Text

Revision to EP-PS-244, Dose Assessment Staffer.
	ML022770171
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Site:	Susquehanna
Issue date:	09/26/2002
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To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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EOF DOSE ASSESSMENT STAFFER: EP-PS-244 Emergefncy-Plan-Position-Specific Instruction Revision 6 Page 1 of 5 QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:

QA Program O' 0 Non-QA Program E3 Plant Fl[Non-Plant 0 Instruction "'

EFFECTIVE DATE: ____...______

PERIODIC REVIEW FREQUENCY:' , 2 Years PERIODIC REVIEW DUEDATE:,ý __,__--___

RECOMMENDED REVIEWS: ',,

All

.4 ProcedureO&ner:c' " Nuclear Emergency Planning Responsible Supervisor: Supv.-Operations Technology Responsible FUM: Supv.-Nuclear Emergency Planning Responsible Approver: General Manager-Plant Support FORM NDAP-QA-0002-1, Rev. 3, Page 1 of 1

EP-PS-244 Revision 6 Page 2 of 5 Dose Assessment Staffer: Emergency Plan Position-Specific Procedure WHEN: Emergency Operations Facility (EOF) is Activated.

HOW NOTIFIED: Paged/Telenotification System REPORT TO: Dose Assessment Supervisor WHERE TO REPORT: Emergency Operations Facility OVERALL DUTY:

Direct, coordinate and review operations of the dose assessment area, assuring the Dose Assessment Supervisor receives an accurate overview of off-site radiological conditions to support development of a Protective Action Recommendation, (PAR).

MAJOR TASKS: TAB: REVISION:

Plume Phase: TAB A 3 Provide direction to EOFDC (EOF Dose Calculator) in performance of MIDAS dose projections for the analysis of airborne releases. Confirm input for these calculations from available engineering, field monitoring, and computer based (PICSY) data.

Review results of field team measurements and dose TAB B 4 projections and provide a summary of results for ease of interpretation and use by DASU.

TAB C 2 When indicated by calculation results or available field data, notify DASU of trends and/or flag situations where conditions are approaching critical points, triggers or action levels. Monitor possible liquid release pathway, if indicated.

TAB D 3 Support Field Team Director, (FTD), for team placement and radiological protection.

Post Plume:

Assist the Dose Assessment Supervisor in determining TAB E 0 the post plume phase analytical sampling strategy and providing radiological protection requirements and briefings to environmental sampling teams.

EP-PS-244 Revision 6 Page 3 of 5 SUPPORTING INFORMATION: TAB:

Shift Takeover List TAB I MIDAS Field to Projection Measurement Projection TAB 2 Emergency Classification TAB 3 Intentionally Blank TAB 4 Placement of Field Teams TAB 5 PPL Emergency Personnel Dose Assessment and TAB 6 Protective Action Recommendation Guide MIDAS Operation TAB 7 Meteorological Data Acquisition TAB 8 SSES Environmental Sampling Strategy TAB 9 Environmental Team Briefing Sheet TAB 10 Public Protective Action Recommendation Guide TAB 11 Instructions for Obtaining Current Personnel Exposure TAB 12 Using NIMS TSC to EOF Radiological Dose Assessment Phone Log TAB 13 Dose Assessment Flowchart TAB 14 MIDAS Guidance/Data Sheets TAB 15

Back Calculation (E-W) Guidance Data Sheet

Forward Calculations Guidance/Data Sheet

Event Tree Calculations Guidance/Data Sheet

Blowout Panel Calculations Guidance/Data Sheet

Default Accident Calculations Guidance/Data Sheet PICSY SPING Release Rates Guidelines TAB 16 MIDAS Protective Action Recommendation Action Levels TAB 17 Clarification of Responsibilities of Initial and Augmented TAB 18 Staff

- EP-PS-244 Revision 6 Page 4 of 5

REFERENCES:

EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92-001 May 1992)

FDA Guidance: "Accidental Radioactive Contamination of Human Food and Animal Feed and Recommendations for State and Local Governments." Federal Register, pp 47073-47083, October 22, 1982 ICRP Publication 28, The Principles and General Procedures for Handlinq Emergency and Accidental Exposures of Workers. International Commission on Radiation Protection. (1978)

IE Notice 83-28 NCRP Report 55, Protection of the Thyroid Gland in the Event of Releases of Radioiodine, National Council Radiation Protection and Measurements. (1977)

NCRP Report 91, Recommendations on Limits for Exposure to Ionizing Radiation, National Council on Radiation Protection and Measurements. (1987)

NCRP Report 116, "Limitation of Exposure to Ionizing Radiation, National Council on Radiation Protection and Measurements." (1993)

NUMARC Graded Response Study NUREG-0654, Planning Standards and Evaluation Criteria NUREG-0731, Guidelines for Utility Management Structure and Technical Resources, September 1980 Radiological Assessment Reference Book Spray Pond Blowdown Water Outlet Flow Rate PLI 50258 (May 8, 1987)

Susquehanna SES Emergency Plan 10 CFR 20 Appendix B Study of Travel Time and Mixing Characteristics for the Susquehanna River below the Susquehanna SES - SUTRON CORPORATION - November 1985 NDAP-QA-1190, Nuclear Department Radiation Protection Program and Policies NDAP-QA-1191, ALARA Program and Policy Program

EP-PS-244 Revision 6 Page 5 of 5

REFERENCES:

NEPM-QA-1014, Radiological Environmental Monitoring Program National Interim Primary Drinking Water Regulations, EPA 570/9-76-003 (U.S.)

Environmental Protection Agency, Washington, D.C. 1976 Commonwealth of Pennsylvania State Emergency Operations Plan, Appendix 6 to Annex E - BRP Technical Assessments and Protective Actions, September 22, 1988.

TAB A EP-PS-244-A Revision 3 Page 1 of 14 MAJOR TASK:

Provide direction to EOFDC (EOF Dose Calculator) in performance of MIDAS dose projections for the analysis of airborne releases. Confirm input for these calculations from available engineering, field monitoring, and computer based (PICSY) data.

SPECIFIC TASKS: HOW:

1. Notify DASU upon arrival in the EOF.

2. Prepare to assume responsibilities for 2a. Complete DAST section of "Shift the Dose Assessment Area. Takeover Checklist."

HELP SHIFT TAKEOVER CHECKLIST See TAB I HELP Clarification of Responsibilities of Initial and Augmented Staff See TAB 18 2b. Determine status of MIDAS and PICSY equipment. If equipment is not functional, notify NERO staff.

2c. Inform DASU when-you are prepared to assume responsibilities for your area.

3. Determine if any dose calculations 3a. Contact the TSC Dose Calculator and were performed by the TSC Dose determine if any dose calculations were Calculator. performed.

3b. Request copies of calculations be faxed, if not available in the EOF.

3c. Discuss and verify the validity of assumptions used in previously performed calculations by the TSC Dose Calculator.

TAB A EP-PS-244-A Revision 3 Page 2 of 14 SPECIFIC TASKS: HOW:

SPECIFIC TASKS:

3d. Record assumptions for each calculation performed by TSC on separate

<YELLOW> FORWARD CALCULATION Guidance Data Sheet. Number TSC calculations sequentially starting with TSC-1, TSC-2,etc.

HELP MIDAS GUIDANCE/DATA SHEETS See TAB 15 HELP MIDAS OPERATION See TAB 7

4. Verify the EOF Dose Calculator, 4a. If the EOFDC is unavailable, initiate data (EOFDC), is ready to assume collection activities in Task 6, and responsibilities. prepare calculations as needed.

5. Attend staff briefing(s) convened by 5a. Obtain information on accident status DASU to review overall situation. and current Protective Action Recommendations, (PAR).

5b. Verify/confirm which type of MIDAS calculations are to-be performed in EOF:

1) FORWARD

2) BACK

3) STUDY - EVENT TREE

4) STUDY - DEFAULT ACCIDENT

5) BLOWOUT PANEL

TAB A "EP-PS-244-A Revision 3 Page 3 of 14 SPECIFIC TASKS: HOW:

6. Ensure the EOFDC has initiated the 6a. Begin data input collection from available MIDAS program. If a radiological resources. These resources include:

release has started, begin input data collection. 1) Previously performed TSC dose calculations

2) Available engineering information

3) PICSY data

4) Available field team data

5) RMS data

6) Chemistry Vent Sample data

7) HP air sample data

8) Default Noble Gas to 1-131 or Noble Gas to Particulate ratio(s).

TAB A EP-PS-244-A Revision 3 Page 4 of 14 SPECIFIC TASKS: HOW:

7. Monitor available plant data for 7a. A radiological release or potential for changes which may be indicative of a release may be indicated by (but is not radiological release. Consult/inquire limited to) the following:

with engineering support as conditions warrant. 1) Elevated valid SPING release data from PICSY screen or control terminal.

2) Elevated Field Monitoring data from field teams or the RMS system.

3) Elevated in-plant radiation measurements.

4) Confirmed blow-out panel lifts.

5) Abnormal plant conditions such as:

a) low Rx water level/core uncovery b) high containment radiation c) high coolant activity d) high drywell pressure HELP DOSE ASSESSMENT FLOWCHART See TAB 14

8. Provide VALID dose calculations 8a. Select an appropriate and valid accident every 15 minutes or whenever plant menu.

conditions indicate a significant event with the potential for a release has 1) Use measured vent data in the occurred. Forward Calculation MIDAS model whenever possible.

2) Initiate Back Calculations if field data is available. Test the validity of field data using the Default Accident or NUREG 1228 MIDAS Study Case models.

TAB A EP-PS-244-A Revision 3 Page 5 of 14 SPECIFIC TASKS: HOW:

CAUTION NOTE:

Study Case Calculations are Only VALID calculations are to be hypothetical calculations that are used for EAL Classification, Initial based on assumed, unverified PAR Determination or a PAR plant conditions and leakage rates Upgrade. and meteorology that existed at the time of the calculation.

A VALID calculation is defined as one that is based on: 3) In the absence of valid measured radiological data, perform a Valid

1) Current meteorology and MIDAS Default Accident or expected release duration, and NUREG 1228 Calculation. Use results for EAL Classification and

2) Valid vent data, Chemistry PAR determinations only when:

vent sample, HP air sample results or approved a) Plant conditions indicate a 1-1311/Particulate default ratios, release is in progress.

or b) Valid vent or field data is not

3) Valid in the field radiological available or will not be measurements, or available within the allowed 15 minute assessment

4) In the absence of valid interval.

measured radiological data, a MIDAS Default or NUREG 1228 c) The calculation represents calculation based on inputs current meteorology and that are judged by Engineering expected release duration.

to be consistent with the current conditions in the d) Input parameters are based affected unit. on current plant conditions that have been validated as appropriate by Engineering.

NOTE:

The Default Model is the appropriate and preferred model for a filtered release that does not exceed design basis leak rates.

TAB A

- EP-PS-244-A Revision 3 Page 6 of 14 SPECIFIC TASKS: HOW:

9. When, if required, direct/develop input NOTE:

for "FORWARD CALCULATIONS." FORWARD CALCULATIONS are These calculations use MIDAS performed when valid SPING Menu B. release data is available and release rates exceed technical requirements.

SPING data should be confirmed with Engineering if PICSY data appears any color other than YELLOW. WHITE data should be considered as a potential unmonitored release unless Engineering/Chemistry data indicates otherwise. Notify DASU immediately if WHITE data occurs for SPING release rates indicated on PICSY. If valid SPING data is not available, perform BACK CALCULATIONS and appropriate Default or NUREG 1228 Calculation.

9a. Direct/help EOFDC to obtain input data and record data on <YELLOW>

"FORWARD CALCULATION Guidance Data Sheet(s)."

HELP MIDAS GUIDANCE/DATA SHEETS See TAB 15 9b. - Review information collected by EOFDC on Guidance/Data sheet for accuracy.

9c. Direct the EOFDC to perform calculation.

NOTE:

Color coded MIDAS Calculation Guidance/Data sheets are found at the EOF Dose Calculator's workstation.

TAB A EP-PS-244-A Revision 3 Page 7 of 14 SPECIFIC TASKS: HOW:

HELP MIDAS OPERATION See TAB 7 9d. Ensure ANY calculations performed in EOF are numbered sequentially, i.e., EOF-1, EOF-2, etc.

10. Assess reliability dose rate and 10a. Periodically evaluate dose and release release rate data. rate data by:

(1) Reviewing field measured to projected dose rate ratios when possible.

HELP MIDAS Field Measurement to Projection Comparison See TAB B and TAB 2 (2) Determining if low confidence (white) PICSY (SPING) release rate data exists.

NOTE:

WHITE data should be considered as a potential unmonitored release pathway-unless Engineering/Chemistry data indicates otherwise.

(3) Determine if Iodine 131 detection channels are over responding due to interference from noble gas or short lived nitrogen isotopes. In general, data is suspect if NG/I-1 31 release rates are less than 1000 for a given vent.

TAB A

- EP-PS-244-A Revision 3 Page 8 of 14 SPECIFIC TASKS: HOW:

HELP EOF DOSE ASSESSMENT FLOWCHART See TAB 14 Pg. 3 10b. If low confidence (white) PICSY (SPING) data exists:

(1) Consult with Engineering to determine if condition is normal (i.e., per design) and/or if vent totals are valid from the Engineering/Dose Assessment perspective.

(2) Ifvent totals are considered valid and/or the field measured/projected dose is within 0.1 to 5 range), the results can be considered reasonable.

(3) If measured field data is higher than projected values, perform a Back Calculation and use the more conservative results.

1Oc. If PICSY (SPING) vent totals are questionable:

(1) Request Engineering promptly pursue corrective actions, obtain Chemistry vent sample data, and/or evaluate need to switch vent monitoring to PAVSS.

(2) Notify RPC and discuss alternate methods to obtain release data (e.g., HP air samples) and/or need to switch to PAVSS.

TAB A EP-PS-244-A Revision 3 Page 9 of 14 SPECIFIC TASKS: HOW:

HELP EOF DOSE ASSESSMENT FLOWCHART See TAB 14 Pg. 4 (3) Use appropriate data such as grab sample (vent, PAVSS, HP air samples) results or previously measured or default noble gas to iodine/particulate ratios.'

(4) Ensure field teams are taking air samples as appropriate and keeping their exposure ALARA.

(5) Report conditions as a potential unmonitored or an unmonitored release as appropriate depending on measured to projected dose rate ratios.

(6) Initiate BACK CALCULATIONS if field data is available and as appropriate a Default Accident or NUREG 122-8 MIDAS Calculation.

NOTE:

If valid SPINGIPAVSS data is not available, test the validity of field data using the Default Accident or NUREG 1228 MIDAS Study Case Models.

TAB A EP-PS-244-A Revision 3 Page 10 of 14 SPECIFIC TASKS: HOW:

11. When/if required, direct/develop input NOTE:

for "BACK CALCULATIONS." These BACK CALCULATIONS are calculations use MIDAS Menu E-W. performed when valid SPING/PAVSS release data is unavailable and/or an unmonitored release pathway may exist. Field dose rate data is required. Field team data is available from Remote Monitoring System (RMS) or by radio.

11a. Review available field team data with the EOFDC and Field Team Director (FTD).

11b. Ensure the following data is available for MIDAS input:

1) Field monitor reading (mR/hr),

2) OSCAR location (distance in miles),

3) Iodine Concentration in (uCi/cc) for RMS or (cpm) for cartridge data.

(Default value may be used if iodine data is-unavailable.)

11c. If "BACK CALCULATIONS" are to be performed, direct/help EOFDC to obtain input data and record on <PINK>

"BACK Calculation Guidance Data Sheets."

11d. Review information collected by EOFDC on Guidance/Data Sheet for accuracy.

11e. Ensure ANY calculations performed in EOF are numbered sequentially, i.e., EOF-1, EOF-2, etc.

TABA EP-PS-244-A Revision 3 Page 11 of 14 SPECIFIC TASKS: HOW:

1If. Direct the EOFDC to perform calculation.

HELP MIDAS GUIDANCE/DATA SHEETS See TAB 15 NOTE:

Color coded MIDAS Calculation GuidancelData sheets are available at the EOF Dose Calculator's workstation.

HELP MIDAS OPERATION See TAB 7

12. When/if required, consider need for 12a. Performance of"Study Calculations" "STUDY CALCULATIONS" since should be considered if abnormal plant certain plant conditions may be a events occur such as:

precursor to or be indicative of the potential for a radiological release. 1) Low Rx water level/core uncovery These calculations use MIDAS Menu C for "EVENT TREE" or Menu D for 2) High Containment Radiation Levels "DEFAULT."

3) High Drywell Pressureffemperature NOTE:

Study Calculations are 4) Spent Fuel Pool Release hypothetical calculations that are plant conditions, which may occur sometime in the future,

5) Valid SPING/PAVSS release data is unavailable I but do not currently exist NOTE:

The performance of Study Calculations is not limited to the above examples.

12b. Contact Engineering Support personnel to determine if any abnormal plant conditions or events may be precursors to a possible radiological release.

12c. Discuss possible release pathway and source term with engineering and review with EOFDC.

TAB A EP-PS-244-A Revision 3 Page 12 of 14 SPECIFIC TASKS: HOW:

12d. Consider performing "STUDY CALCULATION" using "EVENT TREE" or "DEFAULT ACCIDENT" evaluations.

HELP DOSE ASSESSMENT FLOWCHART See TAB 14 HELP MIDAS OPERATION See TAB 7 12e. If conditions exist which warrant the performance of a "Default Accident or NUREG 1228" calculation, direct/help EOFDC to obtain input data.

1) Obtain appropriate input parameters from Engineering and current meteorology.

2) Direct the EOFDC to record data on the <GREEN> "Calculation Guidance/ Data Sheet(s)" for "EVENT TREE" calculation.

3) Direct the EOFDC to record data on the <BLUE> Calculation GuidancelData Sheet(s) for "DEFAULT ACCIDENT" calculations.

4) Review information collected by the EOFDC on Guidance/Data Sheet for accuracy.

5) Direct the EOFDC to perform calculation.

NOTE:

Color coded MIDAS Calculation Guidance/Data Sheets are available at the EOF Dose Calculator's workstation.

- TABA EP-PS-244-A Revision 3 Page 13 of 14 SPECIFIC TASKS: HOW:

HELP MIDAS GUIDANCEIDATA SHEETS See TAB 15 HELP MIDAS OPERATION See TAB 7

6) For NUREG 1228 calculations, review input parameters used and calculational results with Engineering. Have Engineering sign off Calculation as reviewer to document their concurrence that the calculation appropriately models the existing plant conditions.

12f. Ensure ANY calculations performed in EOF are numbered sequentially, i.e., EOF-1, EOF-2, etc.

13. When/if required, direct/develop input NOTE:

for "BLOW OUT PANEL" "BLOW OUT PANEL calculations. These calculations use CALCULATIONS" are performed MIDAS Menu B. when indication exists that a component has failed and resulted in the release of significant amounts of steam and/or coolant directly to the environment.

A blow out panel lift should be confirmed by operations.

13a. Determine the need for performing a "BLOWOUT PANEL" calculation.

HELP DOSE ASSESSMENT FLOWCHART See TAB 14

TABA EP-PS-244-A Revision 3 Page 14 of 14 SPECIFIC TASKS: HOW:

13b. If"BLOW OUT PANEL" calculations are to be performed, direct/help EOFDC to obtain input data and record data on

<CANARY ORANGE> "BLOWOUT PANEL" Calculation GuidancelData Sheet(s).

13c. Review information collected by the EOFDC on Guidance/Data Sheet for accuracy.

13d. Direct the EOFDC to perform calculation.

13e. Ensure ANY calculations performed in EOF are numbered sequentially, i.e., EOF-1, EOF-2, etc.

HELP MIDAS GUIDANCEIDATA SHEETS See TAB 15 NOTE:

Color coded "MIDAS Calculation GuidancelData Sheets" are located at the EOF Dose Calculator's workstation. -

HELP MIDAS OPERATION See TAB 7

TAB B EP-PS-244-B Revision 4 Page 1 of 3 MAJOR TASK:

Review results of field team and dose projections and provide a summary of results for ease of interpretation and use by DASU.

SPECIFIC TASKS: HOW:

1. Review "FORWARD la. Where possible, compare monitored CALCULATION" to determine if data release rates, calculated dose rates, is within reasonable correlation. RMS and Field Team measurement data.

If time permits and conditions warrant, compare calculated dose rates to field lb. Iftime permits and field data is available, measurements. determine the measured to projected ratio for whole body and thyroid measurements.

HELP MIDAS FIELD MEASUREMENT TO PROJECTION COMPARISON See TAB 2 lc. Ifthe measured to projected ratio is within the range of 0.1 to 5, the correlation is reasonable.

1d. Ifmeasured field dlta is higher than projected values, perform a Back Calculation and use the more conservative results.

le. If field team readings are significantly high, (ratio > 5) an unmonitored release is in progress. Initiate "BACK" calculations. Validate "Back Calculation" results with appropriate default or NUREG 1228 calculation.

Notify DASU immediately if unmonitored release is confirmed.

If. If field team readings are low, (ratio< 0.1), the field team may not be in the plume. Notify the Field Team Director, (FTD), to locate plume and continue with "FORWARD CALCULATIONS."

- TAB B EP-PS-244-B Revision 4 Page 2 of 3 SPECIFIC TASKS: HOW:

1g. If SPINGIPAVSS vent release data does not exist, test the validity of the field data using the Default or NUREG 1228 MIDAS models as appropriate.

2. Prepare a color coded "Dose 2a. The DAST should prepare a color coded Summary Package" to aid in the "Dose Summary Package" for each transfer of dose projection information MIDAS calculation performed by the to the DASU. EOFDC.

2b. The "Dose Summary Package" consists of:

1) Applicable color coded "Calculation GuidancelData Sheet" prepared by the EOFDC.

2) The "MIDAS Dose Summary Report," (MIDAS printout),

associated with the MIDAS calculation.

3) If projected doses exceed the PAG Values at 10 miles, attach the applicable MIDAS "More Reports" printout that indicates the distance in which the projected dose is less than the PAG values.

2c. Make a copy of the "Dose Summary Package" for logbook.

2d. Staple together the "Calculation Guidance/Data Sheet" to the Midas "Dose Summary Report."

3. Review the color coded "Dose 3a. If applicable, annotate or attach results Summary Package," and annotate of measured to projected dose rate any assumptions, or deviations. evaluation performed in step #1.

3b. Add any other comments which will aid in interpretation by the DASU.

- TABB EP-PS-244-B Revision 4 Page 3 of 3 SPECIFIC TASKS: HOW:

HOW:

4. For all EOF produced calculation 4a. EOFDC signs as preparer.

types, ensure the "MIDAS Dose Summary" Report contains required 4b. DAST signs as reviewer.

signatures. For significant changes or indications, notify DASU immediately.

5. Provide Dose Summary Package to DASU with brief verbal explanation/summary of results.

I

- TAB C EP-PS-244-C Revision 3 Page 1 of 2 MAJOR TASK:

Where indicated by calculation results or available field data, notify DASU of trends and/or flag situations where conditions are approaching critical points, triggers or action levels. Monitor possible liquid release pathway, if indicated.

SPECIFIC TASKS: HOW:

1. Review available field, dose la. Review "EOF Dose Assessment calculation, or release data and Flowchart," and/or available job aids meteorological information. and compare to current calculation results and/or field data. Look for dose/dose rate or release values nearing or exceeding those provided in the flowchart.

HELP DOSE ASSESSMENT FLOWCHART See TAB 14

2. If changes in release or dose data 2a. Notify the DASU as soon as possible trend toward values that can trigger with the updated information.

an EAL reclassification, PAR or changes in field monitoring positions, 2b. Discuss changes with the Field Team notify DASU as soon as possible with Director, (FTD).

the updated information and confer with FTD as needed. HELP DOSE ASSESSMENT FLOWCHART See TAB 14 HELP PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE See TAB 11

3. If a liquid release pathway is 3a. Notify the DASU of any liquid release indicated, notify the DASU pathways including radwaste tank leak or immediately. possible plant system leaks into the cooling tower basin or spray pond.

TAB C EP-PS-244-C Revision 3 Page 2 of 2 SPECIFIC TASKS: HOW:

3b. Discuss release pathway with the Field Team Director, (FTD).

HELP PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE See TAB 11 HELP SSES ENVIRONMENTAL SAMPLING STRATEGY See TAB 9

TAB D EP-PS-244-D Revision 3 Page 1 of 3 MAJOR TASK:

Support Field Team Director, (FTD), for team placement and radiological protection.

SPECIFIC TASKS: HOW:

1. Discuss Field Team placement la. Ensure field monitoring and sampling strategy with the Field Team Director, objectives are clearly defined and (FTD). justified relative to the potential radiological risk.

lb. The Radiological Protection objectives are:

1) Limit Field Team TEDE to 2 Rem if possible, 4 Rem otherwise.

and I

2) Limit Field Team Thyroid CDE to 5 Rem per shift and 25 Rem total.

ic. Review current meteorological data to determine potential affected sectors.

1d. Review any previous dose calculations to determine potential radiological conditions in the area.

le. As time permits, provide the "Field Team Director" with a visual display of plume path predicted by "MIDAS."

HELP PLACEMENT OF FIELD TEAMS See TAB 5

TAB D EP-PS-244-D Revision 3 Page 2 of 3 SPECIFIC TASKS: HOW:

2. Provide field teams with radiological 2a. Direct the Field Team Director to begin protection guidance. Thyroid Dose tracking if:

1) Measured RMS Thyroid CDE dose rate > 1000 mrem/hr or

2) Measured iodine air sample canister

> 1200 net cpm.

2b. Determine the necessity and importance of obtaining the data:

1) Has a PAR already been made?

2) What are the benefits/risks associated with obtaining the data?

3) Can the data be obtained another way?

2c. If it is determined that the data cannot be obtained another way, consider:

1) Rotating team§-to limit and equalize dose.

2) Use of respiratory protection (OSCAR only)

3) Processing Dose Extensions

4) Consider administration of KI if conditions warrant.

HELP PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION GUIDE See TAB 6

TAB D EP-PS-244-D Revision 3 Page 3 of 3 SPECIFIC TASKS: HOW:

HELP INSTRUCTIONS FOR OBTAINING CURRENT PERSONNEL EXPOSURE USING NIMS See TAB 12

3. If Thyroid CDE Dose Tracking is required, schedule Field Teams for Whole Body Counts.

TAB 7 EP-PS-244-7 MIDAS OPERATING PROCEDURE TABLE OF CONTENTS A. INTRODUCTION/SYSTEM STARTUP 2

"* AIRBORNE DOSE ASSESSMENT FLOWCHART 4

"* EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS 5

"* SSES BLOWOUT PANEL LOCATIONS 6 B. MENU B: FORWARD CALCULATIONS 7 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS 12 "D. MENU D: DEFAULT ACCIDENT CALCULATIONS 15 E. MENU E-W: BACK CALCULATIONS 18 F. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE

SUMMARY

REPORT 23 G. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES 26 H. ACCIDENT DESCRIPTIONS 27 EP-AD-000-112, Revision 19, Page I of 33

TAB 7 EP-PS-244-7 A. INTRODUCTIONISYSTEM STARTUP

1. The following conventions are used in this procedure to describe computer operations:

a. Bold, upper case text (i.e., CURRENT DATE), denotes text which appears on the screen.

b. Underlined, uppercase text (i.e., LOGIN) denotes text to be typed.

c. Bracketed, upper case text (i.e., [ENTER]), denotes special keys which are to be pressed.

d. Most mouse selections can be made with a single click.

"* Single click RESET to cancel previous screen selections.

"* Double click RESET to back out of present menu.

"* Double click to EXIT menu.

2. The met and vent spreadsheet will appear with all of the meteorological and ventilation release rate parameters across the top of the page. The current time period is highlighted in the left-hand column. The first time interval is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before the current time and the last time interval is 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months after the current time.

3. All required meteorological and ventilation data for MIDAS can be obtained using the METNENT DATA ACQUISITION OPTIONS tab.

4. To start MIDAS:

a. Turn ON each component (monitor, computer, and printer) of the computer system on which MIDAS is loaded.

b. At the MIDAS logon screen, enter the password MIDAS and [ENTER].

c. At the MIDAS MAIN MENU screen, select A: MIDAS (Dose Calculator) and [ENTER].

d. The system will then display the CURRENT DATE. Ifthe date is correct, press [ENTER]. Ifthis date is incorrect, type the correct date using the format which is illustrated in the prompt and press [ENTER].

e. The system will then display the CURRENT TIME, which is stored in the computer system's clock (24-hour clock format). Ifthe time is correct, press [ENTER]. If this time is incorrect, type the correct time using the format which is illustrated in the prompt and press [ENTER].

EP-AD-000-112, Revision 19, Page 2 of 33

TAB 7 EP-PS-244-7

f. The MIDAS logon screen will now appear for 20 seconds.

g. The ACCIDENT MENU SELECTION screen will appear. Use the AIRBORNE DOSE ASSESSMENT FLOWCHART to select the appropriate calculation option and CONFIRM your selection.

5. To exit MIDAS, double-click EXIT on each menu screen that appears. At the SECURITY MENU, press [F8] to log off.

EP-AD-000-112, Revision 19, Page 3 of 33

TAB 7 EP-PS-244-7 AIRBORNE DOSE ASSESSMENT FLOW CHART DETEMJJNE WLEASERATES FF ".E BLOWOUT PAW,.

7ABLE.L*E TKEMFORA MENJS CALCULAflON EP-AD-000-112, Revision 19, Page 4 of 33

TAB 7 EP-PS-244-7 EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS DIRECTIONS

1. Select the appropriate station blowout panel location.

2. Select an appropriate accident source term mix.

3. Use the corresponding design base release rates for input into MENU B.

4. Enter the release rates for one (1) fifteen-minute time period.

NOTE: If Clad Failure or Fuel Melt mixes are selected, multiply the site total noble gas, 1-131, and particulate release rates by the appropriate fraction of clad failure or fuel melt prior to entering the values onto the vent spreadsheet (e.g., the multiplier for 50% FUEL MELT would be 0.5).

[1] BLOWOUT PANEL LOCATION [31 DESIGN BASIS (SITE TOTAL) RELEASE RATES NOBLE GAS 131 'PARTICULATE RCIC PUMP ROOM (pCi/min) (pCi/min) (pCi/min)

[2 ] ACCIDENT SOURCE TERM Normal Reactor Coolant'Activity 1.2E+02" 1.8E+02 1.1 E+03 (LOCA) Reactor Depressurization-No FD 2.6E+06 8.4E+04 2.2E+04 (LOCA) 100% Clad Failure 2.1 E+09 2.4E+08 9.1E+07 (LOCA) 100% Fuel Melt 4.3E+10 1.3E+09 1.7E+09 HPCI PUMP ROOM (pCi/min) (pCi/min) (pCi/min)

Normal Reactor Coolant Activity 2.1 E+03* 3.2E+03 1.9E+04 (LOCA) Reactor Depressurization-No FD 4.6E+07 1.5E+06 3.8E+05 (LOCA) 100% Clad Failure 3.7E+10 4.3E+09 1.6E+09 (LOCA) 100% Fuel Melt 7.5E+11 2.3E+10 3.OE+10 HPCIIRCIC ROUTING AREA (pCi/min) (pCi/minm) (Ci/min)

Normal Reactor Coolant Activity 3.2E+03* 4.9E+03 2.9E+04 (LOCA) Reactor Depressurization-No FD 7.OE+07 2.2E+06 5.8E+05 (LOCA) 100% Clad Failure 5.7E+10 6.5E+09 2.4E+09 (LOCA) 100% Fuel Melt 1.1E+12 3.5E+_10 4.6E+10 RWCU PENETRATION ROOM (pCi/min) (pCi/min) (pCi/min)

Normal Reactor Coolant Activity 7.3E+03* 5.8E+03 6.6E+04 (LOCA) Reactor Depressurization-No FD 1.6E+08 2.6E+06 1.3E+06 (LOCA) 100% Clad Failure 1.3E+11 7.6E+09 5.5E+09 (LOCA) 100% Fuel Melt 2.6E+12 4.1E+10 1.0E+11 RBITB MAIN STEAM TUNNEL (pCi/min) (pCi/min) (pCi/min)

Normal Reactor Coolant Activity 2.6E+04" 3 9E+04 2.3E+05 (LOCA) Reactor Depressurization-No FD 5.6E+08 1.8E+07 4.7E+06 (LOCA) 100% Clad Failure 4.6E+11 5.2E+10 1.9E+10 (LOCA) 100% Fuel Melt 9.1E+12 2.8E+11 3.7E+11 FD = FUEL DAMAGE

Value less than that defining a release (See previous page).

REFERENCE:

EC-RADN-1018, Evaluation of Unmonitored Releases from Station Blowout Panels, Revision 1, File R2-1.

EP-AD-000-112, Revision 19, Page 5 of 33

TAB 7 EP-PS-244-7 SSES BLOWOIT PANEL LOCATIONS

-- NSTEAM*

STEAM * . MAIN .

TUNNEL ~ -. ~rLJNNE---~

U2 TURBINE I ý j 10NTRqQ; BUILDING L S~fiUTUR2

-~~1 -.

'j If 'T

-MAIN STEAM TUNI U2HI'" I --REACTOR BUILDING '.5

- ROUT*

FIPE A".

REA--..*::*:

u I R I -m NG TRUCK BAY ~ CK SAY 2A UII U21PV u;AUS--U

~~~~II 7HR R24RRCIC HRRN RI NO HIGH ENERGY PIPING EP-AD-000-112, Revision 19, Page 6 of 33

TAB 7 EP-PS-244-7 B. MENU B: FORWARD CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

"* TIME OF REACTOR SHUTDOWN

"* RELEASE START TIME

"* DURATION OF RELEASE

"* PROJECTION TIME

"* ACCIDENT SOURCE TERM SELECTION MET DATA

1OMWINDSPEED

10 M WIND DIRECTION

STABILITY CLASS 0 PRECIPITATION RATE VENT DATA

"* SITE TOTAL NOBLE GAS RELEASE RATES

"* SITE TOTAL 1-131 RELEASE RATES

"* SITE TOTAL PARTICULATE RELEASE RATES

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM, OR

b. If you have already initiated calculations and wish to modify either the existing met spreadsheet file or vent spreadsheet, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET or change your initial selection or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page. Place the cursor on the data period corresponding to the start of release. Input the following met data:

EP-AD-000-112, Revision 19, Page 7 of 33

TAB 7 EP-PS-244-7 NOTE 1: Ifthe met data remains the same for successive time periods, the operator need only enter the met data once. MIDAS will persist the data to future time periods automatically.

NOTE 2: Any time historical data is being used in MIDAS (i.e., met and vent data entered into the spreadsheets within the two-hour period up to and including the current time), all met and vent data must be manually entered over all affected time periods up to and including the current time.

If a value is to be repeated in a field it can still be manually copied down the spreadsheet using the K (copy last) key while that value is highlighted.

a. In the column labeled 10M SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled 1DM WD; enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. Ifthis screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

EP-AD-000-112, Revision 19, Page 8 of 33

TAB 7 EP-PS-244-7

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. The vent (GASEOUS VENT AND FLOW) spreadsheet will appear next.

Enter vent data from the START OF RELEASE. The data entry for each 15 minute period is as follows:

NOTE: Vent data may be entered in a regular numerical presentation (10000) or in scientific notation (1.OE+04).

a. In the column labeled TOT NG RELEASE, enter the site total noble gas release rate in liCi/min.

b. In the column labeled TOT 1-131 RELEASE, enter the site total 1-131 release rate in jgCi/min.

c. In the column labeled TOT P RELEASE, enter the site total particulate release rate in jaCi/min.

d. When the data entry is complete, press the X key to save the information and exit the spreadsheet.

5. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM. Select RESET if you wish to change your previous selection.

If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of an appropriate accident source term.

a. Obtain Reactor Power from Engineering, Operations or as follows:

1. From PICSY, select Unit #1 or Unit #2 formats to view affected unit

2. Type STA and press [ENTER]

3. "Reactor Power" is in the top left section

4. Click on MET VENT to return to the Met/Vent data display

b. If the reactor is operating at or greater than 10% power, select the ATWS source term.

c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.

EP-AD-000-1 12, Revision 19, Page 9 of 33

TAB 7 EP-PS-244-7

d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.

6. The RELEASE TIMING SELECTION screen will appear next. There are three lines to the screen.

a. On Line 1, select TRIP DATE (date and time of reactor trip). Using the calendar wheel, enter the appropriate date and time of reactor trip.

CONFIRM to close the calendar wheel.

1) The time of reactor trip must be equal to or earlier than the START OF RELEASE.

2) The time of reactor trip can be set up to roughly one year (8,190 hours0.0022 days 0.0528 hours 3.141534e-4 weeks 7.2295e-5 months ) prior to the START OF RELEASE.

NOTE 1: MIDAS assumes the reactor must be shutdown before a release can occur. The TRIP DATE triggers the start of decay for the accident mix.

NOTE 2: Even during an ATWS, where a release is in progress and the reactor has not shut down, a TRIP DATE must be entered to run MIDAS. It is recommended the same date and time for the START OF RELEASE be used for the TRIP DATE.

Entering a date and time for reactor trip has no impact on decay of the ATWS mix.

b. On Line 2, select START OF RELEASE DATE. Using the calendar wheel, enter the appropriate date and time of the start of release.

CONFIRM to close the calendar wheel.

NOTE: The START OF RELEASE is defined as the date and time of the first vent data entry. This time range includes the two-hour period prior to and including the current time.

c. On Line 3, select REMAINING DURATION of the release. Using the NUMPAD enter the duration of release, in minutes, and select EN or press

[ENTER] to close the numpad. If the duration of release is not known, use the default of 360 minutes, except that for blow-out panel calculations, the assumed release duration is 15 minutes.

NOTE: The REMAINING DURATION (DURATION OF RELEASE) can use forecasted or persisted data for up to 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months into the future.

EP-AD-000-112, Revision 19, Page 10 of 33

TAB 7 EP-PS-244-7

d. Select CONFIRM to continue with the calculation or RESET to change any of your previous choices.

7. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

8. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART REPORT.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

EP-AD-000-112, Revision 19, Page 11 of 33

TAB 7 EP-PS-244-7 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

RELEASE PATHWAY

CORE CONDITION

CONTAINMENT CONDITIONS

FILTRATION

PROJECTION TIME MET DATA S10 MWINDSPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE

1. The EVENT TREE NUREG-1228 SELECTION screen will appear.

a. Using information provided by Engineering Support or Operations, select one cell in each row of the menu. When a cell in thelcurrent row is selected, the next row then appears.

b. [PRINT SCREEN] when final selections are made on the EVENT TREE NUREG-1228 SELECTION screen to document the calculation inputs.

c. CONFIRM entries to continue with the calculation or RESET if you wish to change any of your selections. You may also double-click EXIT to return to the ACCIDENT MENU SELECTION screen.

2. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM, OR

b. If you have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

EP-AD-000-112, Revision 19, Page 12 of 33

TAB 7 EP-PS-244-7

3. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE 1: Ifthe primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled 1DM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) ifthe primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. Ifthe precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION 0(zero)

DRIZZLE or MIST LIGHT STEADY RAIN .MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. Ifthis screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

EP-AD-000-112, Revision 19, Page 13 of 33

TAB 7 EP-PS-244-7

5. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. Ifyou wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

6. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on "thenext page, MORE REPORTS.

c. Ifyou wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

EP-AD-000-112, Revision 19, Page 14 of 33

TAB 7 EP-PS-244-7 D. MENU D: DEFAULT ACCIDENT CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

MET DATA

10 MWINDSPEED

10 MWIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE SOURCE TERM

"* ACCIDENT SOURCE TERM SELECTION

"* PERCENT OF CLAD FAILURE OR FUEL MELT

"* PROJECTION TIME

1. The MET/VENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. Ifyou have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

EP-AD-000-112, Revision 19, Page 15 of 33

TAB 7 EP-PS-244-7

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION _O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.

5. A PERCENT FAILURE FOR LOCA screen will appear if the clad failure or fuel melt accident source term is selected. Input the percent of clad failure or fuel melt using the numpad and CONFIRM.

6. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. If you wish to change any of your previous choices, select RESET.

EP-AD-000-1 12, Revision 19, Page 16 of 33

TAB 7 EP-PS-244-7 NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

7. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: If a hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

EP-AD-000-112, Revision 19, Page 17 of 33

TAB 7 EP-PS-244-7 E. MENU E-W: BACK CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.

PLANT CONDITIONS

TIME OF REACTOR SHUTDOWN

RELEASE START TIME

DURATION OF RELEASE

ACCIDENT SOURCE TERM SELECTION

PROJECTION TIME MET DATA 10 M WIND SPEED

10 M WIND DIRECTION

STABILITY CLASS

PRECIPITATION RATE FIELD DATA

3 FT (CW) SURVEY METER READING 0 DISTANCE FROM PLANT 0 IODINE CARTRIDGE NET CPM OR DEFAULT IODINE MIX

1. The METNENT DATA CONTROL TABLE screen will appear.

a. Select START NEW SCENARIO and then CONFIRM.

b. Ifyou have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.

c. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.

2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.

NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.

a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).

EP-AD-000-1 12, Revision 19, Page 18 of 33

TAB 7 EP-PS-244-7 NOTE 1: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.

b. In the column labeled I OM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).

c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available.

MIDAS will convert the letter entry to a numerical value.

d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:

NO PRECIPITATION O(zero)

DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY

e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.

a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.

b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.

c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.

4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.

If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of an appropriate accident source term:

a. Obtain Reactor Power from Engineering, Operations or as follows:

1. From PICSY, select Unit #1 or Unit #2 formats to view affected unit EP-AD-000-112, Revision 19, Page 19 of 33

TAB 7 EP-PS-244-7

2. Type STA and press [ENTER]

3. "Reactor Power" is in the top left section

4. Click on MET VENT to return to the Met/Vent data display

b. If the reactor is operating at or greater than 10% power, select the ATWS source term.

c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.

d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.

5. The next screen is the FIELD MONITOR PARAMETER SELECTION screen.

Select the appropriate cells and input the information requested using the numpad on the screen or enter the data using the computer keyboard. Once the data entry is complete, CONFIRM to continue with the calculation.

a. If air sample data is available, enter either the IODINE CARTRIDGE reading in net counts per minute or an IODINE CONCENTRATION value in pCi/cc. A zero (0) value may be entered for the net count per minute or the [tCi/cc measurement, if indicated.

b. Select the DEFAULT MIX option if you wish to characterize the iodine source term when air sample data is not available.

6. On the RELEASE TIMING SELECTION screen, enter the estimated remaining duration for the release, then CONFIRM. If the duration of release is not known, use the default of 360 minutes.

7. The PPL

SUMMARY

DATA SELECTION screen allows the user to select different options for the MIDAS DOSE

SUMMARY

REPORT.

a. Select the projection time from the left-hand column if other than the default of six hours is needed.

b. Select the PEAK SECTOR dose rate option if other than the default CURRENT AFFECTED SECTOR is required; then CONFIRM. If you wish to change any of your previous choices, select RESET.

NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The CURRENT AFFECTED SECTOR is used to estimate dose rates based on current wind speed and direction.

EP-AD-000-1 12, Revision 19, Page 20 of 33

TAB 7 EP-PS-244-7

8. After the calculations have completed, the MIDAS DOSE

SUMMARY

REPORT will be displayed on the screen.

a. If you want to select a different projection time or sector designation from the PPL

SUMMARY

DATA SELECTION screen, select RESTART PROGRAM.

b. Ifyou wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.

c. Ifyou wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.

d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].

NOTE: Ifa hard-copy printout is made of the MIDAS DOSE

SUMMARY

REPORT, be sure to fill in the required information documenting the name of the dose calculator, reviewer, and date the calculation was performed.

e. Remote Monitoring System perimeter monitoring location dose rates can be displayed by MIDAS using the perimeter monitoring dose rate screen option.

NOTE: The displayed values are only numeric dose;estimates based on MIDAS calculations. They are not "real-time" readings from the perimeter monitor system.

Directions for accessing the MIDAS perimeter monitor dose rate screen option are as follows:

1) At the MIDAS DOSE

SUMMARY

REPORT screen, select CONTINUE.

2) On the next screen select MORE REPORTS.

3) From the MORE REPORTS SELECTION screen, select FM GAMMA DOSE RATE PLOT and CONFIRM.

4) From the REPORT PARAMETER SELECTION screen, choose the appropriate projection time and CONFIRM.

EP-AD-000-112, Revision 19, Page 21 of 33

TAB 7 EP-PS-244-7

5) From the MAP SELECTION screen, select MAP SCALE and input 1.25 miles, then CONFIRM.

6) On the next screen, select MAP FEATURES.

7) On the next screen, select CALCULATED PERIMETER MON DOSE RATES and CONFIRM.

8) To exit, select CONTINUE, MORE REPORTS, and EXIT.

EP-AD-000-112, Revision 19, Page 22 of 33

TAB 7 EP-PS-2444 F. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE

SUMMARY

REPORT

1. PRINT DATE/TIME Date and time MIDAS DOSE

SUMMARY

REPORT was printed.

2. CURRENT TIME PERIOD Current meteorological time period used for dose projections provided on quarter hour increments to match met spreadsheet entries.

3. REACTOR SHUTDOWN Date and time of reactor shutdown.

4. START OF RELEASE This is the date and time of first dose calculation as indicated by the first positive vent release rate value entered on the vent data spreadsheet or if the vent spreadsheet is not used, the date and time of the met data used for the current projection period.

NOTE: For MENU C: NR-1228 CALCULATIONS, MENU D: DEFAULT CALCULATIONS, and MENU E-W: BACK CALCULATIONS, it is conservatively assumed that the date and time of reactor shutdown is concurrent with the start of release.

5. MENU SELECTION Identifies the dose calculation option used for the current dose projection summary report. Choice of four options:

"* MENU B: FORWARD CALCULATIONS

"* MENU C: NR-1228 CALCULATIONS

"* MENU D: DEFAULT CALCULATIONS

"* MENU E-W: BACK CALCULATIONS

6. SOURCE TERM Identifies the source term used for the current dose projection summary report calculations. Choice of six options:

"* ATWS-Normal Reactor Coolant Activity (UNDECAYED)

"* Normal Reactor Coolant Activity (DECAYED)

EP-AD-000-1 12, Revision 19, Page 23 of 33

TAB 7 EP-PS-244-7

"* (LOCA) Coolant Activity Leak with Depressurization S;pike-No Fuel Damage

"* (LOCA) Cladding Failure-Gap Release

(LOCA) Fuel Melt-Early In-Vessel Release

"* Fuel Handling Accident

7. MET DATA Meteorological data (wind speed, wind direction, stability class, and precipitation rate) used for the summary report dose projections.

8. CURRENT AFFECTED SECTOR OR PEAK SECTOR DOSE RATES This table provides the TEDE, EDE, and THYROID CDE dose rates calculated at the OSCAR and EPB distances. These rate calculations are based on a variable projection/integration period for the current affected sector or peak sector.

9. PROJECTED DOSES This table provides a TEDE and THYROID CDE dose projection calculated at the OSCAR, EPB, 2-mile, and 10-mile distances for varying projection times.

The projection time will appear in the header line e.g., 4 HOUR PROJECTED DOSES on the MIDAS DOSE

SUMMARY

REPORT. The sector designation for this dose projection is based on the maximum calculated dose determined from all sixteen sectors for the given projection time. Information for distances between 10 and 50 miles is available using the "More Reports" feature.

10. CALCULATED/REVIEWED BY The sign-off for review of calculation results is done for documentation purposes. The intended review does not necessarily mean an independent verification of each input to the calculation but more an interactive discussion between the RPC/HP Level II Dose Calculator and/or DASU/DAST (or dose calculator) to ensure the calculated results are reasonable based on current plant and environmental information.

This review should occur before the calculated results are used for any emergency classification determinations or protective action recommendations.

11. COMMENTS Section added to provide space for additional statements of qualification or background information pertaining to the dose projections.

EP-AD-000-112, Revision 19, Page 24 of 33

TAB 7 EP-PS-244-7 MIDAS DOSE

SUMMARY

REPORT Q PRINT DATE/TIME: 8/19/97 11:25 CURRENT TIME PERIOD: S/997 11:39 MIDAS DOSE

SUMMARY

REPORT SREACTOR SHUTDOWN: 8n19/97 18:53 MIND SPEED C(PH): 5 START OF REX.EASE: 8/19/97 19:53 MIND FROM CDEG): 129 CES)

KEU SELECTION: FORWIARD CALCULATIONS STABILITY CLASS: J SOURCE TERM: LOCA (CLAD FAILURE) -P] PRECIPITATION: NO CURRENT (SITE TOTAL) RELEASE RATE

( uCie'mi n)

NOBLE CAS 1-131 PARTICULATES 6.98E+89 9.. 9,E+8-1 9.96E+61 UNIT"S :DOSE IOT'E5- IJFFFCTE; "OSE ITEZEAFFE*CTED T9ERrE 183.4q2 RHMl TEDE mr-'E(*evnohr) (elhx) 775.90 1111

" SCAR-SECTOR

.EDE ]RATE 88.27.9 SECTOR LOCAT 101 Ot t

THY CD)E 8.2"2"- .16 RATE I B

IIE--93

-1.

3 E.03 3.3GE-ID3 CALCULATED BY:__________ DATE:_

NEU I EI4ZD BY: _________________

DATE:

COMMENTS:

I +l!Ih1T EP-AD-000-112, Revision 19, Page 25 of 33

TAB 7 EP-PS-244-7 G. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES

1. From the MIDAS DOSE

SUMMARY

REPORT screen, select CONTINUE and, on the next page, MORE REPORTS.

2. Select TEDE 4-DAY DOSE REPORT or THYROID CDE DOSE REPORT, depending on which PAR guide has been exceeded at the 10-mile distance.

3. On the REPORT PARAMETER SELECTION screen, select PROJECTION TIME until the appropriate PROJECTION TIME (0.25, 4, 6, or 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ) is displayed on the screen; then select CONFIRM.

4. The screen will now display projected doses at the EPB and at 2, 5, 10, 25, and 50 miles. To obtain finer increments of distance, select CONTINUE until the desired range of distances is displayed.

NOTE: An objective is to determine the approximate distance from the plant at which dose projections are less than 1 rem TEDE and 5 rem THYROID CDE. A PAR is then likely to be issued to the next furthest 5-mile distance increment from the plant.

Example: A PAR for distances to 30 miles may be selected if projected doses become less than the PAG values (1 rem TEDE, 5 rem THYROID CDE) between 25 and 30 miles from the plant.

EP-AD-000-112, Revision 19, Page 26 of 33

TAB 7 EP-PS-244-7 H. ACCIDENT DESCRIPTIONS A. DEFAULT ACCIDENT DESCRIPTIONS (MENU B AND MENU D)

1. NORMAL REACTOR COOLANT ACTIVITY This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system with no damage to the fuel and no activity spiking. The source term for this accident is normal reactor coolant system liquid and steam activity.

2. LOCA (RX DP-NO FD)

This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system. Depressurization of the primary coolant system is assumed, resulting in an activity spike in the reactor coolant. The source term for this accident is normal reactor coolant liquid and steam activity plus the depressurization activity spike. There is no fuel damage.

3. LOCA (CLAD FAILURE)

This accident scenario is defined as a Loss-of-Coolant Accident which results in.damage to the reactor fuel cladding. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the fuel clad gap. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.

4. LOCA (FUEL MELT)

This accident scenario is defined as a Loss-of-Coolant Accident which results in damage to the reactor fuel. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the reactor fuel. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.

5. FUEL HANDLING ACCIDENT This accident scenario is defined as a fuel handling accident which results in the release of spent fuel activity. The source term for this accident is spent fuel gap activity assuming a decay time after shutdown of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

EP-AD-000-1 12, Revision 19, Page 27 of 33

TAB 7 EP-PS-244-7

6. ATWS This accident scenario is used for releases from a reactor unit continuing to operate at or greater than 10% power. The source term for this accident is normal reactor coolant system liquid and steam activity. The source term is undecayed; that is, no reactor trip is assumed to have occurred.

NOTE: For Menu D calculations, design basis assumptions are utilized.

For example, design basis leakage rates are assumed and iodine filtration efficiency of 99% is assumed in those pathways for which filters are in place.

NOTE: The source term for Menu D accident types is fixed. Release rate is calculated by MIDAS by dividing the total activity released by a predetermined release duration (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all but fuel handling accidents, for which release duration is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

B. NUREG 1228 ACCIDENT TYPES (MENU C)

1. LOCA - DRYWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release into the drywell which bypasses the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the environment.

2. LOCA - WETWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release through the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the environment.

3. LOCA - CONTAINMENT BYPASS RELEASE This accident is a Loss-of-Coolant Accident with an activity release to the environment that bypasses the containment and the Standby Gas Treatment System.

4. ZIRCALLOY FIRE IN ONE THREE MONTH OLD BATCH This accident is a zircalloy fire in spent fuel that results in an activity release similar to a core melt. It assumes that the activity is filtered by the Standby Gas Treatment System prior to release.

EP-AD-000-1 12, Revision 19, Page 28 of 33

TAB 7 EP-PS-244-7

5. SPENT FUEL GAP RELEASE This accident is a release of fuel gap activity from the spent fuel pool with treatment by the Standby Gas Treatment System prior to release.

NOTE: Menu C (from NUREG-1228 Event Tree Analyses) is used to relatively quickly provide a bounding estimate of offsite dose, for situations where there are substantial uncertainties in prediction of source term and any resultant doses.

EP-AD-000-112, Revision 19, Page 29 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR DRYWELL RELEASE DRYWELL WETWELL CONTAINMENT SPENT FUEL RELEASE RELEASE BYPASS RELEASE POOL RELEASE (100% Clad Failure) (100% Fuel Melt) (100% Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN SPRAY ON SPRAY OFF Status of Drywell Containment Spray HOLDUP TIME HOLDUP TIME HOLDUP TIME Drywell Holdup Time:

<1 HOUR 2-12 HOURS 24 HOURS Time from Release into Containment to Start of Release into Environment LEAK RATE LEAK RATE 10 A LEAK RATE DESIGN DESIGN 100% HOUR 100% DAY 100% DAY LEAK RATE LEAK RATE

-UNFILTERED FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1% Day Containment Failure EP-AD-000-1 12, Revision 19, Page 30 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR WETWELL RELEASE WETWELL CONTAINMENT SPENT FUEL RELEASE BYPASS POOL RELEASE RELEASE (100% Clad Failure) (100% Fuel Melt) (100% Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

>30 MIN I SATURATED I SUB-COOLED Conditions in Suppression Pool HOLDUP TIME HOLDUP TIME HOLDUP TIME Wetwell Holdup Time:

<1 HOUR 2-12 HOURS 24 HOURS Time from Release into Wetwell to Start of Release into Environment LEAK RATE LEAK RATE LEAK RATE DESIGN DESIGN 100% HOUR 100% DAY 100% DAY LEAK RATE LEAK RATE UNFILTERED FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1% Day Containment Failure EP-AD-000-112, Revision 19, Page 31 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR CONTAINMENT BYPASS RELEASE WETWELL CONTAINMENT SPENT FUEL POOL RELEASE BYPASS RELEASE RELEASE (100% Clad Failure) (100% Fuel Melt) (100% Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED

> 30 MIN I UNFILTERED FILTERED Is Release Filtered?

RELEASE RATE RELEASE RATE TYPICAL DESIGN Release Rate, in 100% HOUR 100% DAY RELEASE RATE Terms of Percent of Core Inventory Catastrophic Failure to Isolate Containment Failure Corntainment 1% Day EP-AD-000-112, Revision 19, Page 32 of 33

TAB 7 EP-PS-244-7 NUREG 1228 MENU STRUCTURE FOR SPENT FUEL POOL RELEASE CONTAINMENT DRYWELL WETWELL SPENT FUEL POOL RELEASE BYPASS RELEASE RELEASE RELEASE ZIRCALLOY FIRE IN GAP RELEASE GAP RELEASE Condition of Spent ONE3 FROM ONE 3 FROM 15 Fuel MONTH OLD MONTH OLD BATCHES BATCH BATCH (TOTAL POOL)

SPRAY ON SPRAY OFF Status of Containment Spray (Default) into Pool HOLDUP TIME HOLDUP TIME Time from Release

<1 HOUR 2-12 HOURS from Fuel to Start of Release into Environment LEAK RATE LEAK RATE LEAK RATE 100% HOUR 100% DAY Release Rate, in 100% DAY UNFILTERED FILTERED Terms of Percent of Source Inventory Catastrophic Failure of Containment EP-AD-000-1 12, Revision 19, Page 33 of 33

TAB 14 I TEST FOR IODINE VALIDITY I EP-PS-244-14 YES ..I P- Iodine Datai Valid AMhi.

I-*IMIJ Initiate Chemistry Sample of Vent YES and Determine NG/1-131 ratio YES YES SYES F

Consider 1-131 Consider 1-131 DATA INVALID DATA VALID Unless Chemistry Data Unless Chemistry Data Indicates Otherwise Indicates Otherwise EP-AD-000-087 Revision 3, Page 3 of 4

EOF DOSE ASSESSMENT FLOWCHART TAB 14 E-4414 FACILITY STATUS Dose Assessment Supervisor

Recovery Manager Info and Target Takeover Time Dose Assessment Staffer

- Phones/Fax Field Team Director

- RMS/Radio/Phones EOF Dose Calculator

- MIDAS/PICSY Rad Uaison

- Phones/DEP-BRP "A" and "B"Field Teams

- Kits/Vehlcies/Phones/Radios EVENT STATUS RPC to DASU TSC DC to DAST HP Radioman to FTD "A" and "B" Team Briefing Staff Briefing and Info Exchange TURNOVER RPC to DASU ALL Calculations OSCAR Control DEP/BRP Communications Event/Source Term Agreement Liquid/Airborne Release Previous Data Transferred Turnover Time --

L* ,* J MONITOR EFFLUENT RELEASE A ND PLANT STATUS SI

PICSY MetVent Data SJ*Field Team and Fixed Monitor Data '

Sj **InPlant Conditions

"* -YS~ De~~faulggts .- J 1 NO

PC-..Y.Dat~a *Emmm S(note YES Accident3 triggers PQ2) ,Is PI White? E Filtered Cnutwt Design Basis Engineering YES Leakage on Release? Low Confidlence IRE ESNUR G Cenwhite)JData 4,EY S Triggers? No

'~No ei YtidData Valid? G a Default Accident Calculation MIDAS MlenuD Ji ,ý ES Ioin (Helplp Pg34 Ný YES-- Field TeNm PefomBakCacuaiolowFetiRainon UnmSnetrredeReeease

Select appropriate TEDE and THY CDt ConrolEuosuednd1os

...... Ds Release Pathway andDSource Term ICauatDdata Lt with Engineering Support Supervisor Repurt Classlficatios and PAR Triggers Im RM [

SSelect PAR at Command and Control Table per PARGuide

'Approve PAR Forms *4 Contact DEP/BRP aS>Remn Rem WBThy *CDE/Shift w/Emerg Extension

-About every 30 Minutes S Rem Thy CDE Total ConsIder transition from YEea Perud1000

""Initiate Thy CDETracklng plume to post plume phase te 1 NO mrem/hr Thy CDE for Env Sampling Teams r *1200 ncpm UConsider WMC (cartridge)

I EP AD-C000-87. Revision 3, Page I of 4

TAB 14 TAB 14 EP-PS-244-14 EP-PS-244-14 NOTE 1 NOTE 2 NOTE 3 NOTE 4 NOTE 5 VENT RELEASE RMS/FIELD DEFAULT'ACCIDENT NUREG 1228 LIQUID RELEASE TRIGGERS TRIGGERS TRIGGERS TRIGGERS TRIGGERS

AIRBORNE RELEASE

AIRBORNE RELEASE BLOWOUT PANEL RELEASE

UNFILTERED VENT RELEASE

LIQUID RELEASE

+ RELEASE RATE> DESIGN BASIS 1%/DAY

>8.51 E5 gci/min NG > 0.1 mrem/hr WB

References:

CORE UNCOVERED > 15 MINUTES S Liquid Effl. > TRM

>1.04E2 pci/min Iodine > 68.4 mrem/hr Thy CDE 0 MIDAS Operating Procedure, SPENT FUEL POOL RELEASE

>7.72E2 gci/min Part. >100 ncpm on 1 Cartridge EP-AD-O00-1 12

Blowout Panel Guidance/Data Sheet, EP-AD-000-094

EAL 15.1 FORGOmin.

EAL15.1

>1.70E6 Jtci/min NG Liquid Effl. > TRM

>2.08E2 pci/min Iodine

>1.54E3 gLci/min Part.

EAL15.2forl5min.

EAL3.2

EAL15.2 SEVERE CLAD DEGRADATION

>1.70E8 jici/min NG >200 R/hr CHRM Liquid Effl. > 10 x TRM

>2.08E4 ci/min Iodine >300 gci/cc DE 1-131

>1.54E5 pci/min Part.

+ EAL 15.3 + EAL 3.3 SEVERLY DEGRADED CORE Projected dose rates @EPB > 400 R/hr CHRM

>100 mrem/hr TEDE for 30min or > 1000 pci/cc DE 1-131

>500 mrem/hr THY CDE for 30min or

>15 rem/hr TEDE for 2min or

>75 rem/hr THY CDE for 2min Projected dose @EPB

>500 mrem TEDE within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

+ EAL15.4 + EAL 3.4 CORE MELT Projected Dose @ EPB >400R/hr CHRM

> 1 Rem TEDE >1 000pci/cc DE Iodine-131

> 5 Rem THY CDE > 2000 R/hr CHRM LEP-AD-000-087, Revision 3, Page 2 of 4 I

TAB 14 EP-PS-244-14 I

I QUESTIONABLE NOBLE GAS DATA I I QUESTIONABLE IODINE DATA I I QUESTIONABLE PARTICU LATE DATA I I

I II SPING NG SPING IODINE SPING PARTICULATE Value(s) White Value(s) White Value(s) White IT Consult with Engineering Consult with Engineering Consult with Engineering

Is condition normal and

Is condition normal and

Is condition normal and acceptable due to no acceptable due to no acceptable due to no flow through the vent? flow through the vent?

flow through the vent?

Is the release through

Is the release through an unaffected vent?

I an unaffected vent?

Note: Ia Data will turn white due to High Resolution Time

(-lhr @ 2E4 uCi/min) r NG Ilodineý P.articu late NO Totals YES NO Totals YES NO YES Valid? N*NValid?0 otlsVaid p.

T Take Appropriate Action: Take Appropriate Action:

Take Appropriate Action: Continue Using Continue Using "* Use default value ',Continue Using "* Use default value

"* Restore Channel SPING DATA SPING DATA SPING DATA NG/l=1,000 NG/Part.=1 0,000

"* Obtain/Analyze Vent "* Use last valid NG/I "* Use last valid NG/Part.

Sample(s) if appropriate if appropriate

"* Initiate PAVSS "* Restore Channel "* Restore Channel

"* Obtain Air Sample(s) "* Obtain/Analyze "* Obtain/Analyze

"* Obtain Field Reading SPING or PAVSS SPING or PAVSS Vent Sample(s) Vent Sample(s)

"* Initiate PAVSS "* Initiate PAVSS

"* Obtain Air Sample(s) "* Obtain Air Sample(s)

"* Obtain Field Reading "* Obtain Field Reading EP-ADO-000-087, Revision 3, Page 4 of 4

TAB 15 EP-PS-244-15 MIDAS calc. #

MIDAS BLOWOUT PANEL (B) GUIDANCE/DATA SHEET When to perform: As directed by the DAST when an unmonitored radiological release through a blowout panel has occurred or is considered likely to occur.

Frequency: As directed by the DAST. Note: Usually once and done unless changing plant conditions require additional assessment.

Data/information Required Meteoroloqical Data: Primary Data Source - PICSY Met Vent Screen (directions from PICSY Main Menu Screen, point and click uE-plan menu" then "Met Vent Data Display")

Secondary Data Source - Use Tab 8.

l0mws mph 10m wd degrees AT _C or Wind Speed Corrected Stability Class Calculate precipitation rate: PICSY rate , in/hour + 4 = in/15 min Release Data: Data Source - DAST/Engineering will provide blowout panel location, accident source term (see below), and, if required, % clad failure or % fuel melt.

Design Basis (site total) Release Rates are obtained from form in Help Tab 7.

Blowout panel location (circle one): RCIC pump room HPCI pump room HPCI/RCIC routing area RWCU penetration room .RB/TB main steam tunnel

% of fuel damage x 0.01 = Fuel Damage multiplier (below)

Design Base release rates X Fuel Damage multiplier = Corrected release rates Noble gas _______ x = _ _ _ Ci/min 1-131 x = __ LCi/min Particulate x = _ _ _ _ Ci/min Accident Source Term: Data source - DAST/Engineering (circle one)

ATWS Normal Rx Coolant LOCA (Rx DP, no FD)

LOCA (clad failure) LOCA (fuel melt) Fuel Handling EP-AD-000-094, Revision 2, Page I of 2

TAB 15 EP-PS-244-15 Release Timing: Data source - DAST/Engineering Start of release: Date Time Rx Trip date: Date Time (note: must be before start of release)

Remaining duration: 155 minutes (release rates are only applicable to a 15 minute period)

Summary Data Selection: Data Source - DAST (Note: shaded selections are default) (circle ifother than default)

Projection time: 0.25 hr 4 hr 9 hr Affected Sector: sectr>i Peak sector Reason for using other than default:

EP-AD-000-094, Revision 2, Page 2 of 2

TAB 18 EP-PS-244-18 RESPONSIBILITIES OF INITIAL AND AUGMENTED EOF RADIOLOGICAL ASSESSMENT STAFF AFTER TURNOVER

1. DOSE ASSESSMENT SUPERVISOR A. Initial

Primary manager of EOF radiological function

Primary representative of EOF radiological function at command and control table

Signature authority for EOF radiological function on PAR forms, dose extension forms, and potassium iodide administration forms.

B. Supplemental While not a "minimum staffing" position, a second qualified DASU may be able to significantly assist the staff perform functions such as the following*:

9 Assisting the DASU and the DAST-A by maintaining an overview of the dose assessment function and communicating insights to the DASU and the DAST-A (e.g. are ongoing actions consistent with those expected from using the dose assessment flowchart, are staffers fully communicating with one another, are the right questions being forwarded to the Engineering Support staffers, are forward looking actions being discussed) o Assisting the DAST-A in communicating with the Engineering Support and other staffs as necessary

' Working with the Radiological Liaison (RL) to ensure that queries from agencies are being answered; working with the RL, in communicating PARs to the agencies.

The RL, may even wish to have the supplemental DASU do PAR communications to the state and other agencies.

Assuming the duties of the DASU should the DASU need torelinquish duties for a period of time (ensuring the appropriate turnover and communications occur)

NOTE: The first three actions are especially important if the DASU-A is needed at the command and control table for a significant portion of the time.

I1. DOSE ASSESSMENT STAFFER A. Augmented

"* Continuous direction, coordination, and review of operations in the dose assessment area

"* Communications with Engineering Support to address radiological group needs and to provide relevant information to the engineering staff

"* Communication with DASU to ensure Supervisor has an accurate overview of off-site radiological conditions and ability to provide overall input to and direction for function

"* Secondary EOF dose calculator, reviewer of EOF dose calculations EP-AD-000-076, Revision 0, Page I of 2

TAB 18 EP-PS-244-1 8 B. Initial

Primary EOF dose calculator, using MIDAS or other dose calculation tools Ill. FIELD TEAM DIRECTOR A. Augmented o Direction of field monitoring team efforts to determine radiation and/or radioactive material concentration levels around the site o Performance or direction for use of the Emergency Remote Monitoring System (ERMS) to assess radiation and/or radioactive material concentration levels around the site o Tracking and control of field monitoring team exposure o Communication of results of monitoring efforts to the DASU and the DAST-A B. Initial While not a "minimum staffing" position after the turnover to the FTD-A has occurred, the FTD-I may be able to significantly assist the FTD-A by staying on to perform functions such as the following*:

Taking a lead role in directing the monitoring of airborne releases from the station should there be "simultaneous" liquid and airborne releases to the environment (thereby, the FTD-A taking the lead on performing liquid release calculations and directing associated river monitoring related to the airborne release)

For the more likely situation of a single release (assumed to be airborne):

"* Assisting the FTD-A with communications and direction of field teams information from the ERMS to the FTD-A and the DAST-ANDASU

"* Assisting the FTD-A in answering queries about the field monitoring team members

"* Assuming the duties of the FTD-A should the FTD-A need to relinquish duties for a period of time (ensuring appropriate turnover and communications occur)

The important item is mutual agreement on roles and responsibilities of the supplemental DASU and FTD;l, and the communication of those roles and responsibilities so that the entire EOF-radiological assessment staff is aware of them. In the absence of mutually defined and communicated roles and responsibilities, the roles of DASU and FTD are the responsibilities of the DASU-I and the FTD-A, respectively.

NOTE: Once state and/or federal monitoring teams arrive, and/or once a Federal Radiological Monitoring and Assessment Center has been established, roles are likely to change. Augmented staff personnel may report to the FRMAC. Initial staff may stay at the EOF or report to the FRMAC to assist with the PPL contribution at that facility.

EP-AD-000-076, Revision 0, Page 2 of 2

Sep. 26, 2002 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2002-4421 I

USER INFORMATION:

FLAI-RLAUfTEL D EMPL#:23244 CA#: 0363

'9drzzp. ITUCOA2.

Phone#: 254-3658 TRANSMITTAL INFORMATION:

TO. ,LAIfl*LA'nL D 09/26/2002 LOCATION: DOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

"--THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

245 - 245 - DOSE ASSESSMENT SUPERVISOR REMOVE MANUAL TABLE OF CONTENTS DATE: 08/26/2002 ADD MANUAL TABLE OF CONTENTS DATE: 09/25/2002 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-245 REMOVE: REV:3 ADD: REV: 4 UPDATES FOR HARD NOTE: Additional TabRIBUTED WITHIN 5 DAYS IN T PROCEDURES. PLE Changes Attached ACKNOWLEDGE COMPLm+/-r L"v ivun s ... -J0O

'ON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

PROCEDURE COVER SHEET PPL SUSQUEHANNA, LLC NUCLEAR DEPARTMENT PROCEDURE DOSE ASSESSMENT SUPERVISOR: EP-PS-245 Emergency-Plan-Position-Specific-Instruction Revision 4 Page 1 of 4 QUALITY CLASSIFICATION: APPROVAL CLASSIFICATION:

QA Program (X) Non-QA Program ( ) Plant!".. i> E,(, ) Non-Plant Plat,,,,

Y N (X) ,Instructiorn *'ý ,

EFFECTIVE DATE.

PERIODIC REVIEW FREQUENCY:'"` Two Years PERIODIC REVIEW DUE-DATE RECOMMENDED REVIEWS: <,

All "

Procedure Owner: Nuclear Emergency Planning Responsible Supervisor: Supervisor-Operations Technology Responsible FUM: Supervisor-Nuclear Emergency Planning Responsible Approver: General Manager-Plant Support FORM NDAP-QA-0002-1, Rev. 3, Page 1 of I

EP-PS-245 Revision 4 Page 2 of 4 DOSE ASSESSMENT SUPERVISOR: Emergency-Plan-Position-Specific Instruction WHEN: EOF is activated HOW NOTIFIED: Paged/telephone REPORT TO: Recovery manager WHERE TO REPORT: Emergency Operations Facility OVERALL DUTY:

Manage radiological functions in the EOF, which includes providing Radiological component of the protective action recommendation to the Recovery Manager.

MAJOR TASKS: TAB: REVISION:

I Obtain, then keep current, information you will need to manage the radiological functions in the EOF.

TAB A 2 Recommend changes to the emergency TAB B 1 classification to the Recovery Manager, if needed.

I Recommend public protective actions to the Recovery Manager.

TAB C 3 Manage assessing and communicating TAB D 3 radiological information from the EOF.

Recommend protective actions for PPL TAB E 2 emergency personnel to the Recovery Manager.

Provide direction for field monitoring strategy. TAB F 0 Support termination activities. TAB G 0 Assist re-entry/recovery efforts. TAB H 0 Make sure information and functions that are TAB I 1 in progress during shift relief are turned over smoothly.

EP-PS-245 Revision 4 Page 3 of 4 SUPPORTING INFORMATION: TAB:

EOF Dose Assessment Flowchart TAB 1 Emergency Classification TAB 2 Public Protective Action Recommendation Guide TAB 3 Supplementary Meteorological Information Table TAB 4 Emergency Forms TAB 5

Shift Takeover Checklist

Protective Action Recommendation Form Responsibilities of Initial and Augmented EOF TAB 6 Radiological Assessment Staff after Turnover

- EP-PS-245 Revision 4 Page 4 of 4

REFERENCES:

EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92-001 May 1992)

FDA Guidance: "Accidental Radioactive Contamination of Human Food and Animal Feed and Recommendations for State and Local Governments." Federal Register, pp 47073-47083, October 22, 1982 ICRP Publication 28, The Principles and General Procedures for Handling Emergency and Accidental Exposures of Workers. International Commission on Radiation Protection. (1978)

IE Notice 83-28 NCRP Report 55, Protection of the Thyroid Gland in the Event of Releases of Radioiodine, National Council Radiation Protection and Measurements. (1977)

NUMARC Graded Response Study NUREG-0654, Planning Standards and Evaluation Criteria NUREG-0731, Guidelines for Utility Management Structure and Technical Resources, September 1980 Radiological Assessment Reference Book Spray Pond Blowdown Water Outlet Flow Rate PLI 50258 (May 8, 1987)

Susquehanna SES Emergency Plan 10 CFR 20 Appendix B Study of Travel Time and Mixing Characteristics for the Susquehanna River below the Susquehanna SES - SUTRON CORPORATION - November 1985 NDAP-QA-1 190, Nuclear Department Radiation Protection Program and Policies NDAP-QA-1 191, ALARA Program and Policy NEPM-QA-1014, Radiological Environmental Monitoring Program SSES Emergency Plan National Interim Primary Drinking Water Regulations, EPA 570/9-76-003 (U.S.) Environmental Protection Agency, Washington, D.C. 1976 Commonwealth of Pennsylvania State Emergency Operations Plan, Appendix 6 to Annex E BRP Technical Assessments and Protective Actions, September 22, 1988.

EC-ENVR-1047, Protective Action Guides, (PAGs), for the Evaluation of Abnormal, Unusual, or Unplanned Liquid Releases to the Susquehanna River

TABA EP-PS-245-A Revision 2 Page 1 of 7 MAJOR TASK:

Obtain, then keep current, information you will need to manage the radiological functions in the Emergency Operations Facility.

SPECIFIC TASKS: HOW:

1. Read the "Chronology of Events" upon arrival.

2. Prepare for turnover from TSC. 2b. Confirm staff is ready to assume control of Dose Assessment:

(1) Fully staffed (as a minimum, the DASU, DAST and FTD are present)

(2) Prepared to perform and evaluate dose calculations (3) Prepared to assume control of field teams.

(4) Prepared to assume communications with DEP/BRP.

3. Obtain The radiological history and 3a. Talk to the Recove[y Manager and technical picture of the emergency. obtain:

(1) Technical picture of conditions at the plant and its prognosis.

(2) Target turnover time NOTE:

Only steps through 3a are necessary to complete prior to EOF activation.

- TAB A EP-PS-245-A Revision 2 Page 2 of 7 SPECIFIC TASKS: HOW:

3b. Obtain radiological history from the on-shift Dose Assessment Supervisor, (if applicable), or the Radiation Protection Coordinator, (if TSC still in charge).

(1) Who has control of the Rad Function? (TSC or EOF)

(2) Open items (3) Type(s) and magnitude(s) of release(s)

(4) Status of the emergency (5) Last transmitted PAR Form.

3c. Consult with members of the Dose Assessment Staff:

(1) Brief staff on accident status and current PARs (2) Obtain Shift Takeover Checklist and record:

(a) MIDAS information from DAST (b) Field Team and RMS Data from FTD HELP SHIFT TAKEOVER CHECKLIST See TAB 5

4. Contact the Radiation Protection 4a. Confirm the EOF will assume Coordinator and confirm turnover, responsibility for forward calculations.

4b. Confirm the EOF will assume responsibility for back calculations.

- TABA EP-PS-245-A Revision 2 Page 3 of 7 SPECIFIC TASKS: HOW:

4c. Confirm the EOF will assume responsibility for study case calculations.

4d. Confirm the EOF will assume responsibility for OSCAR.

4e. Determine time for EOF to assume communications with DEP/BRP.

4f. Obtain current plant radiological status.

4g. Obtain current effluent release status.

4h. Determine status of latest dose calculation.

5. Accept turnover of Dose Assessment 5a. Turnover can be part of the TSC/EOF responsibilities. facility turnover or can be conducted after conference call.

6. Maintain awareness of plant status 6a. Periodically discuss with other managers:

and prognosis.

(1) EOF Support Supervisor (2) Engineering Support Supervisor (3) Recovery Manager (4) Radiation Protection Coordinator HELP EOF DOSE ASSESSMENT FLOWCHART See TAB I 6b. Periodically meet with the Dose Assessment Staffer and Field Team Director to discuss:

(1) Dose Assessment Summary Sheets (2) Results of Dose Calculations

- TAB A EP-PS-245-A Revision 2 Page 4 of 7 SPECIFIC TASKS: HOW:

(3) Field Team and RMS results and team placement strategy (4) Meteorological observations and forecasts (5) Communications obstacles and opportunities

7. Assess reliability of data. 7a. Periodically evaluate data by:

(1) Reviewing measured/calculated dose rate ratios.

(2) Determining if low confidence (white), PICSY data exists.

NOTE:

"White" data is an indication of unreliable data. It may be normal and acceptable due to low or no flow in the SPING Monitor or may indicate a release exceeding the range of the instrument or an indication of instrumentation/

computer interface problems.

NOTE:

White data should be considered as a potential unmonitored release condition unless Engineering or Chemistry data indicates otherwise.

(3) Determining if Iodine detection channels are over responding due to interference from noble gas or short lived nitrogen isotopes. In general, data is suspect if the NG1i-1 31 rate ratio is less than 1,000 for a given vent.

-TABA EP-PS-245-A Revision 2 Page 5 of 7 SPECIFIC TASKS: HOW:

HELP DOSE ASSESSMENT FLOWCHART See TAB 1 Page 3 7b. If low confidence (white), PICSY data exists:

(1) Consult with Engineering to determine if condition is normal (i.e., per design) and if vent totals are valid from the Engineering or.

Dose Assessment perspective.

(2) If vent totals are considered valid from the measured/calculated ratios (measured to projected dose is within 0.1 to 5 range), use forward calculations with caution.

If measured field data is higher than projected values, perform a Back Calculation and use the more conservative results.

7c. If PICSY vent totali are questionable:

(1) Request Engineering promptly pursue corrective actions, obtain Chemistry vent sample data, and/or evaluate need to switch vent monitoring to PAVSS.

(2) Notify RPC and discuss alternate methods to obtain release data (e.g., HP air samples) and/or need to switch to PAVSS.

TAB A EP-PS-245-A Revision 2 Page 6 of 7 SPECIFIC TASKS: HOW:

HELP EOF DOSE ASSESSMENT FLOWCHART See TAB I Pg. 3 for Questionable Data (3) Use appropriate alternate data such as grab sample (vent, PAVSS, HP air samples) results, or previously measured or default noble gas to Iodine/particulate ratios in Forward Calculation.

(4) Ensure field teams are taking air samples as appropriate and consistent with ALARA principles.

(5) Report conditions as a potential unmonitored or an unmonitored release as appropriate depending on measured to projected dose rate ratios.

(6) Initiate Back Calculations if field data is available and as appropriate a Default Accident or NUREG 1228 MIDAS Calculation.

8. Provide VALID dose calculations 8a. Select an appropriate and valid accident every 15 minutes or whenever plant menu.

conditions indicate a significant event with the potential for a release has (1) Use measured vent data in the occurred. Forward calculation MIDAS model whenever possible.

(2) Initiate Back Calculations if field data is available. Test the validity of field data using the Default Accident or NUREG 1228 MIDAS Study Case models.

~TAB A EP-PS-245-A Revision 2 Page 7 of 7 SPECIFIC TASKS: HOW:

CAUTION: NOTE:

Only VALID calculations are to be Study Case Calculations are used for EAL Classification, Initial hypothetical calculations that are PAR Determination or a PAR based on assumed, unverified Upgrade. plant conditions and leakage rates and meteorology that existed at A VALID calculation is defined as the time of the calculation.

one that is based on:

(3) In the absence of valid measured

1) Current meteorology and radiological data, perform a Valid expected release duration and MIDAS Default Accident or

2) Valid vent data, Chemistry NUREG 1228 Calculation. Use vent sample, HP air sample results for EAL Classification and results or approved PAR determinations only when:

1-1311Particulate default ratios (a) Plant conditions indicate a or release is in progress.

3) Valid in the field radiological (b) Valid vent or field data is measurements or not available or will not be

4) In the absence of valid available within the measured radiological data, a allowed 15 minute MIDAS Default or NUREG-1228 assessment interval.

calculation based on inputs (c) The calculation represents that are judged by Engineering current meteorology and to be consistent with the expected release duration.

current conditions in the affected unit. (d) Input parameters are based on current plant conditions that have been validated as appropriate by Engineering NOTE:

The Default model is the appropriate and preferred model for a filtered release that does not exceed design basis leak rates.

Tab B EP-PS-245-B Revision 1 Page 1 of 2 MAJOR TASK:

Recommend changes in the emergency classification to the Recovery Manager, when required.

SPECIFIC TASKS: HOW:

1. Evaluate all radiological information. la. Obtain and evaluate the following:

(1) Monitoring Team and RMS results (2) PICSY vent release data (3) dose projection results (4) "study case" calculations

2. Help classify emergency according to 2a. If there is a release in progress, radiological data. determine the appropriate Emergency Classification.

2b. If there is potential for a release, utilize the study case results criteria given in the Emergency Classification matrix.

HELP EMERGENCY CLASSIFICATION See TAB 2

3. Recommend changes in classification. 3a. Keep presentation clear, concise, and in perspective. Address the following, where applicable:

(1) Impact(s) on classification and protective action recommendations.

(a) Specify the EAL which has been exceeded.

(2) Release:

(a) yes or no

Tab B EP-PS-245-B Revision 1 Page 2 of 2 SPECIFIC TASKS: HOW:

(b) monitored or unmonitored (3) Dose rates (at EPB and/or two miles)

(a) Use few significant figures (b) Use "REM" vs. mrem as dose units for General Emergency declaration and PAR discussions.

(4) Type of calculation and/or field monitoring used to estimate dose.

(a) Present key assumptions or limitations, when relevant.

(5) Impact(s) on classification and I

protective action recommendations.

- TAB C EP-PS-245-C Revision 3 Page 1 of 3 MAJOR TASK:

Recommend public protective actions to Recovery Manager.

SPECIFIC TASKS: HOW:

1. Obtain the pertinent data needed to la. Consider the following information as a assess the magnitude and anticipated minimum:

duration of offsite releases.

(1) Release rates/trends.

NOTE: (2) Prognosis for release/continued The Dose Assessment Staffer is release.

responsible to provide hard copy reports and assumptions to support PAR NOTE:

recommendation. SBGT Turnover Rate: I Volume/

day with SBGT in operations.

Turbine Building Turnover Rate:

2.5 Volumeslhr assuming ventilation system is operating.

After the leak is stopped, building concentration decays exponentially (exp(-Xt) where X is the turnover rate) and is reduced by a factor of 2.7 for every volume turnover.

(3) In-plant source terms and leakage pathway(s).

(4) Meteorological and/or river flow data.

(5) Dose calculations.

(6) Field data HELP Public Protective Action Recommendation Guide See TAB 3

- TAB C EP-PS-245-C Revision 3 Page 2 of 3 SPECIFIC TASKS: HOW:

2. Participate in the PAR 2a. Use the communication guidelines in decision-making process at the TAB B Item 3a.

Command and Control Table.

2b. Provide radiological input required to determine the appropriate protective actions.

2c. Complete or ensure the Radiological Liaison:

(1) Completes "Protective Action Recommendation" Form.

(2) Obtains appropriate approval(s) of the Form for any Protective Action.

(3) Communicates the approved PAR form to PA DEP/BRP.

HELP Protective Action Recommendation Form See TAB 5

3. When the Field Team Director 3a. Determine action required.

identifies the need for liquid release or agricultural protective actions, relay 3b. Complete or ensure Radiological Liaison:

recommendation to the Recovery Manager. (1) Completes "Protective Action Recommendation" Form.

(2) Obtains appropriate approval(s) of the Form for any Protective Action.

(3) Communicates the approved PAR form to PA DEP/BRP.

4. Continue to evaluate the current PAR and recommend revising the PAR to the Recovery Manager based on increasing dose levels.,

- TABC EP-PS-245-C Revision 3 Page 3 of 3 SPECIFIC TASKS: HOW:

HOW:

5. Assess if a protective action 5a. Perform dose projection estimates for recommendation beyond ten miles is distances greater than ten miles.

appropriate.

5b. Consult with Engineering Support Supervisor and/or Recovery Manager to verify that dose projections are consistent with plant conditions.

5c. Insure that PAR's have been made for distances up to ten miles. I 5d. Recommend a PAR rounding out the distance to the nearest five mile increment until dose projections are less than 1 REM TEDE and 5 REM thyroid CDE.

TAB D EP-PS-245-D Revision 3 Page 1 of 2 MAJOR TASK:

Manage assessing and communicating radiological information from the EOF.

SPECIFIC TASKS: HOW:

1. Instruct Administrative Assistant to call out additional offsite monitoring teams, and/or Dose Assessment Staff if they are needed.

2. Communicate with or ensure the 2a. Approximately every thirty minutes, Radiation Liaison communicates with telephone DEP/BRP and relay PA DEPIBRP. information contained in the "Protective Action Recommendation" form.

2b. Advise DEP/BRP when projected thyroid dose is 25 rem or higher outside the EPB.

NOTE:

PA DEPIBRP representative may request that updates should be provided solely to their representative at the EOF upon their arrival. That practice is acceptable upon verification by telephone with PA DEPIBRP.

3. Maintain ongoing communication with 3a. Determine status-Df dose calculations the Dose Assessment Staffer and and field surveys.

Field Team Director regarding calculations and field readings. 3b. Provide needed direction to efforts.

NOTE:

Use of the headsets available to the DAST and DASU may facilitate communications when face-to-face discussions are difficult to arrange.

4. Notify Recovery Manager of 4a. Changes to note would include:

significant changes, especially those which would indicate an escalation in (1) Release rates or indications of an the classification or a change to the unmonitored release.

current PAR.

(2) Field Team readings.

(3) Projected doses or weather.

- TAB D EP-PS-245-D Revision 3 Page 2 of 2 SPECIFIC TASKS: HOW:

(4) The approaching of any related EALs and PAGs.

(5) Significant environmental sample analysis results.

5. Maintain ongoing communications with the Radiological Liaison and RPC.

6. Periodically update the Dose 6a. Include this information when updating:

Assessment Staffer and Field Team Director. (1) Plant status.

(2) What mitigative or protective actions are being considered.

(3) Any other information that might affect dose assessment.

TAB E EP-PS-245-E Revision 2 Page 1 of 2 MAJOR TASK:

Recommend protective actions for PPL emergency personnel to the Recovery Manager.

SPECIFIC TASKS: HOW:

1. Ensure that the dose received by field 1a. Make sure team exposures are tracked teams is appropriate for their mission. by the Field Team Director.

lb. Make sure teams are rotated, new teams called out, etc. to minimize exposure.

HELP Emergency Personnel Dose Assessment & Protective Action Recommendation Guide See EP-PS-247, TAB 5 1c. Make sure emergency exposure extensions are processed as needed.

Id. Obtain Recovery Manager approval of extensions if necessary.

2. Discuss thyroid exposure control for 2a. If iodine concentrations are greater than teams in the field with Dose 5 rem/shift Thyroid-CDE (1000 mrem/hr Assessment Staffer. or 1200 ncpm on frisker assuming - 50%

occupancy factor) ensure the Field Team Director has initiated Thyroid CDE tracking.

2b. Make sure teams are rotated, or new teams are called out, etc. to maintain thyroid exposure less than 25 rem.

2c. Perform bioassay as needed to determine actual internal exposure. I 2d. For doses potentially exceeding 25 rem, recommend to and obtain approval from the Recovery Manager for the team to use KI tablets.

TAB E EP-PS-245-E Revision 2 Page 2 of 2 SPECIFIC TASKS: HOW:

2e. Make sure teams are notified of recommendation to use KI and of any precautions regarding interactions with other drugs.

2f. Contact Consulting Radiological Physician as appropriate for input regarding the administration of subsequent doses of KI, potential drug interaction and cessation of KI intake.

TAB I EP-PS-245-1 Revision 1 Page 1 of 1 MAJOR TASK:

Make sure information and functions that are in progress during shift relief are turned over smoothly.

SPECIFIC TASKS: HOW:

1. Work with the Administrative Assistant to develop and maintain schedules.

2. Remain at your duty station with full 2a. If there are two Dose Assessment responsibility until properly relieved. Supervisors available for duty, refer to the Responsibilities document (TAB 6) for guidance.

HELP Responsibilities of Initial and Augmented EOF Radiological Assessment Staff After Turnover See TAB 6

3. Make sure all personnel going off duty 3a. Instruct personnel on what to relay. In relay pertinent information to their short, they should:

counterparts.

(1) Relay pertinent information/data.

(2) Discuss in detail only that information that is directly related to their function.

HELP Shift Turnover Checklist See TAB 5

4. Advise off-going staff about protective actions that should be taken when they leave the facility and about any bioassay requirements for each individual.

TAB 1 I TEST FOR IODINE VALIDITYI EP-PS-245-1 YESIdine Datad lMU=

I Initiate Chemistry Sample of Vent YES - and Determine NG/1-131 ratio YES YES SYES*

r I

Consider 1-131 Consider 1-131 DATA INVALID DATA VALID Unless Chemistry Data Unless Chemistry Data Indicates Otherwise Indicates Otherwise I EP-AD-0D0-087 Revision 3, Page 3 of 4 1

EOF DOSE ASSESSMENT FLOWCHART LjS TAB1 2

FACILITY STATUS Dose Assessment Supervisor

- Recovery Manager Info and Target Takeover Time Dose Assessment Staffer

- Phones/Fax Field Team Director

- RMS/Radio/Phones EOF Dose Calculator

. MIDAS/PICSY Rad Liaison

- Phones/DEP BRP "A" and "B"Field Teams

. Kits/Vehicles/Phones/Radios EVENT STATUS RPC to DASU TSC DC to DAST HP Radioman to FTD "A" and "B" Team Briefing Staff Briefing and Info Exchange I

TURNOVER RPC to DASU ALL Calculations OSCAR Control DEP/BRP Communications Event/Source Term Agreement Liquid/Airborne Release Previous Data Transferred Turnover Time Am ata YM ntSsP e t V en t D YAcIC Field Team and Fixed Monitor Data Plant Conditions PIn F ielSIer e dC

-YES l inBss No FilteredConsult FEngineering with CnDefuaul!wi L nAccident MIDAS Menu D ** ]*

RpYEtCaifcinadPRrgest Vald PerormBacsCacultiowLoCFnldieddngsce latesupions

~~~~~

ayadSuc Dics emClulation ees ah 3(whtDaDaa with Suport Suerviso Egineerng A tn t y ORWLUME rp FTDALCLACATE t

UNONTRE p ELAen pEn

~~~~~~~~Hl SeetPAg Co4) ndCnro al G ide AccPA n CalculationmrgExenio Ca lculteer0Mionuts<25 e h CETt. osde rnito rm ees 30 Minute nst > 25cRemoTh IOO mMenur hC CACULTIOta (E nforenvSamping)eaAstermnate FORWARnDpm Cosdrtastinfoees d Vertrige)ta CALCULATION WES CN o Blowout PA angel YEEr-(HhlCESmln)e I EPAD-O-087. Revision 3. Page I of 141

__ __ __ _ __ __ __ _ __ __ __ ___ __ __ _ __ __ __ _ __ __ __ _ __ __ __ _ __ __ __ _ __ __ __ _ EP-PS-245-1 NOTE1 NOTE 2 NOTE 3 NOTE 4 NOTE 5 VENT RELEASE RMS/FIELD DEFAULT ACCIDENT NUREG 1228 LIQUID RELEASE TRIGGERS TRIGGERS TRIGGERS TRIGGERS TRIGGERS AIRBORNE RELEASE AIRBORNE RELEASE

BLOWOUT PANEL RELEASE

UNFILTERED VENT RELEASE

LIQUID RELEASE

RELEASE RATE> DESIGN BASIS 1%/DAY

>8.51E5 pci/min NG >0.1 mrem/hr WB

References:

CORE UNCOVERED > 15 MINUTES S Liquid Effl._> TRM

>1.04E2 gci/min Iodine > 68.4 mrem/hr Thy CDE 0 MIDAS Operating Procedure,

SPENT FUEL POOL RELEASE

>7.72E2 gci/min Part. > 100 ncpm on 1 Cartridge EP-AD-O00-112 0 Blowout Panel Guidance/Data Sheet, EP-AD-O00-094

EAL 15.1 FOR60 min. EAL15.1

>1.70E6 jci/min NG Liquid Effl. > TRM

>2.08E2 fci/min Iodine

>1.54E3 pci/min Part.

EAL15.2forl5min.

EAL3.2

EAL15.2 SEVERE CLAD DEGRADATION

>1.70E8 jici/min NG >200 R/hr CHRM Liquid Effl. > 10 x TRM

>2.08E4 laci/min Iodine >300 gci/cc DE 1-131

>1.54E5 gci/min Part.

EAL 15.3

EAL 3.3 SEVERLY DEGRADED CORE Projected dose rates @EPB > 400 R/hr CHRM

>100 mrem/hr TEDE for 30min or > 1000 gci/cc DE 1-131

>500 mrem/hr THY CDE for 30min or

>15 rem/hr TEDE for 2min or

>75 rem/hr THY CDE for 2min Projected dose @EPB

>500 mrem TEDE within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

EAL15.4

EAL 3.4 CORE MELT Projected Dose @ EPB . >400R/hr CHRM

>1 Rem TEDE >1 000pci/cc DE Iodine-131

> 5 Rem THY CDE > 2000 R/hr CHRM EP-AD-000-087, Revision 3, Page 2 of 4

TAB I EP-PS-245-1 I QUESTIONABLE NOBLE GAS DATA I

i I QUESTIONABLE IODINE DATA I I QUESTIONABLE PARTICU LATE DATA I SPING PARTICULATE SPING NG SPING IODINE Value(s) White Value(s) White Value(s) White "7

V Consult with Engineering Consult with Engineering Consult with Engineering

Is condition normal and "* Is condition nonrial and Is condition normal and acceptable due to no acceptable due to no acceptable due to no flow through the vent? flow through the vent? flow through the vent?

"* Is the release through

Is the release through

'a an unaffected vent? an unaffected vent?

Note: U Data will turn white due to High Resolution Time

(-1 hr @ 2E4 uCi/min) a NG Iodine Tot Al Particulate NO YES NO Totals YES NO o% YES Valid?

N"NValid?

I r

Take Appropriate Action: Take Appropriate Action:

Take Appropriate Action:

Continue Using "* Use default value Continue Using "* Use default value

"*Restore Channel SPING DATA NG/I=1,000 SPING DATA NG/Part.=1 0,000

"* Obtain/Analyze Vent "* Use last valid NG/I "* Use last valid NG/Part.

Sample(s) if appropriate if appropriate

"* Initiate PAVSS "* Restore Channel "* Restore Channel

"* Obtain Air Sample(s) "*Obtain/Analyze "*Obtain/Analyze

"* Obtain Field Reading SPING or PAVSS SPING or PAVSS Vent Sample(s) Vent Sample(s)

"*Initiate PAVSS "* Initiate PAVSS

"* Obtain Air Sample(s) "*Obtain Air Sample(s)

"* Obtain Field Reading "*Obtain Field Reading a

I EP-AD-O00-087, Revision 3, Page 4 of 4 I i

TAB 6 EP-PS-245-6 RESPONSIBILITIES OF INITIAL AND AUGMENTED EOF RADIOLOGICAL ASSESSMENT STAFF AFTER TURNOVER

1. DOSE ASSESSMENT SUPERVISOR A. Initial

"* Primary manager of EOF radiological function

"* Primary representative of EOF radiological function at command and control table

"* Signature authority for EOF radiological function on PAR forms, dose extension forms, and potassium iodide administration forms.

B. Supplemental While not a "minimum staffing" position, a second qualified DASU may be able to significantly assist the staff perform functions such as the following*:

Assisting the DASU and the DAST-A by maintaining an overview of the dose assessment function and communicating insights to the DASU and the DAST-A (e.g. are ongoing actions consistent with those expected from using the dose assessment flowchart, are staffers fully communicating with one another, are the right questions being forwarded to the Engineering Support staffers, are forward looking actions being discussed) 0 Assisting the DAST-A in communicating with the Engineering Support and other staffs as necessary

"" Working with the Radiological Liaison (RL) to ensure that queries from agencies are being answered; working with the RL, in communicating PARs to the agencies.

The RL, may even wish to have the supplemental DASU do PAR communications to the state and other agencies.

o Assuming the duties of the DASU should the DASU need to. relinquish duties for a period of time (ensuring the appropriate turnover and communications occur)

NOTE: The first three actions are especially important if the DASU-A is needed at the command and control table for a significant portion of the time.

II. DOSE ASSESSMENT STAFFER A. Augmented

"* Continuous direction, coordination, and review of operations in the dose assessment area

"* Communications with Engineering Support to address radiological group needs and to provide relevant information to the engineering staff

"* Communication with DASU to ensure Supervisor has an accurate overview of off-site radiological conditions and ability to provide overall input to and direction for function

"* Secondary EOF dose calculator, reviewer of EOF dose calculations EP-AD-000-076, Revision 0, Page I of 2

TAB 6 EP-PS-245-6 B. Initial

- Primary EOF dose calculator, using MIDAS or other dose calculation tools Ill. FIELD TEAM DIRECTOR A. Augmented

"* Direction of field monitoring team efforts to determine radiation and/or radioactive material concentration levels around the site

"* Performance or direction for use of the Emergency Remote Monitoring System (ERMS) to assess radiation and/or radioactive material concentration levels around the site

"* Tracking and control of field monitoring team exposure

"* Communication of results of monitoring efforts to the DASU and the DAST-A B. Initial While not a "minimum staffing" position after the turnover to the FTD-A has occurred, the FTD-I may be able to significantly assist the FTD-A by staying on to perform functions such as the following*:

Taking a lead role in directing the monitoring of airborne releases from the station should there be "simultaneous" liquid and airborne releases to the environment (thereby, the FTD-A taking the lead on performing liquid release calculations and directing associated river monitoring related to the airborne release)

For the more likely situation of a single release (assumed to be airborne):

"* Assisting the FTD-A with communications and direction of field teams information from the ERMS to the FTD-A and the DAST-NDASU

"* Assisting the FTD-A in answering queries about the field monitoring team members

"* Assuming the duties of the FTD-A should the FTD-A need to relinquish duties for a period of time (ensuring appropriate turnover and communications occur)

The important item is mutual agreement on roles and responsibilities of the supplemental DASU and FTD-I, and the communication of those roles and responsibilities so that the entire EOF-radiological assessment staff is aware of them. In the absence of mutually defined and communicated roles and responsibilities, the roles of DASU and FTD are the responsibilities of the DASU-l and the FTD-A, respectively.

NOTE: Once state and/or federal monitoring teams arrive, and/or once a Federal Radiological Monitoring and Assessment Center has been established, roles are likely to change. Augmented staff personnel may report to the FRMAC. Initial staff may stay at the EOF or report to the FRMAC to assist with the PPL contribution at that facility.

EP-AD-000-076, Revision 0, Page 2 of 2

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