound (or a talk-permit tone or ID sidetone sounds), speak into the microphone in a normal voice. State your FCC call sign at the beginning of each transmission.

To Talk Mobile-to-mobile (Conventional Modes): Press [Dir]; the DIR indicator lights to indicate direct (mobile-to-mobile) operation. Press [Dir] again to return to repeater operation.

To Activate operator Selected Coded Squelch (Conventional Modes): Press [MPL];

the MPL indicator lights to indicate the operator selected value is now active. Press

[MPL] again to return to the mode strapped value.

~

To Activate Scan: Press [Scan] to start the scanning operation. The radio scans a preselected list of modes for activity. If no activity exists, the display shows your selected mode. When a scanned channel or talkgroup becomes active, the display

~

shows the active mode name. The PRI and NPRI indicators show priority. Press [Scan]

again to stop scanning.

Page 18 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 9 of 11)

Operating Instructions for the Motorola Spectra Radio (continued)

To Edit a Scan List: Hold [Scan] until a beep sounds and the scan indicator blinks.

Then, (1) Use [Mode] to select the mode you want to program.

(2) Press [Sel] to add or to remove the displayed mode to the scan list. Repeat these steps to add to or change the list as desired. Then press [Home].

To Select Scan Mode Priority: When editing a Priority Scan list, you may designate two of the modes as priorities by pressing the [Sel] button as indicated below. When priorities are set, press [Home] to end scan list selection.

Press [Sel] Assigns Mode to Indicator 1 Time Non-Priority NPRI Lights 2 Times Second Priority PRI Lights 3 Times First Priority PRI Blinks NOTE The radio should be turned off whenever the engine is off to avoid draining the vehicle battery.

GENERAL SAFETY INFORMATION The United States Department of Labor, through the provisions of the Occupational Safety and Health Act of 1970 (OSHA) has established an electromagnetic energy safety standard that applies to the use of this equipment. Proper use of this radio will result in exposure below the OSHA limit. The following precautions are recommended:

DO NOT operate the transmitter of a mobile radio when someone outside the vehicle is within two feet (0.6 meter) of the antenna.

DO NOT operate the transmitter of a fixed radio (base station, microwave, the rural telephone RF equipment) or marine radio when someone is within two feet (0.6 meter) of the antenna.

Page 19 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 10 of 11)

Operating Instructions for the Motorola Spectra Radio (continued)

GENERAL SAFETY INFORMATION (continued)

DO NOT operate the transmitter of any radio unless all RF connectors are secure and any open connectors are properly terminated.

DO NOT operate this equipment near electrical blasting caps or in an explosive atmosphere.

All equipment must be properly grounded according to Motorola installation instructions for safe operation.

All equipment should be serviced only by a qualified technician.

Refer to the appropriate section of the product service manual for additional pertinent safety information.

INSTALLATIONSAFETY WARNING Consider the occupants'afety when you choose a location for the radio. Do not mount the radio overhead or on a sidewall unless you take special precautions.

If someone were to remove the radio and fail to replace it properly, road shock could bump the radio loose and the falling radio could, in some circumstances, cause serious injury to the driver or a passenger. In a crash, even when properly installed, the radio could break loose and become a dangerous missile.

If you must mount the radio overhead or on a sidewall, give it the added protection of a retaining strap.

OPERATIONAL SAFETY WARNINGS WARNING For vehicles equipped with electronic anti-skid systems, see ANTI-SKID BRAKING PRECAUTIONS Publication, Motorola Number 68P81109E34.

Page 20 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX A OPERABILITY INSTRUCTIONS (Page 11 of 11)

Operating Instructions for the Motorola Spectra Radio (continued)

OPERATIONAL SAFETY WARNINGS (continued)

WARNING For vehicles equipped with electronic ignition systems, check the service manual for warnings about the use of two-way radio equipment in the vehicle.

WARNING It is mandatory that radio installation in vehicles fueled by liquefied petroleum gas conform to the following standard:

National Fire Protection Association standard NFPA 58 applies to radio installation in vehicles fueled by liquefied petroleum (LP) gas with LP gas container in the trunk or other sealed-off space within the interior of the vehicles. This standard requires that:

1. Any space containing radio equipment shall be isolated by a seal from the space in which the LP gas container and its fittings are located.

2. Remote (outside) filling connections shall be used.

3. The container space shall be vented to the outside.

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Page 22 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX B PRESELECTED ON-SITE MONITORING POINTS (Page 2 of 4)

DISTANCE MONITORING FROM PLANT EPZ POINT LOCATION ~MILES SECTOR Red-1 Met Tower, Site Assembly Sta. 0.5 A Red-2 Gate A8 Rte A1A 0.3 Red-3 Gate B & Rte A1A 0.25 Red-4 Discharge Canal Bridge Rte A1A 0.2 Red-5 Gate C 8 Rte A1A 0.25 Red-6 Gate D & Rte A1A 0.3 Red-7 Gate E 8 Rte A1A 0.33 Red-8 Gate F & Rte A1A (north side of intake canal) 0.45 Red-9 Gate G 8 Rte A1A 0.6 Red-10 Ball Park Road (first north to westbound corner) 0.5 G Red-11 Ball Park Road (e mile marker on berm) 0.46 G,H Red-1 2 Ball Park Road (e corner turning north) 0.5 H,J Red-13 Ball Park Road (post in berm, midway between monitoring points Red 12 & 14) 0.38 Red-14 Ball Park Road (e left turn towards Gun Range/

Picnic Pavilion) 0.3

/R25

Page 23 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX B PRESELECTED ON-SITE MONITORING POINTS (Page 3 of 4)

DISTANCE MONITORING FROM PLANT EPZ POINT LOCATION ~MILES SECTOR Red-1 5 Gate W-25 (east side of Gun Range) 0.4 Red-16 Picnic Pavilion 0.33 Red-17 Intersection of Boat Ramp turnoff 8 road to Fire Training Area 0.32 Red-1 8 Gate W-26 (west side of Gun Range) 0.5 Red-19 Boat Ramp 0.36 M,N Red-20 Fitness Trail ( .5 mi. sign) 0.5 Red-21 Road, north side of Big Mud Creek (opposite Boat Ramp) 0.35 Red-22 Road, north side of Big Mud Creek (opposite City Water Storage Tanks) 0.30 Q Red-23 Road, north side of Big Mud Creek (opposite Barge Slip) 0.4 Red-24 Turtle Beach Parking Lot 0.62 Red-25 Large foot bridge 0.54 B,C Red-26 Small foot bridge 0.51 Red-27 Concrete power pad 0.5 Red-28 Discharge Canal Header 0.5

/R25

Page 24 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX B PRESELECTED ON-SITE MONITORING POINTS (Page 4 of 4)

DISTANCE MONITORING FROM PLANT EPZ POINT LOCATION ~MILES SECTOR Red-29 Halfway between Discharge 8 Intake Canal Headers 0.52 Red-30 Intake Canal Header 0.6 Red-31 Walton Beach entrance road

( fork in the road) 0.8

/R25

)e

P Page 25 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX C PRESELECTED OFF-SITE MONITORING POINTS (Page 1 of 4)

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Page 26 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX C PRESELECTED OFF-SITE MONITORING POINTS (Page 2 of 4)

Monitoring Location Distance From Plant EPZ Sector Point S.R. A1A, NNW of plant site R2 2.3 (Little Mud Creek Bridge)

Intersection S.R. A1A and Clipper Blvd.

R7 6.7 (Entrance to Ocean Village)

S.R. A1A, NNW of plant site R9 8.6 (West of Fire Dept. at Siren)

R10 East side of North Bridge (S.R. A1A) 9.6 Intersection of Indian River Dr.

Q4 (S.R. 707) and White Rd., East of White City 3.7 Q and South of Fort Pierce Intersection of Indian River Dr.

Q5 5.4 Q (S.R. 707) and Rio Vista Dr.

Intersection of U.S. 1 and Edwards Rd.

Q6 (S.R. 611.B), South side of Ft. Pierce near 6.4 Q railroad crossing Intersection of Oleander Blvd.

Q7 7.4 Q (S.R. 605) and Virginia Ave.

Q8 Intersection U.S. 1 and Delaware Ave. Q Intersection of Okeechobee Rd.

Q9 (S.R. 70) and Hartman Rd. (S. 41st St.) 9.1 Q (near siren)

Intersection of Orange Ave. (S.R. 68)

Q10 9.6 Q and Angle Rd.

P3 Intersection of Bartow St. and Yucca Dr. 3.2 Intersection of U.S. 1 and Midway Rd.

P5 5.2 (S.R. 712), White City Intersection of Midway Rd. (S.R. 712)

P7 7.1 and Christianson Rd. (at siren)

/R25

4 Page 27 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX C PRESELECTED OFF-SITE MONITORING POINTS (Page 3 of 4)

Monitoring Location Distance From Plant EPZ Sector Point Intersection of McNeil Rd. and Edwards Rd.

P9 8.7 (611 B)

Intersection of Okeechobee Rd.

P10 9.7 (S.R. 70) and I-95 N2 S.R. 707 West of plant site (at siren) 2.0 Intersection of U.S. 1 and Saeger Rd.

N5 4.8 (south of White City)

N6 Intersection of St. James Dr. and Airoso Blvd. 6.4 St. Lucie's EOF, Intersection of S.R. 712 N10 10.2 and l-95 M3 East end of N. Mediterranean Blvd. 3.4 Intersection of U.S. 1 and Prima Vista Blvd.,

4.8 Port St. Lucie Intersection of Prima Vista Blvd. and M6 6.5 Airoso Blvd.

M7 Intersection of Airoso Blvd. and Whitmore Dr. 7.3 Intersection of Prima Vista Blvd. and M8 7.8 Bayshore Blvd.

Intersection of U.S. 1 and Walton Rd.,

L5 4.8 Port St. Lucie L6 Intersection of Floresta Dr. and Thornhill Dr. 6.4 Intersection of Whitmore Drive and L7 7.2 Port St. Lucie Blvd.

Intersection of Port St. Lucie Blvd. and L8 8.4 Fla. Turnpike Intersection of Port St. Lucie Blvd. and L10 10 Cairo Ave.

/R25

e Page 28 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES APPENDIX C PRESELECTED OFF-SITE MONITORING POINTS (Page 4 of 4)

Monitoring Location Distance From Plant EPZ Sector Point K5 Intersection of Lennard Rd. and Blossom Rd. 4.7 Intersection of U.S. 1 and Port St. Lucie Blvd.,

K6 5.7 Port St. Lucie Intersection of Morningside Blvd. and Westmoreland Blvd.

71.

Intersection of Morningside Blvd. and K8 8.0 River Vista Dr.

Intersection of Walton Rd. and Indian River Dr.

J3 3.4 (S.R. 707)

Intersection of Indian River Dr. (S.R. 707) and J5 4.7 Mockingbird Hill Rd. (near siren)

Intersection of Jensen Beach Blvd. (S.R. 707A)

J7 7.0 and Savannah Rd. (S.R. 723)

J9 Intersection of Wright Blvd. and U.S. 1 9.2 J10 Martin Memorial Hospital 10.0 S.R. A1A, south of plant (at siren) North to H4 4.0 entrance to Nettle's Island Intersection of S.R. A1A and the Jensen Beach H7 6.9 turnoff (A1 A Alt.) (at siren)

Intersection of S.R. A1A and Ocean Blvd.

H10 9.8 (Elliot Museum)

/R25

~f O

0

Page 29 of 29 ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NO. HP-202, REVISION 25 ENVIRONMENTALMONITORING DURING EMERGENCIES HP 202.1 ENVIRONMENTALAIRBORNE ACTIVITYCALCULATION FORM

1. Team

2. Location Date ~~ Time

3. Radiation Survey: Window Open mrem/hr Window Closed mrem/hr

4. Air Sample Volume:

Sample Start Time Sample Stop Time Starting Flow Rate CFM Ending Flow Rate CFM Average Flow Rate CFM Sample Time Min Sample Volume = Average Flow Rate (CFM) X Sample Time (Min)

CFM X NOTE In the event radioiodine (l-131) analysis cannot be done in the field, the TSC HP Supervisor will provide for the transport of air samples to the plant site for analysis.

5. Background Count Rate = Background Counts / Count Time counts / BKG cpm

'DCR = BKG cpm+ 4.66 BKG cpm MDCR (cpm)

BKG Count Time

7. Gross sample count rate (GCPM) = Gross counts / Count Time counts / min GCPM

8. Net Count Rate (NCPM) = GCPM - Bkg cpm NCPM GCPM - BKG cpm NCPM

9. If "NCPM's less than "MDCR", Then '"I activity is "<MDA" (less than detectable). /R25

" "/ activity (pCilm/)- ( NC/ /I//)

M)

(2.63 E + 09) ( samp/e volume, Ft')

/R25

"" ~31/ activity = p,Cilml

12. Plume Departure Time

" 13. Plume Stay Time: minutes Survey performed by NOTIFY TSC OF ALL

ITEMS

Pl C

ML17309A996

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