Text

Revised Emergency Plan Implementing Procedures, EPIP-09, Revision 7 - EPIP-12, Revision 11
	ML022470337
Person / Time
Site:	Saint Lucie
Issue date:	08/26/2002
From:	Jernigan D; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2002-161
	Download: ML022470337 (117)
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EPIP-09 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE F PL IEffective Date SAFETY RELATED 08101102

Title:

PSL

,OFF-SITE DOSE CALCULATI C Responsible Department: EMERGENCY PREPAREDNESS 6

0 REVISION

SUMMARY

PROCEDURE PRODUCThN Revision 7 - Corrected process & effluent monitor ranges, corrected fan flow rates, made numerous procedure step clarifications / improvements based on user / student feedback, and made editorial / administrative changes. (J. R. Walker, 07/26/02)

Revision 6A - Upper level met instrumentation @ 57.9 not 59.7 meter. Revision not typed as submitted / approved. (J.R. Walker, 02/13/02)

Revision 6 - THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN. Reformatted instructions / procedure layout to better accommodate user's with different backgrounds, added data interpretation information for both units to assist persons with less background in release pathways and effluent monitors, made human factors improvements, and made editorial / administrative changes. (M. Cooper, 11/15/01)

Revision 5 - Clarified Delta T determination. (J. R. Walker, 06/18/01)

Revision 4 - Revised fan flow rates to accommodate for maintenance acceptance criteria and included minor correction to a number used in an example. (Steve Knapp, 02/02/01)

Revision 3 - Made human factors improvements; identified applicable unit, relocated note and caution messages, changed table, revised instructions for changing date and time on Class A computer, and changed responsible department from Training to Emergency Preparedness.

(Steve Knapp, 09/11/00)

FRG Review Date 12/15/97 FRG Review Date 07/25/02 Approved By J. Scarola PFlant General Manager Approved By Dick Rose Plant General Manager N/A Designated Approver N/A Designated Approver (Minor Correction)

Approval Date 12/15/97 Approval Date 07/26102 S__OPS DATE DOCT PROCEDURE DOCN EPIP-09 SYS COM COMPLETED ITM 7

Revision 0

Revision 7

I I

Current Revision No.

7

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 2 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE PURPOSE..........................................................................................................

3 REFERENCES / RECORDS REQUIRED / COMMITMENT DOCUMENTS....... 4 RESPONSIBILITIES.......................................................................................

5 DEFINITIONS.................................................................................................

5 INSTRUCTIONS.............................................................................................

8 ATTACHMENTS ATTACHMENT 1 ATTACHMENT 2 ATTACHMENT 3 ATTACHMENT 4 ATTACHMENT 5 ATTACHMENT 6 ATTACHMENT 7 ATTACHMENT 8 ATTACHMENT 9 ATTACHMENT 10 ATTACHMENT 11 ATTACHMENT 12 DATA ACQUISITION VIA ERDADS.................................... 11 GROSS NOBLE GAS CONCENTRATIONS VIA EBERLINE CONTROL TERMINAL A OR B..........................................

13 GROSS NOBLE GAS CONCENTRATION VIA THE PC-1 1, RADIATION MONITORING CONSOLE...............................

14 UNIT 1 - DATA INTERPRETATION.................................... 15 UNIT 2 - DATA INTERPRETATION....................................

18 CLASS A MODEL DOSE CALCULATION.......................... 22 METEOROLOGICAL DATA...............................................

28 RELEASE RATE DATA.....................................................

38 MANUAL DOSE CALCULATION.........................................

61 RESPONDING TO AN UNMONITORED CONTAINMENT BU R P..................................................................................

71 ESTIMATE OF CONTAINMENT "% MASS LOSS".............. 77 FIELD TEAM MEASUREMENTS ASSESSMENT............... 79 1.0 2.0 3.0 4.0 5.0

REVISION NO.:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 3 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT 1.0 PURPOSE 1.1 Discussion

1.

This procedure is applicable to both Unit 1 and Unit 2. Should both units be affected, provisions have been made on the worksheets to sum the release rates.

2.

Off-site dose estimates, release rates and containment radiation levels will be used by the EC for classifying emergencies and making Protective Action Recommendations (PARs).

3., CLASS A MODEL DOSE CALCULATIONS, provides instructions for performing dose calculations using the computer model.

This model estimates off-site dose rates and cumulative doses and parallels this procedure. More detailed information on the Class A Model is available in the "FPL - Class A Emergency Offsite Dose Calc Program User Guide;" a controlled copy of which is available in the TSC and EOF.

4. 0, RESPONDING TO AN UNMONITORED CONTAINMENT BURP, is to be used to assess unmonitored releases resulting from rapid containment depressurization events.

5. 1, ESTIMATE OF CONTAINMENT "% MASS LOSS", is to be used to assess a rapid depressurization (i.e., greater than design basis) of containment through an estimate of containment volume loss.

6. 2, FIELD TEAM MEASUREMENTS ASSESSMENT, provides a method to back calculate a release rate from Field Monitoring Team survey results.

REVISION NO.:

PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 4 of 81 PROCEDURE NO.

EPIP-09 ST. LUCIE PLANT

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, Operating Experience, License Renewal, 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.

Indicates a step that requires a sign off on an attachment.

2.1 References

1.

St. Lucie Plant Updated Final Safety Analysis Report (UFSAR), Unit 1 and Unit 2

2.

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

3.

E-Plan Implementing Procedures (EPIP 13)

4.

HP-2, FP&L Health Physics Manual

5.

QI-17-PSL-1, Quality Assurance Records

6.

Bases for Accident Dose Calculations for St. Lucie Nuclear Power Plant (Bases prepared by HMM Associates of Waltham, Massachusetts)

7.

NUREG-0654, Rev. 1, FEMA Rep-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November, 1980

8.

NUREG/BR-1 50, Vol. 1, Response Technical Manual

9.

EPA-400-R-92-001, EPA Manual of Protection Action Guides and Protective Actions for Nuclear Incidents, October, 1991.

10.

¶12 FPL Engineering Calculation PSL-BFJM-93-032, March, 1994.

2.2 Records Required

1.

All completed data / worksheets or computer generated forms providing similar information, shall be maintained in the plant files in accordance with QI-17-PSL-1.

REVISION NO PROCEDURE TITLE:

7 OFF-SITE DOSE CALCULATIONS 5 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT 2.3 Commitment Documents

1.

¶1 Condition Report 96-2609 (ERDADS Data / Fan Status)

2.

¶3 PMAI PM99-09-016 (PARs Based on FMT Data)

3.

¶4 Condition Report 00-1426 Supplement 1 (Fan Flowrates)

4.

¶5 PMAI PM01-05-073, Condition Report CR 01-0351 (Determination of Delta T)

5.

16 PMAI PM02-04-053, Condition Report 00-1426 Supplement 2 (Fan Flowrates)

6.

¶7 PMAI PM02-06-010, Condition Report 02-0870 (Process and Effluent Monitors - Range Corrections) 3.0 RESPONSIBILITIES 3.1 The Chemistry Department shall be responsible for performing off-site dose calculations, when directed by the Emergency Coordinator.

3.2 The EOF Dose Assessor shall take primary responsibility for dose assessment when the EOF is operational.

4.0 DEFINITIONS 4.1 Abbreviations / Acronyms

1.

PAR - Protective Action Recommendation - designation used on a Dose Calculation Worksheet that refers to data that should be used when determining Protective Action Recommendations.

2.

SNF - State Notification Form - designation used on the Dose Calculation Worksheet that refers to data that should be transferred to the Florida Nuclear Plant Emergency Notification Form.

3.

Class A Model - Commonly used to refer to the "FPL - Class A Emergency Offsite Dose Calc Program".

4.2 Affected Unit - (for purposes of this procedure) - a reactor unit that has activated the Emergency Plan and has a release.

REVISION NO.:

PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 6 of 81 PROCEDURE NO, EPIP-09 ST. LUCIE PLANT 4.3 Iodine Removal System - is defined as any one Containment Spray pump running with its chemical addition system injecting the chemicals.

1.

This system is considered in service if any one Containment Spray Pump is running AND for:

A.

Unit 1, if its Sodium Hydroxide (NaOH) tank level is decreasing.

B.

Unit 2, if its Hydrazine (N2H4) pump is "ON".

4.4 Core Overheating / Melting - Severe core damage, beyond gap failure, typically indicated by:

1.

The core being uncovered, by coolant, for 30 minutes or more.

2.

CHRRM reading greater than 4.2 E+4 R/hr.

NOTE The 700°F Core Exit Thermocouple value used in other procedures signifies the starting point for potential core melting. The value used in this procedure signifies that the core is in an overheat condition, melting is imminent and the release may include particulates, (e.g., Bariums, Cesiums, Strontiums, etc.).

3.

Valid Core Exit Thermocouple reading(s) in excess of 1700'F.

4.5 Particulate Factor (PF) - a factor used when core melt or overheat is under way to account for the particulate in the release pathway.

NOTE Prior to the declaration of a release, all viable channels for the effluent pathway should be evaluated to confirm increase of the applicable monitor reading(s).

4.6 Release - during any declared emergency, one of the following is true:

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 percent Derived Air Concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

REVISION NO' PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 7 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT 4.7 Sea-breeze - is a coastal phenomena where an artificial ceiling may exist.

1.

Our meteorological data processing methods assume that this ceiling acts as a limit to vertical mixing; that is, the plume is below the ceiling. This leads to a slightly higher concentration for a given stability class.

2.

The Class A Model will, in some cases, state "Sea-breeze: Yes", when manual calculations would indicate No Impact. The Class A Model is stating that sea-breeze may exist, although there is no impact because the ceiling is too high to affect the vertical mixing within 10 miles of the plant. This will not cause significant deviations in calculations performed using the two methods.

4.8 Symbols - the following symbols are used in this procedure:

1.

< = less than

2.

< = less than or equal to

3.

> = greater than

4.

> = greater than or equal to

5.

E =stands for exponent and indicates the power to which 10 is raised, "or times 10 to the power of", e.g.:

A.

E + 04 104 = 10,000 B.

E - 04 =10"4 = 0.0001

REVISION NO.:

PROCEDURE TITLE PAGE*

7 OFF-SITE DOSE CALCULATIONS 8 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Data Acquisition NOTE Be aware of the possibility of a release from an unmonitored point.

Evaluating data on system / component pressures, operating characteristics and local area radiation monitors will help identify such releases.

1.

Evaluate available plant data to determine if a release has occurred or is imminent.

2.

When a release is confirmed, acquire meteorological and source term data; NOTE Information on Data Interpretation, Plant Parameters, Release Pathways and Effluent Monitors for Unit 1 and Unit 2 is available in Attachments 4 and 5, respectively.

A.

If ERDADS - Emergency Data Acquisition and Display System, is available, Then:

1.

Obtain SMD and / or RG (1 or 2) as provided in Attachment 1.

B.

If ERDADS is unavailable, or some of its data is unusable, Then:

1.

Obtain meteorological data as provided in Attachment 7.

2.

Obtain Unit 1 Gross Noble Gas concentrations via Eberline Control Terminal A or B as provided in Attachment 2.

3.

Obtain Unit 2 Gross Noble Gas concentrations via the PC-1 1, Radiation Monitoring Console as provided in Attachment 3.

REVISION NO:

PROCEDURE TITLE.

PAGE:

7 OFF-SITE DOSE CALCULATIONS 9 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT 5.1 Data Acquisition (continued)

2.

(continued)

C.

Obtain plant ventilation exhaust fan status NOTE When obtaining plant ventilation exhaust fan status from the Control Room, specify fan numbers.

1.

Prior to a fully-staffed TSC, obtain exhaust fan status from affected Control Room.

NOTE TSC Sound-powered Phone Talker can be utilized as a source for plant ventilation exhaust fan status not available from TSC status boards.

the

2.

When the TSC is fully staffed, obtain exhaust fan status from the Safety Functions and Equipment Status board in the TSC.

3.

When the EOF is operational, obtain exhaust fan status from TSC Dose Assessor or TSC Chemistry Supervisor.

5.2 Off-Site Dose Calculations Methodologies

1.

The Class A Model should be used if it is available.

A.

Perform system start-up and pre-use verification QC Check in accordance with Attachment 6.

B.

If system start-up and QC check are acceptable, perform dose calculations using the Class A Model.

2.

If Class A Model is NOT available, Then perform manual dose calculations using Attachments 7 through 12.

5.3 Provide the Emergency Coordinator with dose calculation results prepared in the Control Room or TSC.

1.

Provide TSC Administrative Staff with dose calculation results prepared in the Control Room or TSC and request results are faxed to EOF.

5.4 Provide the Recovery Manager and EOF HP Manager with dose calculation results prepared in the EOF.

REVISION NO' PROCEDURE TITLE' PAGE 7

OFF-SITE DOSE CALCULATIONS 10 of 81 PROCEDURE NO" EPIP-09 ST. LUCIE PLANT 5.5 The TSC Chemistry Supervisor or EOF HP Manager, once the EOF is operational, should monitor release rates and meteorological conditions to determine how frequently to update the dose rate estimates.

1.

Release and dose estimates shall be revised at least hourly for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the accident unless it is determined that releases of radioactivity have been terminated.

2.

When performing manual dose calculations, If any of the following averages change by the amounts indicated below, over a period of 30 minutes or less, Then dose estimates shall be updated.

A.

Release rates increase by more than 25 percent.

OR B.

Wind speed decreases to less than one half of previous value.

OR C.

Atmospheric stability becomes more stable by more than one class (e.g., change from stability D to F).

OR D.

Wind direction changes by more than 22.5 degrees (i.e., plume centerline is more than one sector away from prior location).

END OF SECTION 5.0

REVISION NO PROCEDURE TITLE.

PAGE.

7 OFF-SITE DOSE CALCULATIONS 11 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT I DATA ACQUISITION VIA ERDADS (Page 1 of 2)

1.

System Set-up A.

Check for a small square cursor at the top left corner; if it is present, the unit is ready.

1.

If it is not present, be sure the <DIM/NON-DIM> select (on keypad) is on <NON/DIM> and then increase the contract and brightness (knobs at the bottom left of screen).

B.

Press <CLEAR>.

C.

Type "Pup Unit 1" to access Unit 1 data, type "Pup Unit 2" to access Unit 2 data, then press <EXEC>.

D.

Top of screen will read "Unit change is complete" or "Current Unit is same as entered Unit".

2.

To access data using Primary Group Key A.

Press <CLEAR>.

B.

Press the yellow <EPIP> key.

1.

SMD, titled "Site Meteorological Data", showing 15 minute average 10 and 57.9 meter wind speed, wind direction, temperature and differential temperature will display.

CAUTION

1. Large errors may result if the ERDADS computer is NOT addressing the affected unit's database.

2. ¶T "No data" after a parameter name means that this input is NOT available from ERDADS for this unit.

REVISION NO' PROCEDURE TITLE.

PAGE:

7 OFF-SITE DOSE CALCULATIONS 12 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 1 DATA ACQUISITION VIA ERDADS (Page 2 of 2)

2.

(continued)

C.

Press <PG-DN> to scroll through, in order:

1.

RG (1 or 2), titled "Radiation Gaseous Source Term", showing plant effluent monitor, Main Steam Line monitor, CHRRM and containment pressure and same site meteorological data in SMD.

CAUTION

¶i Certain parameters (e.g., fan status) available on Unit 2 (SF2) are NOT available on Unit 1 (SF1).

2.

SF (1 or 2), titled "Safety Functions and Equipment Status",

showing TSC Status Board data.

3.

RBS, titled "Health Physics Evaluation Screen" showing containment radiation levels and trends (not required for dose assessment).

4.

EF (1 or 2), titled "EOF Data Sheet" showing EOF Status Board data.

5.

Return to SMD.

3.

To access Chemistry Data and Radiation Monitors:

A.

Press <CLEAR>.

B.

Type R (Unit 1) and press <DSPLY>.

I.

R (Unit 1), page 1 of Radiation Monitors showing area radiation monitor data will display. Press <PG-DN> to display following pages of radiation monitor data.

4.

To access other data using Display Name Code:

A.

Press <CLEAR>.

B.

Type the 3 character alpha-numeric display name code and press

<DSPLY>.

END OF ATTACHMENT I

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 13 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT ATTACHMENT 2 GROSS NOBLE GAS CONCENTRATIONS VIA EBERLINE CONTROL TERMINAL A OR B (Page 1 of 1)

I

~CAUTION Eberline Control Terminal A or B supplies data for Unit I only.

1.

Enter the following sequence on the keypad for each applicable channel number:

A.

Press 10 MIN HIST.

B.

Determine the applicable pathway channel number from the table below.

C.

Enter the applicable pathway channel number (leading zeros not required).

D.

Press ENTER (value appears in window).

E.

Press PRINT.

F.

Press FILE.

G.

Press ENTER.

H.

Enter effluent monitor data into the applicable Release Rate Data Sheet.

NOTE Use a steamline channel ONLY if the Safeties and I or Atmospheric Steam Dumps are releasing steam. Monitors have one range.

Range Path Low Mid Hi Plant Vent 1-5 1-7 1-9 ECCS - A 2-5 2-7 2-9 ECCS - B 3-5 3-7 3-9 Fuel Bldg.

4-5 4-7 4-9 Steamline A N/A 5-1 N/A Steamline B N/A 5-2 N/A

2.

The Eberline Terminal provides a ribbon paper print out of several rows of ten (10) minute averages of the concentration for the selected pathway channel.

The last row is the current value for the selected pathway channel. The row above the last row is the most recent full ten (10) minute average and should be used as the source data for dose calculations.

END OF ATTACHMENT 2 I

REVISION NO" PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 14 of 81 PROCEDURE NO" EPIP-09 ST. LUCIE PLANT Applicable Pathway Channel Number Range Path Low Mid Hi Plant Vent 621 622 623 ECCS - A 601 602 603 ECCS - B 611 612 613 Fuel Bldg. (If NOT diverted) 413 N/A N/A Steamline A N/A 631 N/A Steamline B N/A 632 N/A Background (Steamline)

N/A 633 N/A END OF ATTACHMENT 3 ATTACHMENT 3 GROSS NOBLE GAS CONCENTRATION VIA THE PC-11, RADIATION MONITORING CONSOLE (Page 1 of 1)

I

~CAUTION The PC-11 Radiation Monitoring Console supplies data for Unit 2 only.

1.

Use the following keystroke sequence for each applicable channel number:

A.

Press Key F8 to display Control Menu.

B.

Use the ARROW Key to highlight the RM-80 Utility Task under the status display.

C.

Press ENTER key.

D.

Press Key F1 to select Historical Display.

E.

Press Key F4 to select Graph 10 Minute.

F.

Determine the applicable pathway Channel Number, from the table below.

G.

At prompt, type M and the Channel Number.

H.

Press ENTER.

I.

Record Top #1 reading in applicable DATA column.

J.

Press Key F10.

K.

Press Key F10.

L.

Press Key F1 to display All Monitor Schematic.

REVISION NO.:

PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 15 of 81 PROCEDURE NO.'

EPIP-09 ST. LUCIE PLANT ATTACHMENT 4 UNIT I - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 1 of 3)

1.

If a single effluent monitor channel is operable and on scale, Then use the value for that channel. If the channel is not on-scale, do NOT use the channel.

2.

If two effluent monitor channels for the same pathway are operable, on-scale, and display concentration values in the overlapping range, Then use the highest (most conservative) value.

3.

Eberline SPING Effluent Monitors Used on Unit I Plant Vent, ECCS A & B and FHB All have 3 gas channels; low, mid and high range Indicate "BAD" if out of instrument range, high or low

4.

Steam Generator Tube Rupture (SGTR)

NOTE Recall that evidence of release may be confirmed / negated by use of backup instrumentation such as Area Radiation Monitors (ARMs) or Containment High Range Radiation Monitors (CHRRMs). Health Physics survey results should also be reviewed, as feasible.

Use a steamline channel only if the Safeties and / or Atmospheric Dumps are releasing steam. Otherwise, verify alignment of Steam Jet Air Ejector exhaust to the Plant Vent (PV) and utilize PV effluent monitor.

5.

Containment Isolation Signal (CIS)

NOTE Containment design pressure = 39.6 psig.

Initiates:

Prior to Containment Pressure reaching 5 psig When Containment Radiation is equal to or greater than 10 r/hr 0

At a Safety Injection Actuation Signal

-.5

-4

REVISION NO:

PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 16 of 81 "PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 4 UNIT I - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 2 of 3)

5.

(continued)

Isolates HVE I0A & B Auto starts HVE 6A & B and HVE 9A & B

6.

Safety Injection Actuation Signal (SIAS)

Initiates:

Prior to Containment Pressure reaching 5 psig When Pressurizer Pressure is equal to or less than 1600 psia Isolates HVE 10A & B Auto starts HVE 6A & B and HVE 9A & B Accident Type Release Pathway Fans Comments LOCA Plant Vent 6 & 10 10 Fans secure on SIAS / CIS ECCS 9

6 & 9 fans auto start on SIAS / CIS SGTR Plant Vent 6 & 10 Air Ejector aligned to PV Atmosphere N/A Atm. Dumps and Safeties Open FUEL HANDLING FHB Stack 15,16 & 17 CASK DROP FHB Stack 15,16 & 17 WGDTR Plant Vent 6&10

REVISION NO' 7

PROCEDURE NO.

EPIP-09 PROCEDURE TITLE OFF-SITE DOSE CALCULi ST. LUCIE PLANT ATTACHMENT 4 UNIT 1 - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 3 of 3)

6.

(continued)

¶7 Cal**hfn M nifnr Channel Units Scale (min - max)

Typical (non-emergency)

Reading Plant Vent - LR 01-05 i.Cilcc 1.0E 1.OE-01 Mid E-07

- MR 01-07 p.Ci/cc 2.5E-02 -4.OE+02 Mid E-04

- HR 01-09 gCi/cc 1.OE 1.OE+05 Mid E-01 CHRRM - A 58 r/hr 1.OE+00 - 1.OE+07 Low E+00 CHRRM - B 59 r/hr 1.0E+00 - 1.0E+07 Low E+00 Post LOCA - A 52 mr/hr 1.0E+00 - 1.OE+05 Mid E+00 Post LOCA - B 53 mr/hr 1.0E+00 - 1.0E+05 Mid E+00 ECCS - A - LR 02-05 jtCi/cc 1.OE 1.OE-01 High E-07

- MR 02-07 l+/-Ci/cc 2.5E 4.OE+02 Low E-03

- HR 02-09 RCi/cc 1.OE 1.OE+05 High E-02 ECCS - B - LR

- MR

- HR Steamline - A Steamline - B Fuel Bldg. - LR

-MR

- HR 03-05 03-07 03-09 05-01 05-02 04-05 04-07 04-09 liCi/cc pCi/cc R.Ci/cc mr/hr mr/hr

[iCi/cc pCi/cc 1iCi/cc 1.OE 1.0E-01 2.5E 4.0E+02 1.OE 1.OE+05 1.OE 1.0E+04 1.0E 1.OE+04 1.OE 1.0E-01 2.5E 4.OE+02 1.OE 1.0E+05 Mid E-04 Low E-01 Low E-02 Low E-02 High E-07 Low E-03 Low E-01 I _

END OF ATTACHMENT 4 I

I I

REVISION NO.:

PROCEDURE TITLE:

PAGE.

7 OFF-SITE DOSE CALCULATIONS 18 of 81 PROCEDURE NO, EPIP-09 ST. LUCIE PLANT ATTACHMENT 5 UNIT 2 - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 1 of 4)

1.

If a single effluent monitor channel is operable and on scale, Then use the value for that channel. If the channel is not on-scale, do not use the channel.

2.

If two effluent monitor channels for the same pathway are operable, on-scale, and display concentration values in the overlapping range, Then use the highest (most conservative) value.

3.

Unit 2 Effluent Monitor channels 604, 614 and 624 All provide values in jtCi/sec that should not be used for dose calculations These channels should not be used to identify or validate a release

4.

Wide Range Gas Monitor (WRGM) Effluent Monitors 0

Used on Unit 2 PV and ECCS A & B 0

Each monitor has three (3) gas channels; low, mid and high range Each monitor uses a 2 sample pump system; the LOW range gas channel utilizes a pump system which is independent of the MID and HIGH range gas channels pump system a

All three gas channels share a common alert and high alarm channel; once the alert or high alarm occurs, it will not occur again, regardless of the channel in operation.

REVISION NO' PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 19 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 5 UNIT 2 - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 2 of 4)

5.

SGTR NOTE Recall that evidence of a release may be confirmed / negated by use of backup instrumentation such as ARMs, CHRRMs or Plant Vent Particulate Iodine and Gas Monitors (PIGs). Health Physics survey results should also Sbe reviewed, as feasible.

Use a steamline channel only if the Safeties and / or Atmospheric Dumps are releasing steam. Otherwise, verify alignment of Steam Jet Air Ejector exhaust to the PV and utilize PV effluent monitor.

Steamline monitors on Unit 2 must be background corrected prior to use in the Release Rate calculation table. Use NET value (i.e., Channel Background).

EXAMPLE Channel 631 (S/G "A")

12 mr/hr Channel 632 (SIG "B") = 2.2 mr/hr Channel 633 (Bkgd) 2.0 mr/hr NET Value for SIG "A" = 10 mr/hr NET Value for SIG "B" = 0.2 mr/hr

6.

Fuel Handling Building (FHB) Pathway Verify alignment of the FHB exhaust system. During a high radiation condition in the Unit 2 FHB, exhaust may be diverted to the Shield Building and thus routed to the PV for discharge.

7.

CiS NOTE Containment design pressure = 44 psig.

Initiates:

° Prior to Containment Pressure reaching 3.5 psig When Containment Radiation is equal to or greater than 10 r/hr 0

At a SIAS

-J

REVISION NO.:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 20 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 5 UNIT 2 - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 3 of 4)

7.

(continued)

Isolates HVE 10A & B Auto starts HVE 6A & B and HVE 9A & B

8.

SIAS Initiates:

Prior to Containment Pressure reaching 3.5 psig When Pressurizer Pressure is equal to or less than 1736 psia Isolates HVE 10A & B Auto starts HVE 6A & B and HVE 9A & B Accident Type Release Pathway Fans Comments LOCA Plant Vent 6 & 10 10 Fans secure on SIAS / CIS ECCS 9

6 & 9 fans auto start on SIAS / CIS SGTR Plant Vent 6 & 10 Air Ejector aligned to PV Atmosphere N/A Atm. Dumps and Safeties Open FUEL HANDLING FHB Stack 15, 16 & 17 Divert to Shield Bldg. (PV) on Hi Rad Plant Vent 6 & 10 CASK DROP FHB Stack 15, 16 & 17 Divert to Shield Bldg. (PV) on Hi Rad Plant Vent 6&10 WGDTR Plant Vent 6&10 1

REVISION NO:

PROCEDURE TITLE PAGE.

7 OFF-SITE DOSE CALCULATIONS 21 of 81 PROCEDURE NO

,EPIP-09 ST. LUCIE PLANT ATTACHMENT 5 UNIT 2 - DATA INTERPRETATION Parameters, Pathways and Effluent Monitors (Page 4 of 4)

B.

(continued)

Effluent Monitor Channel #

Units Scale (min - max)

Typical (non-emergency)

Reading Plant Vent - LR 621 liCilcc I.OE 1.0E-01 High E-07

- MR 622 gICi/cc 1.2E 1.2E+03 Mid E-04

- HR 623 11Ci/cc 1.OE 1.OE+05 Low E-01 CHRRM - A 40 r/hr 1.OE+00 - 1.OE+08 High E-01 CHRRM - B 41 r/hr 1.OE+00 - 1.OE+08 Low E+00 Post LOCA - A 38 mr/hr 1.OE+01 - 1.OE+07 Low E+01 Post LOCA - B 39 mr/hr 1.OE+01 - 1.OE+07 Low E+01 ECCS - A - LR 601 giCi/cc 1.OE 1.OE-01 Low E-06

- MR 602

.tCilcc 1.2E 1.2E+03 Low E-03

- HR 603 jiCi/cc 1.0E 1.OE+05 High E-02 ECCS - B - LR 611 giCi/cc 1.OE 1.OE-01 Low E-06

- MR 612 itCi/cc 1.2E 1.2E+03 Low E-04

- HR 613

!gCi/cc 1.OE 1.0E+05 High E-02 9J7 Steamline - A 631 mr/hr 1.0E 1.0E+04 Low E-01 Steamline - B 632 mr/hr 1.0E 1.0E+04 Low E-01 Steamline Bkg.

633 mr/hr 1.OE 1.OE+04 Low E-01 Fuel Bldg. - LR 413 jLCi/cc 1.OE 1.OE-01 Low E-06 END OF ATTACHMENT 5

REVISION NO:

PROCEDURE TITLE' PAGE:

7 OFF-SITE DOSE CALCULATIONS 22 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 6 CLASS A MODEL DOSE CALCULATION (Page 1 of 6)

Discussion The computer-based Class A Model dose calculation program utilizes inputs and processes similar to the manual procedure. However, refinements in the Class A Model allow for a wider range of input information and mathematical complexity. These instructions provide the guidance for using the Class A Model to derive calculated off site doses in a manner similar to that discussed for the manual calculation. Not all input screens available in the computer program are needed by the general user and are, therefore not discussed in these instructions.

The Class A Model provides two (2) types of dose calculations. The "Actual Dose Calculation" is accomplished in advection steps of fifteen (15) or thirty (30) minutes and is a cumulative dose determination. The "Forecast Dose Calculation" is a projected dose determination based on a given time period such as two (2) hours. Personnel having expertise in dose calculation methodology may utilize the advanced methods available through the screen driven menus to modify and refine these basic calculations.

NOTE If both the Technical Support Center (TSC) and Emergency Operations Facility (EOF) are operational, dose assessment personnel at both locations should coordinate their efforts as a self-check to assure accuracy.

Computer Startup

1.

Ensure the uninterruptible power supply to the computer is energized to prevent data loss if a power interruption occurs.

2.

Ensure that the floppy disk drive is empty.

3.

Turn on the display monitor, the printer and the computer.

REVISION NO.:

PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 23 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 6 CLASS A MODEL DOSE CALCULATION (Page 2 of 6)

4.

Following system startup, check the date and time on the computer.

NOTE Correcting the date and time should be done prior to using a stand-alone computer. When using a computer on the LAN, contact a LAN administrator if the date and/or time need to be changed.

A.

If the dose calculation program starts, Then the date and time is shown in the upper left of the monitor.

B.

Correct the date and time as necessary (time should match ERDADS).

Changing the date/time.

1.

Depress Function Key F5 (to quit the Class A software).

2.

Type "Y".

3.

Depress the "ENTER" key.

4.

At the system prompt, type "TIME" (or "DATE" as required).

5.

Depress the "ENTER" key.

6.

Type correct data and depress "ENTER" key.

C.

If the dose calculation program does not start, Then the date and time is checked at the system prompt using Steps 4-6 above.

5.

When the computer displays the system prompt, and has correct date/time, type "FPL" and depress "ENTER" key to return to Class A software.

Pre-use QC Check

1.

If time and manpower permits, Then perform a pre-use verification QC check following the instructions in the FPL Class A Emergency Offsite Dose Calc Program User Guide.

2.

At the completion of the pre-use QC check, exit to the Main Menu, and proceed to step 3 of Performing Calculations, below.

REVISION NO' PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 24 of 81 PROCEDURE NO

EPIP-09 ST. LUCIE PLANT ATTACHMENT 6 CLASS A MODEL DOSE CALCULATION (Page 3 of 6)

NOTE If editing is required, edit the information in accordance with the displayed instructions.

Performing Calculations CAUTION Changing "Advection time step" after a calculation step can cause the Class A model to generate errors.

1.

When the plant site menu is displayed, Then depress the Function Key (i.e.,

F1-Unit 1 or F2-Unit 2) to select the affected St. Lucie Plant Unit.

2.

When the program asks, "Is this an exercise [Y/N]?", Then answer appropriately and depress the "ENTER" key.

3.

When the Main Menu is displayed, Then select the F1 Function Key to start calculations.

4.

When prompted by the program, 'Warning - Start calculations will destroy previous dose values. OK [Y/N]?", Then depress "Y" and the "ENTER" key to reinitialize the data files.

NOTE

1. Thirty minute advection steps are normally used except for fuel handling accidents, for which fifteen minutes advection time steps should be used.

2. Once advection time is selected it should not be changed while running the program to prevent generating errors.

5.

Select, from the General Accident Information Worksheet, the appropriate screen functions to edit the type of accident, reactor trip time, release start time, and advection step. Use the format shown on the screen by depressing the corresponding Function Keys, F1, F2, F3 or F4 respectively, Then depress "ENTER" after each new entry.

6.

When the correct type of accident, reactor trip time, release start time, and the advection time step have been entered, Then depress the F5 Function Key to accept the inputs.

REVISION NO PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 25 of 81 PROCEDURE NO.'

EPIP-09 ST. LUCIE PLANT ATTACHMENT 6 CLASS A MODEL DOSE CALCULATION (Page 4 of 6)

7.

When the Input Menu is displayed, Then depress the F1 Function Key to bring up the Meteorological Data menu.

8.

When the Meteorological Data Summary Menu is displayed, Select the data sheet corresponding to the source of the data (i.e., Site Tower (ERDADS, chart recorder), Airport (NOAA, NWS), Default).

9.

Enter the meteorological data gathered in the format shown using the displayed Function Keys, Then depress the "ENTER" key after each new entry.

10.

When all necessary meteorological data has been entered, Then depress the F5 Function Key to accept the data and go to the Meteorological data Summary Menu.

11.

Review the entered meteorological data, Depress the F5 Function Key to accept the data and Then return to the Input Menu.

12.

When the Input Menu is displayed, Then depress the F2 Function Key to bring up the Source Term Data menu.

13.

If the accident type is a LOCA or SGTR, Respond appropriately to the question about the Core Damage Situation.

14.

If the accident type is a LOCA, Respond appropriately to the question about the Iodine Removal System Status.

15.

When the Source Term Summary Menu is displayed, Select the data sheet corresponding to the source of the data (i.e., Grab Sampling, Effluent Monitors, CHRRM, Post LOCA Monitors, Default).

16.

Enter the source term data gathered in the format shown using the displayed Function Keys, Then depress the "ENTER" key after each new entry.

17.

When the input of source term information has been completed, Then depress the appropriate Function Key to accept the data and return to the Input Menu.

18.

If a final check of data accuracy is needed, Then depress the F3 Function Key to review a summary of the meteorological and source term data, Depress the F1 Function Key to print or the F2 Function Key to exit.

19.

If the meteorological or source term data need to be revised, Go to step 7 or step 12 above, respectively.

REVISION NO PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 26 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 6 CLASS A MODEL DOSE CALCULATION (Page 5 of 6)

20.

Depress the F4 Function Key at the screen prompt, "Proceed with calculations

[YIN]?", and answer "Y", Depress the "ENTER" key to begin calculations.

NOTE "CRT Displays" may be used instead of "Print Reports".

21.

When the Output Menu is displayed, Then depress the F3 Function Key to select "Print Reports".

22.

When the Printed Report Menu is displayed, Then depress the displayed Function Keys to select the desired reports.

CAUTION Ensure that the printer and print buffer are on line and ready for use prior to proceeding with the printing task. If either device is not ready for use, the computer will exit the dose calculation program.

23.

Depress any key to begin printing.

24.

When the Output Menu is displayed, Then depress the F6 Function Key to select the Run Mode Menu.

25.

When the Run Mode Menu is displayed, Then depress the F1 Function Key to select the Actual Calculation Mode and perform the next advection step (cumulative dose calculation) or depress the F2 Function Key to select the Forecast Calculation Mode.

26.

Edit the forecast period as desired using the displayed instructions.

27.

When the forecast period has been accepted, the Input Menu: Forecast Calculation Mode will be displayed, Then depress the displayed Function Keys to review and/or edit the inputs as necessary.

NOTE

1. Forecast periods are typically two (2) hours.

2. Forecast doses assume release rates and meteorological conditions remain constant during the forecasting period chosen.

3. Consider the reasonableness of assuming constant meteorological conditions and release rates for forecasting periods exceeding two (2) hours.

REVISION NO

PROCEDURE TITLE PAGE 7

OFF-SITE DOSE CALCULATIONS 27 of 81 PROCEDURE NO

EPIP-09 ST. LUCIE PLANT ATTACHMENT 6 CLASS A MODEL DOSE CALCULATION (Page 6 of 6)

28.

When all inputs are acceptable, Then depress the F4 Function Key to perform calculations, at the screen prompt, "Proceed with calculations V/N]?", and answer "Y", and Depress the "ENTER" key to begin calculations.

NOTE "CRT Displays may be used instead of "Print Reports".

29.

When the Output Menu - Forecast Calculations mode is displayed, Then depress the F3 Function Key to select "Print Reports".

30.

When the Printed Report Menu is displayed, Then depress the displayed Function Keys to select the desired reports.

CAUTION The printer and print buffer must be on line and ready!

31.

When the reports have been printed, Then return to the Run Mode Menu to update information and repeat the dose calculation process as needed due to release rate or meteorological changes.

32.

Depress the F1 Function Key for the Actual Calculation Mode or the F2 Function Key for the Forecast Calculation Mode or the F3 Function Key to return to the Main Menu and quit.

33.

Review the Summary of Met and Source Data displays for all subsequent calculations even if the inputs do not change so that they can be reviewed and accepted. Also ensure that the Noble Gas Reduction Factor is reset to its proper value.

END OF ATTACHMENT 6 NOTE

1. The Emergency Coordinator should be provided with a printout of actual calculated doses, Protective Action Recommendations (PARs), and as requested, forecasted doses.

2. The Emergency Coordinator should be updated every thirty minutes during periods of actual or potential off-site release.

REVISION NO.:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 28 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA (Page 1 of 10)

1.

Obtain Meteorological Data A.

Complete applicable pages from this attachment. Three methods are presented in preferential order. To supplement / complete any missing data in the chosen method, use one or both of the other methods. The methods are to be used in the order presented.

NOTE ERDADS and the Unit 1 Control Room and Site Met. Tower chart recorders provide 15 minute average data.

1.

Method 1 - Site Met Tower Provides data from the primary and alternate locations on the Site Meteorological Tower. Use Method 1.

2.

Method 2 - NOAA / NWS Provides meteorological observations taken at the National Oceanic Atmospheric Administration / National Weather Service in Melbourne, Fl. Use Method 2.

3.

Method 3 - Default Values Daytime and nighttime default values are listed in Method 3.

B.

Select Dose Calculation Worksheet

1.

The Worksheet to be used for Dose Calculations is determined as part of completing one of the Meteorological Data Methods.

2.

The Worksheet will be used to determine doses after a Release Rate Data Sheet is completed.

--- 1

REVISION NO

PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 29 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA METHOD 1 - SITE TOWER (Page 2 of 10)

(Page 1 of 3)

1.

Gather Meteorological Data:

A.

Date & Time of meteorological observations B.

Enter 10 Meter (alternate 57.9 Meter) WIND SPEED:

_________mph C.

Enter 10 Meter (alternate 57.9 Meter) WIND DIRECTION (from) --

deg.

D.

Enter Delta-T (displayed by ERDADS) deg. F E.

15 If Delta T is not available from ERDADS, Then:

1.

Enter the difference: 57.9 meter temperature minus 10 meter temperature:

2.

Multiply that difference by 1.044:

F.

If performing Class A Model dose calculation, Then use the above noted information during meteorological data entry.

G.

If performing manual dose calculations, Then proceed to Step 2 of this attachment.

I CAUTION Wind speed, wind direction and Delta temperature values should vary with time, i.e., chart recorders in the Unit 1 Control Room and AlA Site Tower Shack should NOT be straight-lining. Unchanging data should be investigated. If initial efforts to correct straight-lining fail, alternate sources of data may be used.

mph

REVISION NO:

PROCEDURE TITLE' PAGE 7

OFF-SITE DOSE CALCULATIONS 30 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA METHOD I - SITE TOWER (Page 3 of 10)

(Page 2 of 3)

2.

Determine STABILITY CLASS A.

Using Delta-T (AT) and the guide below, determine and enter the Stability Class If DELTA-T is Then Stability Class is less than or equal to -1.7 A

-1.6 to -1.5 B

-1.4 C

-1.3 to -0.5 D

-0.4 to +1.4 E

+1.5 to +3.6 F

greater than +3.6 G

3.

Determine AFFECTED SECTORS A.

Using the guide below, select and circle the AFFECTED SECTORS.

CAUTION Wind direction indicated as greater than 3590 should be corrected by subtractinnq 3600 from the indicated direction.

I NOTE If the wind direction is directly on the edge of two sectors (e.g., 11', 33, 560, etc.), an additional sector should be added to the Affected Sectors.

For example, if the wind direction is from 780, then the affected sectors should be L, M, N and P.

To avoid confusion, there is no sector "0" or "I".

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 I

II II I

I

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 31 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT

6.

Copy information to the selected DOSE CALCULATION WORKSHEET:

A.

WIND DIRECTION and the AFFECTED SECTORS to line A B.

WIND SPEED to line 2

7.

This data sheet is completed, proceed to release rate determination.

END OF METHOD 1 Stab. Seabreeze Dose Calc Stab. Seabreeze Dose Calc Stab.

Dose Calc Class Impa Worksheet Class Impact Worksheet Class Worksheet A

YES 1

D 7

A NO 2

C YES 5

E 8

B YES 3

C NO 6

F 9

B NO 4

G 10 ATTACHMENT 7 METEOROLOGICAL DATA METHOD I - SITE TOWER (Page 4 of 10)

(Page 3 of 3)

4.

Check for SEA BREEZE EFFECT:

Only if All of the following conditions are met, then the Sea Breeze effect is YES If one or more conditions are NOT met, then the Sea Breeze effect is NO 0

Stability Class A, B or C 0

Time of day 6 AM to 7PM Wind Direction (from) is between 0 through EAST to 180 degrees a

10 meter air temperature greater than HISTORICAL AVERAGE SURFACE WATER, listed below:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 69 65 69 73 76 79 80 81 81 79 74 71 Sea Breeze Impact (Yes or No)

5.

Select a DOSE CALCULATION WORKSHEET A.

Using the guide below, select a worksheet from Attachment 9.

REVISION NO' 7

PROCEDURE NO' EPIP-09 I

PROCEDURE TITLE OFF-SITE DOSE CALCULA ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA METHOD 2 - NOAA I NWS (Page 5 of 10)

(Page 1 of 5)

1.

Gather METEOROLOGICAL DATA:

A.

Call NOAA / National Weather Service (NWS) Melbourne Office. The phone number is located in the St. Lucie Plant Emergency Response Directory, Section 4.0, Off-site Support. When the NOAA / NWS person answers, identify yourself as a FPL - St. Lucie Plant and obtain the following information:

1.

Date / Time of observation:

2.

WIND DIRECTION (From):

Degrees

3.

WIND SPEED:

mph

4.

Sunrise:

am Sunset:_

pm

5.

Sky Condition (circle one): Clear Scattered Overcast Broken

a.

If sky condition is overcast or broken, Then enter Ceiling Height ft.

6.

Estimated air temperature for Ft. Pierce area OF

7.

If time permits, ask for a weather forecast for the area:

REVISION NO' PROCEDURE TITLE' PAGE 7

OFF-SITE DOSE CALCULATIONS 33 of 81 PROCEDURE NO" EPIP-09 ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA METHOD 2 - NOAA I NWS (Page 6 of 10)

(Page 2 of 5)

2.

Determine STABILITY CLASS A.

Determine the Solar Radiation Characteristic

1.

If Daytime (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after sunrise to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months before sunset), Then:

a.

Determine Solar Altitude from Figure 1 (at the end of this method sheet), using time and date.

b.

Circle the Solar Radiation Characteristic on the table below, using Sky Condition, Ceiling Height and Solar Altitude.

Day Sky

Ceiling, Solar Altitude Condition Feet

< 15 deg 15 to < 35 deg 35 to 60 deg

> 60 deg Overcast

< 7000 Nil Nil Nil Nil 7K to 16K Weak Weak Weak Slight

> 16000 Weak Weak Slight Moderate Broken

< 7000 Weak Weak Weak Slight 7K to 16K Weak Weak Slight Moderate

> 16000 Weak Slight Moderate Strong Clear not applicable Weak Slight Moderate Strong Scattered I

J

2.

If NOT Daytime, Then:

a.

Circle the Solar Radiation Characteristic on the table below, using Night Sky Condition and Ceiling Height.

Night Sky Condition Ceiling, Ft.

Solar Radiation Characteristic Overcast less than 7000 Nil 7000 or higher Weak Loss Broken not applicable Weak Loss Clear or scattered not applicable Strong Loss

REVISION NO:

PROCEDURE TITLE:

PAGE' 7

OFF-SITE DOSE CALCULATIONS 34 of 81 PROCEDURE NO.

EPIP-09 ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA (Page 7 of 10)

METHOD 2 - NOAA / NWS (Page 3 of 5)

2.

(continued)

B.

Select Stability Class

1.

Using the Wind Speed in MPH and the Solar Radiation Characteristic, find in the table below and circle the Stability Class.

Solar

__Wind Speed in MPH Radiation 0to >1.2to >3.5-

>5.8-

>6.9-

>8-

>10.4-

>11.5-

>12.7 1.2 3.5 5.8 6.9 8

10.4 11.5 12.7 Strong A

A A

B B

B C

C C

Moderate A

B B

C C

C D

Slight B

B C

C C

D D

Weak C

C C

D D

Nil D

D D

Weak Loss F

F E

E D

D D

StrongLoss G

G F

F E

E E

D D

Determine AFFECTED SECTORS A.

Using the guide below, select and circle the Affected Sectors.

NOTE

" If the wind direction is directly on the edge of two sectors (e.g. 110, 330, 560, etc.), an additional sector should be added to the Affected Sectors.

For example, if the wind direction is from 780, then the affected sectors should be L, M, N and P.

"* To avoid confusion, there is no sector "0" or "I".

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 I

3.

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 35 of 81 PROCEDURE NO.*

EPIP-09 ST. LUCIE PLANT ATTACHMENT 7 METEOROLOGICAL DATA METHOD 2 - NOAA I NWS (Page 8 of 10)

(Page 4 of 5)

4.

Check for SEA BREEZE EFFECT:

Only if ALL of the following conditions are met, then the Sea Breeze effect is YES.

If one or more conditions are NOT met, then the Sea Breeze effect is NO.

Stability Class A, B or C Time of day 6 AM to 7 PM Wind Direction (from) is between 0 through East to 180 degrees Sea Breeze Impact (Yes or No)

5.

Select a DOSE CALCULATION WORKSHEET A.

Using the guide below, select a worksheet from Attachment 9.

6.

Copy information to the selected DOSE CALCULATION WORKSHEET:

A.

From line 1A2, copy the WIND DIRECTION to line A of Dose Calculation Worksheet.

B.

From line 1A3, copy WIND SPEED in mph to line 2 of Dose Calculation Worksheet.

C.

From line 3A, copy the AFFECTED SECTORS to line A of Dose Calculation Worksheet.

7.

This data sheet is completed, proceed to release rate determination.

Stab. Seabreeze Dose Calc Stab. Seabreeze Dose Calc Stab.

Dose Cale Class Impact Worksheet Class Impact Worksheet Class Worksheet A

YES 1

D 7

A NO 2

C YES 5

E 8

B YES 3

C NO 6

F 9

B NO 4

1 G

10

II I I

I I

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I Ii C

ADJUSTED FOR DAYLIGHT SAVINGS TIME "7

EASTERN STANDARD TIME (EST) BLACK LINE E

EASTERN DAYLIGHT SAVINGS TIME (EDT) -GRAY aY

o 3020 0s WACson aoI oi l:[lliE

!lll 11 SOLAR ALTITUDE BY TIME OF DAY ST. LUCIE PLANT Is 5

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REVISION NO.

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 37 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT END OF ATTACHMENT 7 ATTACHMENT 7 METEOROLOGICAL DATA METHOD 3 - DEFAULT (Page 10 of 10)

(Page 1 of 1)

NOTE This method is to be used only if Site Met Tower and NOAAINWS data are not available.

If Daytime Hours (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after sunrise to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months before sunset), Then:

A.

Select DOSE CALCULATION WORKSHEET 7.

B.

Enter AFFECTED SECTORS = ALL in line A.

C.

Circle Default in line B.

D.

Enter WIND SPEED = 5 mph in line 2.

2.

If Not Daytime, Then:

A.

Select DOSE CALCULATION WORKSHEET 9.

B.

Enter AFFECTED SECTORS = ALL in line A.

C.

Circle Default in line B.

D.

Enter WIND SPEED = 3 mph in line 2.

This data sheet is completed, proceed to release rate determination.

END OF METHOD 3

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 38 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 1 of 23)

NOTE If both units are in a declared emergency and both units have or had a release, the site release rate is the sum of both units' release rates.

1.

Determine Site Release Rate A.

Complete applicable Data Sheet from this attachment, as appropriate for each affected unit and accident type. The five techniques are listed below in preferential order. Use the next techniques, in order, to supplement any missing data. Indicate the technique(s) used on the selected WORKSHEET from Attachment 9.

1.

CHEMISTRY GRAB SAMPLING - Primary Method for all accident types For Unit 1, use Data Sheet 1A.

For Unit 2, use Data Sheet 2A.

2.

EFFLUENT MONITORS - Alternate for all accident types, when Method 1 is unavailable.

For Unit 1, use Data Sheet 1 B.

For Unit 2, use Data Sheet 2B.

3.

CONTAINMENT HIGH RANGE RADIATION MONITOR - Alternate for LOCA only, when techniques 1 and 2 are unavailable.

Evaluate CHRRM readings by using Data Sheet 3.

NOTE Grab sampling is the primary method. It is unlikely that results will be available in the early phases of an emergency. Dose assessment should not be delayed waiting for these results. Therefore, the Effluent Monitor method may be used initially. Dose assessment using grab sample data should be performed as soon as that data is available.

REVISION NO.

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 39 of 81 PROCEDURE NO.*

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 2 of 23)

1.

A.

(continued)

4.

POST LOCA MONITORS - Alternate for LOCA only, when techniques 1, 2 and 3 are unavailable.

Evaluate Post LOCA Monitor readings by using Data Sheet 4.

5.

DEFAULT - Alternate for all accidents, only if no other technique is available.

For Default calculations for all accidents, use Data Sheet 5.

REVISION NO PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 40 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 3 of 23)

DATA SHEET 1A UNIT 1 GRAB SAMPLE (Page 1 of 4)

1.

Gather ACCIDENT DATA:

A.

Date and time of data:

B.

Ask Emergency Coordinator:

I.

Accident Type

2.

Is core overheating or melting (circle): YES NO

a.

If YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from Data Sheet 5):

hours

2.

Evaluate applicable RELEASE PATHWAY(S):

A.

Based on Accident Type, select release pathway in the following table.

B.

Check the ON fans.

C.

Add up the flows in the spaces provided.

UNIT 1-PLANT VENT Shield Bldg H2 Purge RCB Exhaust RAB Exhaust 4on

¶4,6 SCFM 6600 6600 950 950 52500 52500 93250 93250 (Add) Plant Vent Total =

UNIT 1-FUEL BUILDING Fan 4on

¶4 SCFM 1-HVE-15 New Fuel 1056&

1-HVE-16A Fuel Pool 1138 1-HVE-16B 1138.

1-HVE-17 H&V Room 6250 (Add) Fuel Bldg. Total =

Fan 1-HVE-9A 1 -HVE-9B ECCS AREA 4 On

¶4 SCFM 33000 33000 D.

Enter total pathway SCFM in the table below (Step 4) in the column labeled "SCFM".

-X

-4 Fan 1 -HVE-6A 1-HVE-6B 1 -HVE-7A 1 -HVE-7B 1-HVE-8A 1-HVE-8B 1-HVE-10A 1 -HVE-10 B 3 5 5

REVISION NO PROCEDURE TITLE PAGE*

7 OFF-SITE DOSE CALCULATIONS 41 of 81 PROCEDURE NO*

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 1A RELEASE RATE DATA UNIT I GRAB SAMPLE (Page 4 of 23)

(Page 2 of 4)

NOTE Chemistry Grab Sample results can be obtained from the TSC Chemistry Supervisor or TSC Dose Assessor.

3.

Enter GRAB SAMPLE DATA:

A.

Enter grab sample assay results for Gross Noble Gas pCi/cc concentration in the table below (Step 4) in the column labeled "pCi/cc".

B.

Enter grab sample assay results for DEQ Iodine-131 pCi/cc concentration in the table below (Step 4) in the column labeled "pCi/cc".

1.

If DEQ Iodine-131 pCi/cc concentration is unavailable, perform Step 4 for Noble Gas concentration only.

4.

Determine UNIT 1 RELEASE RATE:

A.

Complete the table below:

(pCi/cc x SCFM x factor = Ci/sec)

Pathway TYPE pCi/cc

¶4 SCFM factor Noble Gas, Ci/sec Iodine, Ci/sec Noble Gas Plant Vent Iodine 4.72 E -04 Noble Gas Fuel Bldg.

Iodine 4.72 E -04 Noble Gas ECCS - A Iodine 33,000 4.72 E -04 Noble Gas ECCS - B Iodine 33,000 4.72 E -04 Summation of Unit 1 Grab Sample Release Rate(s)

-4

REVISION NO:

PROCEDURE TITLE.

PAGE:

7 OFF-SITE DOSE CALCULATIONS 42 of 81 PROCEDURE NO

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 5 of 23)

DATA SHEET 1A UNIT I GRAB SAMPLE (Page 3 of 4)

4.

(continued)

B.

If DEQ Iodine-1 31 grab sample results are not available, Then estimate the Iodine Release Rate by:

1.

Select Iodine Factor based on current Accident Type and Release Pathway.

PATHWAY LOCA SGTR MSLB WASTE GAS FUEL CASK DTR HANDLING DROP Plant Vent 0.01

1. E-06 1.0

4. E-05 0

0 ECCS 0.01 0

0 0

Fuel Bldg.

0 0

0.04 1.3 Steamline 0

1. E-03 0

0 0

0

2.

Enter Gross Noble Gas Ci/sec and Iodine Factor in the following equation and perform the calculation.

x Gross Noble Gas Ci/sec Iodine Factor DEQ Iodine 131 Ci/sec

3.

Enter DEQ Iodine 131 Ci/sec in the appropriate column in the table in Step 5.

5.

Determine the SITE RELEASE RATE:

A.

Complete the table below:

Noble Gas, Cilsec Iodine, Ci/sec Add summation from 4A and 4B to obtain Unit 1 release rates determined above IF Unit 2 is AFFECTED, enter its release rates If Unit 2 is affected, Then add release rates from Unit 1 and Unit 2 to obtain the SITE RELEASE RATES

-J

REVISION NO:

PROCEDURE TITLE*

PAGE:

7 OFF-SITE DOSE CALCULATIONS 43 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT END OF DATA SHEET 1A ATTACHMENT 8 DATA SHEET 1A RELEASE RATE DATA UNIT 1 GRAB SAMPLE (Page 6 of 23)

(Page 4 of 4)

6.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle Grab Sample.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

7.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

REVISION NO.:

PROCEDURE TITLE' PAGE' 7

OFF-SITE DOSE CALCULATIONS 44 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 7 of 23)

DATA SHEET 2A UNIT 2 GRAB SAMPLING (Page 1 of 4)

1.

Gather ACCIDENT DATA:

A.

Date and time of data:

B.

Ask Emergency Coordinator:

1.

Accident Type

2.

Is core overheating or melting (circle): YES NO

a.

If YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from Data Sheet 5):

hours

2.

Evaluate applicable RELEASE PATHWAY(S):

A.

Based on Accident Type, select release pathway in the following table.

B.

Check the ON fans.

C.

Add up the flows in the spaces provided.

UNIT 2-PLANT VENT UNIT 2-FUEL BUILDING If NOT Diverted to Plant Vent, Use Stated Flow Shield Bldg H2 Purge RCB Exhaust RAB Exhaust 2-HVE-1 OB (Add) Plant Vent Total =

-on 114,6 SCFM 6600 6600 2500 2500 52500 52500

__106913 106913 Fan Ion 14 SCFM 2-HVE-15 New Fuel 1212 2-HVE-16A Fuel Pool 1250 2-HVE-16B Fuel Pool 1250 2-HVE-17 Bldg H&V 750(

(Add) Fuel Bldg. Total =

ECCS AREA Fan 2-HVE-9A 2-HVE-9B 5

0 0

/on 14 SCFM 33000 33000

-X

-4 D.

Enter total pathway SCFM in the table below (Step 4) in the column labeled "SCFM".

-J Fan 2-HVE-6A 2-HVE-6B 2-HVE-7A 2-HVE-7B 2-HVE-8A 2-HVE-8B 2-HVE-10A

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 45 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 8 of 23)

DATA SHEET 2A UNIT 2 GRAB SAMPLING (Page 2 of 4)

NOTE Chemistry Grab Sample results can be obtained from the TSC Chemistry Supervisor or TSC Dose Assessor.

3.

Enter GRAB SAMPLE DATA:

A.

Enter grab sample assay results for Gross Noble Gas pCi/cc concentration in the table below (Step 4) in the column labeled "pCi/cc".

B.

Enter grab sample assay results for DEQ Iodine-131 pCi/cc concentration in the table below (Step 4) in the column labeled "pCi/cc".

1.

If DEQ Iodine-131 pCi/cc concentration is unavailable, perform Step 4 for Noble Gas concentration only.

4.

Determine UNIT 2 RELEASE RATE:

A.

Complete the table below:

(pCilcc x SCFM x factor = Ci/sec)

Pathway Plant Vent TYPE Noble Gas Iodine pCi/cc T4 SCFM factor Noble Gas, Ci/sec Iodine, Ci/sec I -

. -,

4.72 E-04 Noble Gas Fuel Bldg.

4.72 E-04 Iodine Noble Gas ECCS - A 33,000 4.72 E -04 Iodine ECCS-B Noble Gas 33,000 4.72 E-04 1Summation of Unit 2 Grab Sample Release Rate(s)

Iodine 11

REVISION NO

PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 46 of 81 PROCEDURE NO

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 9 of 23)

DATA SHEET 2A UNIT 2 GRAB SAMPLING (Page 3 of 4)

4.

(continued)

B.

If DEQ Iodine-131 grab sample results are not available, Then estimate the Iodine Release Rate by:

1.

Select Iodine Factor based on current Accident Type and Release Pathway.

PATHWAY LOCA SGTR MSLB WASTE GAS FUEL CASK DTR HANDLING DROP Plant Vent 0.01

1. E-06 1.0

4. E-05 0.04 1.3 ECCS 0.01 0

0 0

Fuel Bldg.

0 0

0.04 1.3 Steamline 0

1. E-03 0

0 0

0

2.

Enter Gross Noble Gas Ci/sec and Iodine Factor in the following equation and perform the calculation.

x Gross Noble Gas Ci/sec Iodine Factor DEQ Iodine 131 Ci/sec

3.

Enter DEQ Iodine 131 Ci/sec in the appropriate column in the table in Step 5.

5.

Determine the SITE RELEASE RATE:

A.

Complete the table below:

Noble Gas, Cilsec [Iodine, Cilsec Add summation from 4A and 4B to obtain the Unit 2 release rates determined above IF Unit I is AFFECTED, enter its release rates If Unit 1 is affected, Then add the release rates from Unit 2 and Unit I to obtain the SITE RELEASE RATES

-J

-4

REVISION NO:

PROCEDURE TITLE' PAGE' 7

OFF-SITE DOSE CALCULATIONS 47 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT END OF DATA SHEET 2A ATTACHMENT 8 DATA SHEET 2A RELEASE RATE DATA UNIT 2 GRAB SAMPLING (Page 10 of 23)

(Page 4 of 4)

6.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle Grab Sample.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

7.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

REVISION NO' PROCEDURE TITLE.

PAGE' 7

OFF-SITE DOSE CALCULATIONS 48 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 1B RELEASE RATE DATA UNIT 1 EFFLUENT MONITOR (Page 11 of 23)

(Page 1 of 3)

1.

Gather ACCIDENT DATA:

A.

Date and time of data:

J B.

Ask Emergency Coordinator:

1.

Accident Type

2.

Is core overheating or melting (circle): YES NO

a.

If YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from Data Sheet 5):

hours

2.

Evaluate applicable RELEASE PATHWAY(S):

A.

Based on Accident Type, select release pathway in the following table.

B.

Check the ON fans.

C.

Add up the flows in the spaces provided.

UNIT 1-PLANT VENT Shield Bldg H2 Purge RCB Exhaust RAB Exhaust

'4Of 114,6 SCFM 6600 6600 950 950 52500 52500 93250 93250 UNIT 1-FUEL BUlL' Fan 1HVE-15 New Fuel 1-HVE-16A Fuel Pool 1-HVE-16B 1-HVE-17 H&V Room (Add) Fuel Bldg. Total =

ECCS AREA Fan DING Ion

¶4 SCFM 10563 11385 11385 6250 4on 14 SCFM (Add) Plant Vent Total =

1 -HVE-9A 1-HVE-9B D.

Enter total pathway SCFM in the table below (Step 5) in the column labeled "SCFM".

-4 Fan 1-HVE-6A 1-HVE-6B 1-HVE-7A 1 -HVE-7B 1-HVE-8A 1-HVE-8B 1 -HVE-10A 1-HVE-10B

-4 33000 33000

REVISION NO:

PROCEDURE TITLE' PAGE:

7 OFF-SITE DOSE CALCULATIONS 49 of 81 PROCEDURE NO EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 1B RELEASE RATE DATA UNIT 1 EFFLUENT MONITOR (Page 12 of 23)

3.

Enter EFFLUENT MONITOR DATA:

(Page 2 of 3)

NOTE provides additional information on effluent monitor selection based on accident type and release pathway.

A.

B.

4.

Input A.

Based on Release Pathway, select applicable Effluent Monitor.

Enter monitor data in the table below (Step 5) in the column labeled "DATA".

IODINE FACTOR:

Select Iodine Factor based on current Accident Type and Release Pathway.

PATHWAY LOCA SGTR MSLB WASTE FUEL CASK GAS DTR HANDLING DROP Plant Vent 0.01

1. E-06 1.0

4. E-05 0

0 ECCS 0.01 0

0 0

Fuel Bldg.

0 0

0.04 1.3 Steamline 0

1. E-03 0

0 0

0 B.

Enter in the table below (Step 5) in the column labeled "IF".

5.

Determine Unit I RELEASE RATE:

A.

Complete the table below:

(DATA x SCFM x factor = N.G. Ci/sec x Iodine Factor = Iodine Ci/sec)

Pathway DATA T4 SCFM factor Noble Gas, Ci/sec IF Iodine Ci/sec Plant Vent uCi/cc 4.72 E-04 ECCS-A uCi/cc 33,000 4.72 E-04 ECCS-B uCi/cc 33,000 4.72 E-04 Fuel Bldg.

uCi/cc 4.72 E-04 Steamline A mr/hr 1.0 1.24 E-02 Steamline B mr/hr 1.0 1.24 E-02 Summation of Unit I Effluent Monitor Release Rate(s)

XJ

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 50 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET lB RELEASE RATE DATA UNIT 1 EFFLUENT MONITOR (Page 13 of 23)

(Page 3 of 3)

6.

Determine the Site Release Rate.

A.

Complete the table below:

7.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle Effluent Monitor.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

8.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

END OF DATA SHEET 1B Noble Gas, Ci/sec Iodine, Ci/sec Enter the summation of Unit I release rates determined from this worksheet IF Unit 2 is AFFECTED, enter its release rates If Unit 2 is affected, Then add the release rates for Unit 1 and Unit 2 to obtain the SITE RELEASE RATES

REVISION NO' PROCEDURE TITLE PAGE.

7 OFF-SITE DOSE CALCULATIONS 51 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT I

ATTACHMENT 8 DATA SHEET 2B RELEASE RATE DATA UNIT 2 EFFLUENT MONITOR (Page 14 of 23)

(Page 1 of 3)

1.

Gather ACCIDENT DATA:

A.

Date and time of data:

B.

Ask Emergency Coordinator:

1.

Accident Type

2.

Is core overheating or melting (circle): YES NO

a.

If YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from Data Sheet 5):

hours

2.

Evaluate applicable RELEASE PATHWAY(S):

A.

Based on Accident Type, select release pathway in the following table.

B.

Check the ON fans.

C.

Add up the flows in the spaces provided.

UNIT 2 - PLANT VENT UNIT 2 - FUEL BUILDING IF NOT DIVERTED Fan 4on 14.6 Fan 4on 14 SCFM SCFM 2-HVE-6A Shield Bldg 6600 2HVE-15 New Fuel 12125 2-HVE-6B 6600 2-HVE-16A Fuel Pool 12500 2-HVE-7A H2 Purge 2500 2-HVE-16B 6

12500 2-HVE-7B_

2500 2-HVE-17 H&V Room 7500 2-HVE-8A RCB Exhaust 52500 (Add) Fuel Bldg. Total =

2-HVE-8B 52500 ECCS AREA 2-HVE-1OA RAB Exhaust 106913 Fan 4on

$4 SCFM 2-HVE-10B 106913 2-HVE-9A 33000 (Add) Plant Vent Total =

_2-HVE-9B 33000 D.

Enter total pathway SCFM in the table below (Step 5) in the column labeled "SCFM".

REVISION NO" PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 52 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 2B RELEASE RATE DATA UNIT 2 EFFLUENT MONITOR (Page 15 of 23)

3.

Enter EFFLUENT MONITOR DATA:

(Page 2 of 3)

NOTE provides additional information on effluent monitor selection based on accident type and release pathway.

A.

B.

4.

Input A.

Based on Release Pathway, select applicable Effluent Monitor.

Enter monitor data in the table below (Step 5) in the column labeled "DATA".

IODINE FACTOR:

Select Iodine Factor based on current Accident Type and Release Pathway.

PATHWAY LOCA SGTR MSLB WASTE FUEL CASK GAS DTR HANDLING DROP Plant Vent 0.01

1. E-06 1.0

4. E-05 0.04 1.3 ECCS 0.01 0

0 0

Fuel Bldg.

0 0

0.04 1.3 Steamline 0

1. E-03 0

0 0

0 B.

Enter under "IF" Column in Step 5.

5.

Determine RELEASE RATE:

A.

Complete the table below:

(DATA x SCFM x factor = N.G. Cilsec x Iodine Factor = Iodine Cilsec)

Pathway DATA

¶4 SCFM factor Noble Gas, Ci/sec IF Iodine Ci/sec Plant Vent uCi/cc 4.72 E-04 ECCS-A uCi/cc 33,000 4.72 E-04 ECCS-B uCi/cc 33,000 4.72 E-04 Fuel Bldg.

uCi/cc 4.72 E-04 Steamline A mr/hr 1.0 1.24 E-02 Steamline B mr/hr 1.0 1.24 E-02 Summation of Unit 2 Effluent Monitor Release Rates

'II[

B

REVISION NO:

PROCEDURE TITLE' PAGE:

7 OFF-SITE DOSE CALCULATIONS 53 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 2B RELEASE RATE DATA UNIT 2 EFFLUENT MONITOR (Page 16 of 23)

(Page 3 of 3)

6.

Determine the Site Release Rate A.

Complete the table below:

7.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle Effluent Monitor.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

8.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

END OF DATA SHEET 2B Noble Gas, Ci/sec I i Iodine, Ci/sec Enter the summation of Unit 2 release rates determined from this worksheet IF Unit 1 is AFFECTED, enter its release rates If Unit I is affected, Then add the release rates from Unit 2 and Unit 1 to obtain the SITE RELEASE RATES

REVISION NO.:

PROCEDURE TITLE:

PAGE*

7 OFF-SITE DOSE CALCULATIONS 54 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 3 RELEASE RATE DATA UNIT 1 OR 2 CHRRM (Page 17 of 23)

(Page 1 of 3)

NOTE If both units are using this method, then complete one worksheet for each unit.

1.

Gather ACCIDENT DATA:

A.

Unit # (circle): 1 2

B.

Date and time of data:

J C.

Ask Emergency Coordinator:

1.

Accident Type

2.

Is core overheating or melting (circle): YES NO

a.

If YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from Data Sheet 5):

hours

2.

Obtain CHRRM READING and HOURS SINCE REACTOR TRIP:

A.

Highest CHRRM reading:

R/hr; B.

Copy the CHRRM reading in R/hr to Steps 5A and B.

C.

Date and Time of Reactor Trip:

/

D.

Hours Since Reactor Trip:

hours;

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 55 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA DATA SHEET 3 UNIT I OR 2 CHRRM (Page 18 of 23)

(Page 2 of 3)

3.

Determine CORE FRACTION FACTOR (CF):

A.

In the table below, find the CF that corresponds with Hours Since Reactor Trip.

B.

Enter CF value in Steps 5A and B.

Hours Since Reactor Trip CF Hours Since Reactor Trip CF 5.00 E - 07

>2.0 to: 4.0

> 0 to* 0.5 1.00 E - 06

> 4.0 to < 8.0 1.25 E - 05 1.67 E - 06

> 8.0

> 1.0 to < 2.0 3.33 E - 06

4.

Determine NOBLE GAS REDUCTION FACTOR (NGRF):

A.

Find NGRF in the table below.

B.

Enter it in Step 5A.

Hours Since NGRF Hours Since NGRF Hours Since NGRF Hours Since NGRF Rx Trip Rx Trip Rx Trip Rx Trip 0

1.0

> 4 to* 5 0.44

> 9 to* 10 0.26

> 14 to* 15 0.16

>0to___1 0.90

>5to_6 0.39

>10to<11 0.23

> 15to__ 16 0.16

>1to<2 0.70

>6to<7 0.35

> 11to_<12 0.21

> 16to*< 17 0.14

2 to* 3 0.60

> 7 to* 8 0.32

> 12 to 5 13 0.19

> 17 to* 18 0.14

>3to_<4 0.50

>8to_<9 0.28

> 13to_<14 0.18

>18 0.13

5.

Determine RELEASE RATES:

A.

Calculate the Noble Gas Release Rate:

S...

A #Ii R/hr x (CF) x (NGRF) X '+U =

GoDIe uas,I B.

Calculate Iodine Release Rate:

i.

If the Iodine Removal System IS in use, Then Iodine Conversion Value (ICV) = 0.6, If NOT in use, Then ICV = 1.6.

R/hr x (CF) x (ICV) =

Iodine Ci/sec L I I I

'seci 0

>0.5 to:1.0 6.25 E - 06 2.22 E - 05 Isec

REVISION NO.:

PROCEDURE TITLE*

PAGE 7

OFF-SITE DOSE CALCULATIONS 56 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT END OF DATA SHEET 3 ATTACHMENT 8 DATA SHEET 3 RELEASE RATE DATA UNIT 1 OR 2 CHRRM (Page 19 of 23)

(Page 3 of 3)

6.

Determine the SITE RELEASE RATE:

A.

Complete the table below.

F Noble Gas Iodine Enter the release rates determined from this worksheet IF the other Unit is AFFECTED, enter its release rates If both units are affected, Then add the release rates from both units to obtain the SITE RELEASE RATES

7.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle CHRRM.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

8.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

REVISION NO:

PROCEDURE TITLE.

PAGE.

7 OFF-SITE DOSE CALCULATIONS 57 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT Post Loca Noble Gas Iodine Release Rate, (Ci/sec)

Monitor Reading Release Rate with Iodine Removal System (mR/hr)

(Ci/sec)

In Use Not in Use

< 60 Negligible Negligible Negligible

> 605 _100 2.0 0.03 0.1

> 100* 1000 10.0 0.14 0.4

> 1000 40.0 0.60 1.6 ATTACHMENT 8 DATA SHEET 4 RELEASE RATE DATA UNIT 1 OR 2 POST LOCA (Page 20 of 23)

(Page 1 of 2)

NOTE If both units are using this method, then complete one worksheet for each unit.

1.

Gather ACCIDENT DATA.

A.

Unit # (circle): 1 2

B.

Date and time of data:

J C.

Ask Emergency Coordinator:

1.

Accident Type

2.

Is core overheating or melting (circle): YES NO

a.

If YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from Data Sheet 5):

hours

2.

Obtain POST LOCA READING:

A.

From Unit #

, record the Highest POST LOCA reading mR/hr

3.

Determine Unit RELEASE RATE:

A.

Based on the 2A, find the release rates in the table below.

B.

Enter them in Step 4.

REVISION NO.*

PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 58 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 21 of 23)

4.

Determine the SITE RELEASE RATE:

A.

Complete the table below.

Enter the AFFECTED Unit's release rates determined from this worksheet IF the other Unit is AFFECTED enter its release rates If both units are affected, Then add the release rates for both Units to obtain the SITE RELEASE RATES DATA SHEET 4 UNIT I OR 2 POST LOCA (Page 2 of 2)

Noble Gas Iodine

5.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle Post LOCA.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

6.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

END OF DATA SHEET 4

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 59 of 81 PROCEDURE NO '

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 RELEASE RATE DATA (Page 22 of 23)

DATA SHEET 5 UNIT I OR 2 DEFAULT (Page 1 of 2)

I

~CAUTION Use this method only if there is no data to use in other methods.

Gather ACCIDENT DATA:

A.

Unit # (circle): 1 2

B.

Date and time of data:

J C.

Ask Emergency Coordinator:

1.

Accident Type NOTE Refer to definition for Core Overheating / Melting (in Section 4.0 of this procedure). If all criteria unknown, answer is YES (=default).

2.

Is core overheating or melting (circle): YES NO

a.

if YES, PF = 4.4; If NO, PF = 1.0

b.

Enter PF =

3.

Potential DURATION of release (if unknown, use Default Duration from the table below):

hours

2.

Determine the SITE RELEASE RATE:

A.

For the accident type, select and circle the Noble Gas and Iodine Release Rates in the table below.

Accident Type Default Release Rates, Ci/sec Duration Noble Gas Iodine LOCA WITHOUT 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 37 1.6 Iodine Removal System in use LOCA WITH 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 37 0.6 Iodine Removal System in use Steam Generator Tube Rupture 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.0 4.0 E -05 Main Steam Line Break 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.04 0.01 Fuel Handling 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 11 4.0 E - 03 Cask Drop 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.0 0.03 Waste Gas Decay Tank Rupture 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2.0 2.0 E - 06 1.

-4

REVISION NO PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 60 of 81 PROCEDURE NO.*

EPIP-09 ST. LUCIE PLANT ATTACHMENT 8 DATA SHEET 5 RELEASE RATE DATA UNIT 1 OR 2 DEFAULT (Page 23 of 23)

(Page 2 of 2)

2.

(continued)

B.

Complete the table below.

Noble Gas Iodine Enter the release rates determined from this worksheet IF the other Unit is AFFECTED enter its release rates If both units are affected, Then add the release for both Units to obtain the SITE RELEASE RATES

3.

Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET:

A.

On line C, circle Default.

B.

Enter the NOBLE GAS RELEASE RATE into line 8.

C.

Enter the IODINE RELEASE RATE into line 1.

D.

Enter the DURATION (if 2 affected units, use longest) into line 6.

E.

Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11.

4.

This data sheet is completed, follow the instructions on the DOSE CALCULATION WORKSHEET.

END OF DATA SHEET 5 END OF ATTACHMENT 8

REVISION NO.:

7 PROCEDURE NO.:

EPIP-09 I

PROCEDURE TITLE:

OFF-SITE DOSE CALCULj ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 1 of 10)

WORKSHEET I Stability Class = A Seabreeze = YES A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors B.

Circle Meteorological Data Source(s) used:

ERDADS I Tower NOAA I NWS Default C.

Circle Release Rate Method used. (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 / 12 D.

Date and time of data from release rate determination:

I Follnw the instructions to calculate doses @

line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3 Divide line 1 by line 2 4

Iodine Dose Factors, 2.3E+04 8.1E÷03 2.3E+03 8.0E+02 5 Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 mile 2 miles 5 miles 10 miles 8

Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Nobel Gas Dose Factors 5.0 2.6 0.73 0.26 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 1 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF)

E.

Dose Calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET I

REVISION NO:

PROCEDURE TITLE:

PAGE.

7 OFF-SITE DOSE CALCULATIONS 62 of 81 PROCEDURE NO" EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 2 of 10)

WORKSHEET 2 Stability Class = A Seabreeze = NO A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors B.

Circle Meteorological Data Source(s) used:

ERDADS I Tower NOAA I NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 / 12 D.

Date and time of data from release rate determination:

/

Follow the instructions to calculate doses @

line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles I

Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3

Divide line 1 by line 2 4

Iodine Dose Factors, 38E+03 1.8E+03 7.9E+02 4.OE+02 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8 Enter NOBLE GAS RELEASE RATE, Cilsec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 0.82 0.57 0.25 0.13 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0 04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 2

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 63 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 3 of 10)

WORKSHEET 3 Stability Class = B Seabreeze = YES A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors B.

Circle Meteorological Data Source(s) used:

ERDADS / Tower NOAA I NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 / 12 D.

Date and time of data from release rate determination, I

line Instruction for THYROID DOSES (ODE) 1 Mile 2 Miles 5 Miles 10 Miles I

Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3

Divide line 1 by line 2 4

Iodine Dose Factors, 3.0E+04 1.1E+04 3.0E+03 1.1E+03 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF 7 1 Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 9.6 3.4 0.97 0.36 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE I

SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply ine 16 by line 17 to obtain TOTALTI I

PAR DOSE (TEDE),

mrem i

1 1

idoenEO 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HIP Manager if done in EOF}

Follow the Instructions to calculate doses @

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 3

REVISION NO:

7 PROCEDURE NO*

EPIP-09

____________________________.1 PROCEDURE TITLE:

OFF-SITE DOSE CALCULATION ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 4 of 10)

WORKSHEET 4 Stability Class = B Seabreeze = NO A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors B.

Circle Meteorological Data Source(s) used:

ERDADS I Tower NOAA / NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 / 12 D.

Date and time of data from release rate determination:

/

line Instruction for THYROID DOSES (CDE)

I Mile 2 Miles 5 Miles 10 Miles 1

Enter the IODINE RELEASE RATE, Ci/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line 1 by line 2 4

Iodine Dose Factors, 2.3E+04 6.OE+03 1.1E+03 5.7E+02 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mremlhr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem L

line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 byline 11 13 Noble Gas Dose Factors 7.4 1.9 0.36 0.18 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

lFnllnw thep instructions to calculate doses (*

Dose calculations completed; continue monitoring releases and assessing doses END OF WORKSHEET 4

REVISION NO.:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 65 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 5 of 10)

WORKSHEET 5 Stability Class = C Seabreeze = YES A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors_

B.

Circle Meteorological Data Source(s) used:

ERDADS / Tower NOAA / NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default Attachment, 10 / 12 D.

Date and time of data from release rate determination:

/

Follow the instructions to calculate doses @

line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line 1 by line 2 4

Iodine Dose Factors, 6.0 E + 04 1.7 E + 04 3.9 E + 03 1.5 E + 03 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem 1_

line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Cilsec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 19.0 5.3 1.2 0.48 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mremr 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 5

REVISION NO*

PROCEDURE TITLE PAGE:

7 OFF-SITE DOSE CALCULATIONS 66 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 6 of 10)

WORKSHEET 6 Stability Class = C Seabreeze = NO A.

Enter Meteorological Summary Data.

Unit_

Wind Direction From Affected Sectors_

B.

Circle Meteorological Data Source(s) used:

ERDADS / Tower NOAA / NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0/12 D.

Date and time of data from release rate determination:

/

Follow the Instructions to calculate doses @

MieI I

5Miles I lMiles10Me line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 1

Enter the IODINE RELEASE RATE, Ci/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line I by line 2 4

Iodine Dose Factors, 6.OE+04 1.7E+04 3.3E+03 9.5E+02 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 19.0 5.3 1.0 0.30 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 6

REVISION NO.:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 67 of 81 PROCEDURE NO0 EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 7 of 10)

WORKSHEET 7 Stability Class = D Seabreeze = NO A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors_

B.

Circle Meteorological Data Source(s) used:

ERDADS / Tower NOAA / NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 / 12 D.

Date and time of data from release rate determination:

/

Follow the instructions to calculate doses @

line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles I

Enter the IODINE RELEASE RATE, Cil/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line I by line 2 4

Iodine Dose Factors, 1.7E+05 6.0E+04 1.7E+04 5.7E+03 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 53.0 19.0 5.3 1.8 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mremr 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 7

REVISION NO.'

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 68 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 8 of 10)

WORKSHEET 8 Stability Class = E Seabreeze = NO A.

Enter Meteorological Summary Data:

Unit_

Wind Direction From Affected Sectors_

B.

Circle Meteorological Data Source(s) used:

ERDADS / Tower NOAA I NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 / 12 D.

Date and time of data from release rate determination:

J line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles I

Enter the IODINE RELEASE RATE, Ci/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line 1 by line 2 4

Ilodine Dose Factors, 3.0E+05 1.2E+05 3.8E÷04 1.4E+04 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE)

I Mile 2 Mles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Cilsec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 940 39.0 12.0 4.5 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE 7

SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

Fniinw th inRtructions to calculate doses (2 E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 8 S.

A

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 69 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 9

,MANUAL DOSE CALCULATION (Page 9 of 10)

WORKSHEET 9 Stability Class = F Seabreeze = NO A.

Enter Meteorological Summary Data:

Unit Wind Direction From Affected Sectors_

B.

Circle Meteorological Data Source(s) used:

ERDADS /Tower NOAA I NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0 /12 D.

Date and time of data from release rate determination:

/

Follow the instructions to calculate doses @

line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles I

Enter the IODINE RELEASE RATE, Ci/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line 1 by line 2 4

Iodine Dose Factors, 5.3E+05 2.5E+05 7.9E+04 3.5E+04 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE)

I Mile 2 Miles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 1NobleGasDoseFactors 1.7E+02 7.8E+01 2.5E+01 1.1E+01 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem PAR 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 9

REVISION NO:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 70 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 9 MANUAL DOSE CALCULATION (Page 10 of 10)

WORKSHEET 10 Stability Class = G Seabreeze = NO A.

Enter Meteorological Summary Data:

Unit_

Wind Direction From Affected Sectors_

B.

Circle Meteorological Data Source(s) used.

ERDADS / Tower NOAA I NWS Default C.

Circle Release Rate Method used: (if dual unit, then indicate Method for each unit)

Grab Sample Effluent Monitor CHRRM POST LOCA Default 0/12 D.

Date and time of data from release rate determination:

I Follow the instructions to calculate doses @

line Instruction for THYROID DOSES (CDE)

I Mile 2 Miles 5 Miles 10 Miles 1

Enter the IODINE RELEASE RATE, Ci/sec SNF 2

Enter the WIND SPEED, mph SNF 3

Divide line I by line 2 4

Iodine Dose Factors, 9.1E+05 4.7E+05 1.8E+05 7.9E+04 5

Multiply line 3 by line 4 to obtain THYROID SNF DOSE RATE (CDE), mrem/hr 6

Enter DURATION of release, hours SNF 7

Multiply line 5 by line 6 to obtain PROJECTED PAR THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8

Enter NOBLE GAS RELEASE RATE, Cil/sec SNF 9

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Noble Gas Dose Factors 2.9E+02 1.5E+02 5.7E+01 2.5E+01 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain TOTAL DOSE SNF RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain TOTAL PAR DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {EOF HP Manager if done in EOF}

E.

Dose calculations completed; continue monitoring releases and assessing doses.

END OF WORKSHEET 10 END OF ATTACHMENT 9

REVISION NO..

PROCEDURE TITLE.

PAGE 7

OFF-SITE DOSE CALCULATIONS 71 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 10 RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 1 of 6)

1.

Purpose This attachment provides methods for TSC and / or EOF Dose Assessment personnel to define release rates from a containment burp and includes NRCs RTM-91 methods for estimating dose rates based on plant/reactor conditions.

2.

Discussion A.

A containment burp is any suspected release from the containment that may be indicated by a rapid decrease of the containment pressure or rapid decrease in the Containment High Range Radiation Monitor that is determined, by operations or engineering, not due to changes in equipment operation (e.g., additional containment spray, additional containment coolers, etc.).

B.

It must be remembered and understood that the methodology provided in this appendix includes conservative assumptions and is intended to provide the means to estimate an upper bound to the release, not an exact release rate.

3.

Contents Section 1:

Provides guidance in estimating release rates during a LOCA resulting from rapid containment depressurizations; that is, an unmonitored burp release. The guidance is further sub-divided into three cases:

Case 1 - Rapid decrease in CHRRM reading during burp Case 2 - No change in CHRRM reading during burp Case 3 - Increase in CHRRM reading during burp Section 2:

Provides guidance in estimating doses based on plant / reactor conditions following the methodology in NRC RTM-91.

REVISION NO:

PROCEDURE TITLE:

PAGE:

7 OFF-SITE DOSE CALCULATIONS 72 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 10 RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 2 of 6)

4.

Basis Section 1:

Assumes CHRRM is responding only to Noble Gases Assumes Curies in (from core) < < Curies lost 2 E + 06 R/hr = 100% Core Inventory of Noble Gas (1 + CFT=O. CF from EPIP-09) 6.43 E + 08 Curies of Noble Gas is 100% Core Inventory (PSL2 UFSAR) 322 = 6.43 E + 08 Curies ÷ 2 E + 06 R/hr Section 2:

NRC's Response Technical Manual RTM-91 Vol. 1, Rev. 1, pg. C-2.

5.

Percent Mass Loss A.

Use Attachment 11, Estimate of Containment "% Mass Loss", to determine the values required in the following calculations.

REVISION NO.'

PROCEDURE TITLE.

PAGE:

7 OFF-SITE DOSE CALCULATIONS 73 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 10 RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 3 of 6)

Section 1 - Case 1: Rapid Decrease in CHRRM Reading (Applicable to Unit 1 or Unit 2)

1.

Enter date and time of data:

2.

Calculate Delta-CHRRM:

Start CHRRM

- End CHRRM

= __

Delta-CHRF

3.

Calculate Duration:

A.

Clock Time End

- Clock Time Start._

=

B.

Convert Delta-Clock to Delta-Seconds:

A A sec

4.

Estimate Curies Lost:

Delta CHRRM x 322 Ci N.G. per R/hr = _

Noble Gas C

5.

Estimate Noble Gas Release Rate (loss rate):

Noble Gas Curies lost Noble Gas M, R/hr Delta-Clock uries Lost Ci/sec A sec

6.

Estimate the Iodine Release Rate:

N.G. Ci/sec _

x 0.01 (Iodine Factor) = _

Iodine Ci/sec

7.

Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets or enter as Direct if using the computer, to estimate Offsite Doses.

END OF CASE I NOTE

1. A CHRRM drop of about 3 percent per hour may be due to radiological decay.

2. The CHRRM may drop by as much as 10 percent very quickly if containment spray is actuated due to Iodine washout.

-4

REVISION NO:

PROCEDURE TITLE:

PAGE.

7 OFF-SITE DOSE CALCULATIONS 74 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 10 RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 4 of 6)

Section 2 - Case 2: Constant CHRRM Reading (Applicable to Unit 1 or Unit 2)

1.

Enter date and time of data:

/

2.

Estimate Noble Gas Curies in the containment:

CHRRM R/hr x 322 Ci N.G. per RPhr = _

Noble Gas Cu

3.

Calculate Duration:

A.

Clock Time End _

- Clock Time Start

=

B.

Convert Delta-Clock to Delta-Seconds:

A t sec

4.

Estimate Curies Lost:

A.

Determine "% Mass Loss" (Attachment 11)

Noble Gas Curies in Containment x % mass lost_ ____

iries in can Delta-Clock e Gas Curies lost 100

5.

Estimate Noble Gas Release Rate (loss rate):

Noble Gas Curies lost Noble Gas Ci/sec A sec

6.

Estimate the Iodine Release Rate:

N.G. Ci/sec x 0.01 (Iodine Factor) =

Iodine Ci/sec

7.

Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets or enter as Direct if using the computer, to estimate Offsite Doses.

END OF CASE 2

0 0

B.

100

REVISION NO:

PROCEDURE TITLE:

PAGE.

7 OFF-SITE DOSE CALCULATIONS 75 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 10 RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 5 of 6)

Section 1 - Case 3: Increasing CHRRM Reading (Applicable to Unit 1 or Unit 2)

NOTE Engineering may be requested to evaluate the percent mass lost in the burp.

1.

Enter date and time of data:

/

2.

Calculate average CHRRM reading (Start CHRRM

+ End CHRRM

) =

_Avg CHRRM, R/hr 2

3.

Estimate Noble Gas Curies in the containment:

Avg. CHRRM R/hr x 322 Ci N.G. per R/hr =.

Noble Gas Curies in can

4.

Calculate Duration:

A.

Clock Time End _

- Clock Time Start

= _

Delta-Clock B.

Convert Delta-Clock to Delta-Seconds:

A sec

5.

Estimate Curies Lost:

A.

Determine "% Mass Loss" (Attachment 11)

Noble Gas Curies in Containment_

x % mass lost B.

Noble Gas Curies lost 100

6.

Estimate Noble Gas Release Rate (loss rate):

Noble Gas Curies lost Noble Gas Ci/sec A sec

7.

Estimate the Iodine Release Rate:

N.G. Ci/sec x 0.01 (Iodine Factor) =

Iodine Ci/sec

8.

Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets or enter as Direct if using the computer, to estimate Offsite Doses.

END OF CASE 3

REVISION NO

PROCEDURE TITLE.

PAGE:

7 OFF-SITE DOSE CALCULATIONS 76 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 10 RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 6 of 6)

SECTION 2 (Applicable to Unit 1 or Unit 2)

Use this method IF there is not radiological data (e.g., CHRRM, containment grab sample, etc.) AND the accident has progressed past gap failure AND the containment has undergone catastrophic failure (e.g., know there should be pressure and there is none).

II NOTE The following method provides DOSES, not release rates. Doses based on stability class D and four m.p.h. wind speed.

REACTOR ACCIDENT CONSEQUENCE OVERVIEW Containment Leakage Acute Dose (rem) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Core Containment Mitigating System Release @ I mile(B)

Condition Status Status A)

WB THY Early total No Mitigation 1000+

105+

Failure (< I hr)

Mitigated 250 104 MELT Release Late total failure N/A 250 104 From Core (2 - 12 hr)

N/A_250_104 4500OF Major Leakage N/A 10 103 (100% 1 day)

Design leakage N/A 102 1

Early total No Mitigation 50 104 Failure (< I hr)

Mitigated 10 103 Gap Release Late total failure N/A 5

103 FromCore (2-12 hr) 1500OF Major Leakage N/A 10"1 10 (100% / day)

Design Leakage N/A 10"T 10-2 Notes:

(A) Sprays, filters (B) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cloud immersion and inhalation plus 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of ground shine END OF SECTION 2 END OF ATTACHMENT 10

REVISION NO:

PROCEDURE TITLE:

PAGE.

7 OFF-SITE DOSE CALCULATIONS 77 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 11

¶2 ESTIMATE OF CONTAINMENT "% MASS LOSS" (Page 1 of 2)

(Applicable to Unit I or Unit 2)

1.

Purpose The purpose of this calculation is to provide a method to estimate containment %

mass release to the environment during a post-LOCA containment depressurization transient (containment "burp").

2.

Discussion A.

The scope of this calculation is St. Lucie Units 1 and 2.

B.

The dose assessment group can use the containment mass release data to estimate the radiation release to the environment (using Attachment 4, TSC/EOF Dose Assessment Guidance for Responding to an Unmonitored Containment Burp) provided the containment radiological conditions are known.

C.

The containment de-pressurization event should be large (greater than 5.0 psi change), over a short period of time since the methodology does not accurately credit the effect of containment heat removal systems.

3.

Acquire the following data:

[

NOTE The "time span" for data observation should be the same as used for the calculation on Attachment 4, Case 2 or 3.

II A.

Containment Pressure just before blowdown transient:

B.

Containment Temperature just before blowdown transient:

C.

Containment Pressure just after blowdown transient:

psig {Pstart deg F {Tstart}

psig {Pend}

D.

Containment Temperature just after blowdown transient:

deg F {Tend}

i IIm

REVISION NO:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 78 of 81 PROCEDURE NO' EPIP-09 ST. LUCIE PLANT ATTACHMENT 11 ESTIMATE OF CONTAINMENT "% MASS LOSS" (Page 2 of 2)

(Applicable to Unit 1 or Unit 2)

4.

Estimate Initial Containment Atmosphere Density:

144 x (14.7 +..... Pst*r) 53.3 x (460 +..... Tsta)

Initial Density

5.

Estimate End Containment Atmosphere Density:

144 x (14.7 +..... Pend) 53.3 x (460 +..... Tend)

End Density Estimate % Mass Lost:

C 1 minus

(.........End Density X100

% mass lost jx t0

=iaI De n itys))

END OF ATTACHMENT 11 6.

REVISION NO:

PROCEDURE TITLE:

PAGE*

7 OFF-SITE DOSE CALCULATIONS 79 of 81 PROCEDURE NO.:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 12 FIELD TEAM MEASUREMENTS ASSESSMENT (Page 1 of 3)

¶3 This attachment provides methods to estimate a release rate from Field Monitoring Team survey meter measurements and provides guidance on comparing field measurements to dose projections.

NOTE Survey meter Gamma (closed window) results must be from plume centerline; that is, the maximum value from a lateral transverse of the plume.

1.

DATE:

, TIME:

, Unit:_

2.

If the survey meter measurement was at 1 mile value, Then go to Step 4.

3.

Estimate the 1 mile value:

Estimated I mile value = Survey meter results x (downwind distance, miles)z Where the exponent Z = 2 for Stability Class A, B 1.5 for Stability Class C, D 1.0 for Stability Class E, F, G Z___

(z) mr/hr xl (miles)

=

Estimated Dose Rate @ 1 mile mr/hr meter results Ldownwind distance

4.

For the meteorological conditions at time of sampling, select the Dose Calculation Worksheet (DCW).

A.

Use Wind Speed in Miles Per Hour, mph B.

Copy from Line 13, the 1 mile Dose factor as the DF for use in Step 5.

5.

Estimate Noble Gas Release Rate: Estimated 1 mile mr/hr ÷ DF x Wind Speed mr/hr x mph Noble Gas Ci/sec DF

REVISION NO:

PROCEDURE TITLE:

PAGE 7

OFF-SITE DOSE CALCULATIONS 80 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 12 FIELD TEAM MEASUREMENTS ASSESSMENT (Page 2 of 3)

6.

Estimate Iodine Release Rate (IF = Iodine Factor, see the affected units' Effluent Monitor Worksheet):

N.G. Ci/sec x (IF) =

Iodine (131 Deq) Ci/sec

7.

Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets, or enter release rates as Direct if using the computer, to estimate Offsite Doses from this attachment.

Comparing Field Measurements To Dose Proiections NOTE

1. "Reasonable comparison" between Field Measurements & Dose Calculations is if the two are within an order of magnitude. Too many assumptions preclude better precision.

2. A survey team measurements 'off centerline' will yield a low estimated release rate. The Field Monitoring Coordinator (EOF) has a method for estimating centerline values for these situations.

Survey Meter DDE Readings The computerized dose calculation program estimates the 'survey meter reading' DDE and for the pre-designated sampling locations (refer to Field Survey Map for descriptions of the locations). This Survey Meter Estimate is sum of immersion in plume of Noble Gas, and plume shine from iodine & particulates. The noble gasses are the majority of the exposure source. The program adjusts for gap versus core mix of noble gasses in response to the Core Damage Situation question.

The manual method does not calculate a DDE from immersion in noble gas.

Referring to a Dose Calculation Worksheet apropos to the met conditions, a value could be estimated by multiplying the value calculated on line 10 by the Dose Factors listed on line 13. These Dose Factors are based on a core mix of noble gasses, and include the X/Q for the prevailing meteorological conditions.

REVISION NO.:

PROCEDURE TITLE:

PAGE' 7

OFF-SITE DOSE CALCULATIONS 81 of 81 PROCEDURE NO:

EPIP-09 ST. LUCIE PLANT ATTACHMENT 12 FIELD TEAM MEASUREMENTS ASSESSMENT (Page 3 of 3)

Thyroid CDE Thyroid dose projections, both procedure & computer, are based on a release of 1-131 Deq Ci/sec. The field teams measure 1-131 in the plume; their procedure has a time dependent factor to account for the dose from the other iodines. The factor starts at about 1.4 and decays to 1 (one) over about 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Dividing projected thyroid dose rate, mr/hr by 1.3 E + 9 will estimate the Iodine 131 (Deq) concentration uCi/cc.

Time of Sample v. Time of Release Time of field measurement minus (downwind distance, miles I wind speed, m.p.h.) will yield the 'time' of the release rate estimated. The computerized calculations use a time window 15 or 30 minutes long. Select the latest printout that has a Release Observation Time before the time estimated above.

Estimating Dose Rates Or Concentrations At Other Distances (e.g., 1, 2, 5, 10 miles)

Estimated Value @ Dist x = Measured value times (DWD/Dist x)z Where: DWD = Measurement downwind distance, miles Dist x = other distance, miles Z = exponent based on stability class (ref EPA-520 Rev. 6/79, page 5.10.)

END OF ATTACHMENT 12

Procedure No.

ST. LUCIE PLANT EPIP-12 EMERGENCY PLAN Current Revision No.

IMPLEMENTING PROCEDURE 11 FP L Effective Date SAFETY RELATED 08101102

Title:

MAINTAINING EMERGENCY PREPAREDNESS RADIOLOGICAL EMERGENCY PLAN TRAINING Responsible Department: EMERGENCY PLANNING REVISION

SUMMARY

Revision 11 -Added definitions, clarified drill participation requirements, eliminated notification of certain departments, removed PAR training requirements, added OSC manager trng, and made other minor changes. (J. R. Walker, 07/18/02)

REVISION 10 - Adjusted positions for which drill participation may be desirable prior to being placed in ERO. Added requirement for drill participation. Revised ST L,-NDO,-,,

training requirements. (R. Walker, 09/27/01)

_J Revision 9 - Revised Chemistry training relative to PASS elimination.

o (J. R. Walker, 07/23101) 3 Revision 8 - THIS PROCEDURE HAS BEEN COMPLETELY REW ftNiRh!nbdr_

CTIf'3 training requirement for FAPDT (First-Aid Personnel Decontamination Tram) training for Chemistry personnel, added statement regarding Security First Aid Training, and made editorial and administrative changes. (J. R. Walker, 12/07/00)

AND Added reference to NP-912, revised GET procedure number, updated trng. mgr. title, revised annual retraining to allow credit for drill/exercise participation, identified use of PSL/PTN common training modules, deleted RM training module from qual req for ECO and NDDO and made administrative changes. (J. R. Walker, 10/13/00)

Revision 7 - Eliminated backshift paramedic position due to first responder training of Security personnel. (G. Varnes, 08/08/00)

Revision 0

FRG Review Date 12/15/97 Revision FRG Review Date 11 07/18/02 Approved By Approval Date J. Scarola 12/15/97 Plant General Manager Approved By Dick Rose Plant General Manager Approval Date 07/18/02 N/A Designated Approver N/A Designated Approver (Minor Correction)

S OPS DATE DOCT PROCEDURE DOCN EPIP-12 SYS COM COMPLETED ITM 11 I

REVISION NO.:

PROCEDURE TITLE:

PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

2 of 36 PROCEDURE NO:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 P U R P O S E....................................................................................................

3

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT D O C U M ENTS..............................................................................................

4 3.0 RESPONSIBILITIES................................................................................

5 4.0 DEFINITIONS...........................................................................................

7 5.0 INSTRUCTIONS......................................................................................

9 5.1 Initial Training..................................................................................

9 5.2 Annual Retraining...........................................................................

11 5.3 Loss of ERO Qualifications.............................................................

14 5.4 Training for Security Personnel.....................................................

15 5.5 Fire Brigade....................................................................................

16 5.6 Training Exemptions and Substitutions........................................

1,7,.,

ATTACHMENTS ATTACHMENT 1 EMERGENCY RESPONSE ORGANIZATION CHANGE REQUEST..........................................................................

18 ATTACHMENT 2 ERO INITIAL TRAINING MATRIX....................................

19 ATTACHMENT 3 ERO ANNUAL REQUALIFICATION MATRIX................... 28

REVISION NO.:

PROCEDURE TITLE PAGE' 11 MAINTAINING EMERGENCY PREPAREDNESS -

3 of 36 PROCEDURE NO.:

RADIOLOGICAL EMERGENCY 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:

11 MAINTAINING EMERGENCY PREPAREDNESS -

4 of 36 PROCEDURE NO' RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT

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, Operating Experience, License Renewal, 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.

'P Indicates a step that requires a sign off on an attachment.

2.1 References

§1 St. Lucie Plant Radiological Emergency Plan (E-Plan)

I ¶,

QI 1-PR/PSL-1, Site Organization.

1

¶2 QI-17-PSL-1, Quality Assurance Records.

T

¶4 ADM-18.06, General Employee Training.

AP 1800022, Fire Protection Plan.

ADM-1 1.11, Severe Accident Management Guidelines Program Administration St. Lucie Plant Emergency Response Directory.

NP-912, Respiratory Qualifications Requirements 2.2 Records Required

¶2 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-1 7-PSL-1, Quality Assurance Records.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

5 of 36 PROCEDURE NO" RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 2.3 Commitment Documents 10 CFR 50.47, Emergency Plans.

0 10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities.

10 CFR 26, Fitness for Duty.

NUREG 0737, 11..B.4, Training for Mitigating Core Damage

§2 NOV Response L-97-20, Violation II.C, Part 4A.

§3 NOV Response L-97-20, Violation II.C, Part 4B.

§4 NRC Inspection Report 96-18 URI P5.2 0

¶3 QAS-EMP-96-01, Finding 2 a

¶5 PMAI PM99-05-183 (Use and Update of the Personnel Qualification Database (PQD))

0 16 PMAI PM99-09-077, CR 99-1353 (Training requirements for TSC Dose Assessor)

S

¶%7 CR 00-0544, Audit QSL-EP-00-02 (Discrepancies with Primary and Backup ERO Augmentation Processes) 3.0 RESPONSIBILITIES 3.1 The Site 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:

11 MAINTAINING EMERGENCY PREPAREDNESS -

6 of 36 PROCEDURE NO' RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 3.2 Protection Services Manager is responsible for:

1.

¶i 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.

A.

I¶7 Ensuring non-bargaining unit personnel pagers are correctly programmed.

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.

§1 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.

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.

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.

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.

REVISION NO:

PROCEDURE TITLE:

PAGE*

11 MAINTAINING EMERGENCY PREPAREDNESS -

7 of 36 PROCEDURE NO.:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 3.3 Emergency Preparedness is responsible for: (continued)

9.

Providing guidelines to plant management to assist in identifying the appropriate number of ERO personnel for each ERO position.

10.

Notifying the Site Training Manager if changes in the E-Plan and/or EPIPs justify additional training for ERO personnel.

11.

Chairing EP Training Review Committee Meetings.

3.4 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' status 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.

T7 Ensure that non-bargaining unit personnel have pagers.

3.5 The Protection Services Manager is responsible to ensure that Security personnel maintain EP training qualifications per this procedure.

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.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

8 of 36 PROCEDURE NO.:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 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 Recall System - a computer-based automated call-out system used to activate the ERO. This system is also referred to as the "autodialer".

4.6 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.

4.7 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.

4.8 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.

4.9 SAMG - Severe Accident Management Guidelines.

REVISION NO:

PROCEDURE TITLE PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

9 of 36 PROCEDURE NO:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 5.0 5.1

1.

§1 Initial Orientation Training (Plant Access Training - PAT) shall be PROVIDED to permanently assigned new employees.

A.

Training includes information describing:

1.

Actions to be taken by an individual who discovers an emergency condition.

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).

"* Personnel filling the position of Emergency Coordinator, TSC OPS Coordinator, or EOF RM OPS Advisor/Logkeeper should have SRO level knowledge (i.e., current or previous SRO license or SRO equivalent training such as Engineering Management Operations Training (EMOT)).

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.

Certain ERO positions, as indicated in Attachment 2, ERO Initial Training Matrix, require drill participation as part of initial ERO qualification.

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:

- TSC Supervisor

- TSC Coordinator with OSC

- OSC Coordinator with TSC

- St. Lucie County Technical Advisor

- Martin County Technical Advisor W

REVISION NO.

PROCEDURE TITLE:

PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

10 of 36 PROCEDURE NO:

RADIOLOGICAL EMERGENCY.

EPIP-12 ST. LUCIE PLANT 5.1 Initial Training (continued)

1.

A.

(continued)

2.

Location of assembly areas.

3.

Identification of emergency alarms.

4.

Action to be taken upon hearing alarms.

B.

T4 PAT Training is CONDUCTED in accordance with ADM-18.06, General Employee Training.

2.

§3¶3 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, 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.

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.

11 MAINTAINING EMERGENCY PREPAREDNESS -

11 of 36 PROCEDURE NO" RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 5.2 Annual Retraining

1.

§1 Annual retraining shall be PROVIDED at least once per calendar year.

2.

Annual retraining may be ACCOMPLISHED by classroom training, drill /

exercise participation option or other training method.

A.

¶3 Classroom training shall INCLUDE topics identified in, ERO Annual Retraining Matrix.

1.

The drill / exercise participation option is NOT an acceptable alternate for the following topics:

a.

Emergency classification

b.

Protective Action Recommendations (PARs)

c.

Accident assessment / corrective actions

d.

Core melt scenario

e.

Core damage assessment

f.

ERDADS operations

g.

Off-site Dose Calculation (OSDC)

h.

Recovery Manager training L.

Sever Accident Management Guidelines (SAMGs)

2.

Individuals may challenge annual retraining examinations for topics not accounted for in the drill / exercise participation option.

3.

Personnel who teach a class should receive credit for completion of that class at the discretion of the Site Training Manager.

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.

0

REVISION NO:

PROCEDURE TITLE:

PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

12 of 36 PROCEDURE NO.:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 5.2 Annual Retraining (continued)

2.

(continued)

B.

Drill exercise participation option shall include:

1.

¶3 A review of significant changes in the scope or content of the Emergency Plan and / or applicable Emergency Plan Implementing Procedures.

2.

Additional annual retraining topics identified by the EP Training Review Committee, which may include:

Review of selected initial training topics Industry operating experience A review of past drill / exercise performance problems

3.

Attendance at a pre-drill / exercise facility specific briefing.

4.

Participation in the drill / exercise as a player, controller or mentor (drills only).

5.

Participation in the post drill / exercise facility critique or controller critique.

C.

Other training methodologies may be USED on an as needed basis when approved by the EP Training Review Committee and the Site Training Manager and which are consistent with the training requirements of the Emergency Plan.

REVISION NO.:

PROCEDURE TITLE PAGE:

11 MAINTAINING EMERGENCY PREPAREDNESS -

13 of 36 PROCEDURE NO.:

RADIOLOGICAL EMIERGENCY EPIP-12 ST. LUCIE PLANT 5.2 Annual Retraining (continued)

NOTE Deviation from this schedule requires the approval of the Chief Nuclear Officer.

3.

§2 Emergency Response Facility (ERF) drills shall be conducted at least four times per calendar year and should be conducted approximately once each quarter.

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.

1.

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, Mentors and Observers for each facility.

3.

Drill participation should be RECORDED in the training database.

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, controller or mentor (drills only).

2.

Failure to participate in an ERF drill annually may RESULT in remedial training as determined by the Site Training Manager and Protection Services Manager.

END OF SECTION 5.2

REVISION NO.:

PROCEDURE TITLE:

PAGE.

11 MAINTAINING EMERGENCY PREPAREDNESS -

14 of 36 PROCEDURE NO.:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 5.3 T3 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, Then the Site Training Manager or designee shall NOTIFY the Emergency Preparedness Supervisor or designee of the results.

A.

The individual shall not respond to an emergency until such time as remediation has been successfully completed.

B.

The individual should be REMOVED from the ERS and ERD until appropriate remedial training, as recommended by the Site Training Manager and approved by the Emergency Preparedness Supervisor, has been completed.

4.

The individual should COMPLETE remedial training at the earliest opportunity.

END OF SECTION 5.3

REVISION NO.:

PROCEDURE TITLE:

PAGE.

11 MAINTAINING EMERGENCY PREPAREDNESS -

15 of 36 PROCEDURE NO:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 5.4 Training for Security Personnel

1.

Security personnel shall RECEIVE initial training and annual retraining for emergency response in accordance with this procedure.

2.

Security personnel shall RECEIVE First Aid Team training in accordance with Security procedures.

END OF SECTION 5.4

REVISION NO.:

PROCEDURE TITLE:

PAGE 11 MAINTAINING EMERGENCY PREPAREDNESS -

16 of 36 PROCEDURE NO:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 5.5 Fire Brigade

1.

Fire Brigade training is COVERED by the Fire Protection Plan, AP 1800022.

END OF SECTION 5.5

REVISION NO.:

PROCEDURE TITLE:

PAGE 11 MAINTAINING EMERGENCY PREPAREDNESS-17 of 36 PROCEDURE NO:

RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT 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.

The Nuclear Division Duty Officer (NDDO) is not required to participate in a drill / exercise as the emergency duties associated with the position do not differ from normal duties.

END OF SECTION 5.6

REVISION NO:

PROCEDURE TITLE:

PAGE 11 MAINTAINING EMERGENCY PREPAREDNESS -

18 of 36 PROCEDURE NO RADIOLOGICAL EMERGENCY EPIP-12 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY RESPONSE ORGANIZATION CHANGE REQUEST I

I 0

R I

G I

N A

T 0

R NOTE Personnel will not be assigned to an emergency response organization position until required training for that position is completed.

Dept.

Originator:

" Add El Remove "0 Change (Circle new info)

" Name:

Soc. Sec. No.:

"* Position number:

"* Position:

Work Phone:

Home Phone:

Pager:

r~th~r

¶7 NOTE DEPT Non-bargaining unit personnel will not be assigned to a position if they do not have a HEAD pager.

Department Head/Supv. Signature:

Date:

/

Authorization for ERO training E

P EP Supervisor Date:

/

T R

A 1[515 The individual listed above meets the training/qualification requirements of EPIP-12 I

for the position(s) indicated per the Personnel Qualification Database (PQD).

N I

Signature:

Date

/

I N

G

¶7 0 Pager correctly programmed:

Date:

/

I Init.:

El Emergency Recall System database updated:

Date:.

/

Init.:

E 0

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Date:

I

/

Init.:

P

[I Notifications to ERO:

Date:

I Init.:

¶T 0 Notification of Personnel Qualification Database (PQD) Administrator Date:

I I

Init.:

Only information required if removing from ERO (by EP)

END OF ATTACHMENT I X

REVISION NO 11 PROCEDURE NO:

EPIP-12 I'

I PROCEDURE TITLE' MAINTAINING EMERGENCY PREPAREDNESS RADIOLOGICAL EMERGENCY ST. LUCIE PLANT I

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EPIP-12

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PROCEDURE TITLE MAINTAINING EMERGENCY PREPAREDNESS RADIOLOGICAL EMERGENCY ST. LUCIE PLANT PAGE:

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6 REVISION NO.:

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11 rROCEDURE NO' FPlP-I2 I-------------------

PROCEDURE IIILE:

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C REVISION NO*

11

'ROCEDURE NO.

EPIP-12

(

PROCEDURE TIITL:

MAINTAINING EMERGENCY PREPAREDNESS RADIOLOGICAL EMERGENCY ST. LUCIE PLANT PAGE:

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C REVISION NO:

11 PROCEDURE NO.:

EPIP-12 I.

PROCEDURE TITLE.

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MAINTAINING EMERGENCY PREPAREDNESS RADIOLOGICAL EMERGENCY ST. LUCIE PLANT ATTACHMENT 3 ERO ANNUAL REQUALIFICATION MATRIX (Page 1 of 9) r-i-r-i-r-r-i-rrlrTlTrlr(

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L-2002-161, Revised Emergency Plan Implementing Procedures, EPIP-09, Revision 7 - EPIP-12, Revision 11

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