ML20213F878

Revised Emergency Plan Implementing Procedures,Including HP/0/B/1009/17, Post-Accident Containment Air Sampling Sys & HP/0/B/1009/18, Offsite Dose Projections

ML20213F878
Person / Time
Site:	Catawba
Issue date:	11/12/1986
From:	DUKE POWER CO.
To:
Shared Package
ML20213F864	List: ML20213F862 ML20213F878
References
PROC-861112, NUDOCS 8611170227
Download: ML20213F878 (41)

Text

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} HP/0/B/1009/17 DUKE POWER COMPANY CATAWBA NUCLEAR STATION POST-ACCIDENT CONTAINMENT AIR SAMPLING SYSTEM 1.0 PURPOSE To describe a method for obtaining a containment air sample after a nuclear reactor accident using the Nuclear Post-Accident Containment Air Sampling System (PACS).

2.0 REFERENCES

2.1 HP/0/B/1000/06, Emergency Equipment Functional Check and Inventory 2.2 HP/0/B/1009/06, Alternative Methods for Determining Dose Rate Within the Reactor Building 2.3 CP/0/B/8800/13, Chemistry Procedure for the Preparation of

• Thiosulfate Solution for Post Accident Gas Sampling 2.4 OP/1/A/6450/10, Containment Hydrogen Control Systems 2.5 OP/2/A/6450/10, Containment Hydrogen Control Systems 2.6 RP/0/B/5000/12, Coat ol of Assessment and Repair Teams 2.7 Duke Power Company Nuclear Station Post-Accident Containment Air Sampling System II Manual, File No.: CNM-1210.09-0218001 2.8 NuReg-0737 II.B.3 Post-Accident Sampling Capability 2.9 Post-Accident Containment Air Sampling System - Qualifications, j File No.: CN-134.10 l

l 3.0 LIMITS AND PRECAUTIONS 3.1 Exposure from the samples have the potential to be very high; therefore, appropriate surveillance and control of personnel shall i be provided by Health Physics when taking samples. Entry and exit ,

l route to sample panel and control panel area are to be determined l by Health Physics surveys.

L 3.2 The Recire Pump shall never be used at any pressure other than 0" of Hg.

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3*. 3 Moving the Selector switch (#9) from one mode to another stops all current system operations. Depressing the Activate pushbutton (#10) starts operation of the newly selected mode.

3.3.1 Numbers within parentheses (ex. #9) are locations on Enclosure 5.6 and on the control panel.

3.3.2 (SP) to the left of the enclosure step number requires a person to go to the sample panel.

3.4 The Radiation Monitor (#3) on the control panel should provide background levels of radiation prior to, during, and after sampling, and an indication of contamination within the system or panel for progressive samples.

3.5 If the needie of the Radiation Monitor (#3) exceeds the upper end of the meter scale while the lower scale (mR/hr) is being used, immediately turn the selector knob to the higher scale (R/hr).

3.6 If the Radiation Monitor (#3) reading cannot be reduced below 10 R/hr do not return to the sample panel, but contact the Reserve Personnel / Personnel Monitoring Leader (RPPM) immediately for further instructions.

3.7 If problems with the Radiation Monitor (#3) are evident (e.g. no indication of radiation on the meter), notify the RPPM and rely on

-~x Health Physics surveys to determine access to the sample panel.

'w- 3.8 If thiosulfate comes in contact with the skin during preparation, transferal or dilution, wash the affected area as soon as possible with soap and lukewarm water. Consult statica nurse for further instructions.

3.8.1 Do not use NA0H solution and/or sodium thiosulfate crystals (Na2 S2 03 -5H2 O) if the expiration dates on their labels have been exceeded.

1 3.8.2 Chemistry should prepare NA0H solution and sodium thiosulfate crystals (Na2 S2 03 -5H2 ) Per Reference 2.3.

3.9 Dispose of contaminated syringes, septums, rubber gloves, etc., in appropriate radioactive waste receptacles.

3.10 Individuals that have been trained on this procedure are the individuals qualified to use this procedure. Individuals shall be trained and tested every six (6) months and documented in Reference 2.6.

3.11 Due to the nature of this procedure, a Working Copy shall be used to ensure compliance.

4.0 PROCEDURE 4.1 Follow steps on the RPPM PACS Checklist (Enclosure 5.1).

, HP/0/B/1009/17

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Y 4.2 Follow steps on Post-Accident Containment Air Sampling Set-Up k' _,/ (Enclosure 5.2).

4.3 Follow steps on Taking Post-Accident Containment Air Samples (Enclosure 5.3) and complete Post-Accident Containment Air Sample Data Sheet (Enclosure 5.4) for each containment air sample request.

4.3.1 If applicable, determine containment dose rate per Reference 2.2.

4.4 Ensure the isotopic analysis of each containment air sample and its associated Enclosure 5.4 are submitted to the Station Health Physicist.

4.5 Follow steps on Post-Accident Containment Air Sampling Shut-Down (Enclosure 5.5).

4.6 File enclosures and associated calculations in the Health Physics Satellite Master File.

4.7 Connect an appropriate transfer container and drain the sump by turning the Key Lock switch (#48) to Sump Pump. Accompanying power light should illuminate.

4.8 Reinventory OSC kit after use per Reference 2.1.

5.0 ENCLOSURES 5.1 RPPM PACS Checklist 5.2 Post-Accident Containment Air Sampling Set-Up 5.3 Taking Post-Accident Containment Air Samples 5.4 Sample of Post-Accident Containment Air Sample Data Sheet 5.5 Post-Accident Containment Air Sampling Shut-Down 5.6 Post-Accident Containment Air Sampling Control Panel (PACP) Diagram 5.7 Post-Accident Containment Air Sampling Sample Panel (PASP) Diagram 5.8 Location of PACP and PASP l

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, Page 1 of 2 DUKE POWER COMPANY CATAWEA NUCLEAR STATION I HP/0/B/1009/17

'j ENCLOSURE 5.1

, \wd RPPM PACS CHECKLIST Date/ Time / Unit Check Action 5.1.1 After completion of Team Personnel Lists of Reference 2.3, select at least one qualified individual based on PACS training and MSA training (refer to Reference 2.6, Health Physics file 134.10-4 or the OSC Health Physics Notebook).

Select another individual to accompany the other. Consider:

- Age

- Accumulated exposure

- Sex

- Ability to carry 100 lbs. together

- Respiratory printout 5.1.2 Consider the following for the PACS:

I - MSA SCBA's

- Operable breathing air hookups

- Throat mikes 4

- Portable instruments (PIC-6A, Teletector)

- High range dosimetry

- Extremity dosimetry

- To and from route to PACS  !

EMF-2 Control Room readout EMF-1 Control Room readout

- Flashlight

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- Radios

- Control Points 5.1.3 Request assistance in acquiring needed equipment from the Technical Support Center (TSC).

5.1.4 Prepare Counting Room to receive sample. Consider:

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- RCZ setup

- Shielding

- Disposal of sample

- MCA setup

- Personnel

, - Dosimetry (high, extremity) 5.1.5 If necessary, complete dose extension forms. '

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5.1.6 Obtain a High Radiation Area key.

e 5.1.7 Have equipment prepared for conditions at PACS. Consider:

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- Taping wheels on porta pig j - Bagging loose items a

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, DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/17 ENCLOSURE 5.1 RPPM PACS CHECKLIST Check Action 5.1.8 Inform selected individuals of precautions, Safety and Health Physics concerns and then have them obtain the sample.

5.1.9 Remain in contact with the technicians throughout the sampling. They should report problems and data as they get them.

5.1.10 Complete Enclosure 5.4 and route to Counting Room before the analysis takes place.

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CATAWBA NUCLEAR STATION HP/0/B/1009/17 ENCLOSURE 5.2 POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP Date/ Time / Unit Check Action 5.2.1 Inform the Shift Supervisor that gas sampling will be performed and that one Hydrogen Analyzer will need to be inoperable during sampling. Request that Operations complete the Setup Section for Post-Accident Containment Air Sampling of procedure OP/1/A/6450/10 or OP/2/A/6450/10 1

(see Reference 2.4 or 2.5).

5.2.2 After notification that Operations has completed the PACS Setup Section, obtain the Post-Accident Containment Air Sampling Equipment located in the OSC Emergency Kit.

The equipment should be the following:

Quantity Item 1 - Post-Accident Control Panel (PACP) Key 2 - 500 ml Nalgene bottle labeled "2.42 x 10 _3M Na0H" 2 - vials of .3 gm Na2S0 2 3 - 5H 2O 2 - 500 ml graduated bottle labeled " Iodine Sample" O- 2 - 100 ml gas bomb 2 - 60 ml Nalgene bottle - labeled " Iodine Sample" 1 - Stop watch 5.2.3 Prepare thiosulfate solution by adding one vial of Na2 S 203 -5H2 O to one bottle of Na0H. Shake vigorously until all of the crystals are dissolved. Relabel as

" Thiosulfate".

5.2.4 Verify that the Selector switch (#9) is in the Off position.

5.2.5 Move the System Purge toggle switch (#20) to the Normal position.

l 5.2.6 Move the Gas Purge toggle switch (#16) to the center

position.

i 5.2.7 Move the Refill toggle switch (#24) to the Off (down) position.

5.2.8 Turn Key Lock switch (#48) to Power On. Accompanying power light should illuminate.

5.2.9 Turn the Radiation Monitor (#3) On by moving the toggle

l. 3 switch (located below the meter) to the Ug position.

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CATAWBA NUCLEAR STATION HP/0/B/1009/17 ENCLOSURE 5.2 POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP Check Action 5.2.10 Turn the Radiation Monitor (#3) selector to BATT and verify that the needle is in the " red test region" on the right end of the scale. If reading is below the test region, rely on Health Physics surveys to determine access to the sample panel.

5.2.11 Select the appropriate rate so that the needle is on the meter scale by first turning the selector knob to higher scale (R/hr) and, if necessary, to the lower scale (mR/hr).

(SP) 5.2.12 Open all four (4) service valves LI, VI, N2 and TS by turning handles one quarter turn counterclockwise. The DI, VI, and Na valves are located on the outside upper left side of the sample panel, and the TS valve is located on top of the sample panel.

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) HP/0/B/1009/17 ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Date/ Time / Unit Check Action (SP) 5.3.1 Pour thiosulfate solution into the thiosulfate tank, located on top of the sample panel. Leave the cap off of the thiosulfate tank after transferring the thiosulfate solution (Refer to Section 5.2.3 for preparing more solution).

(SP) 5.3.2 Attach an " Iodine Sample" bottle to the sample panel by inserting the plastic hose into the bottle located on the lower left side of the panel. Disconnect the quick connect connector on the lower side of the sample panel and replace with a gas bomb.

5.3.3 Turn Key Lock switch (#48) to On.

5.3.4 Turn Selector switch (#9) to System Purge.

( ,y) 5.3.5 Depress Activate pushbutton (#10).

5.3.6 Depress Evac pushbutton (#17) (Evac light should illuminate) and watch the vacuum gauge (#6) drop to

-25" of Hg.

5.3;7 When the vacuum gauge (#6) reaches -25" of Hg, depress the Stop pushbutton (#19).

5.3.8 Press down the Gas Purge toggle switch (#16) and watch the vacuum gauge (#6) swiftly rise to +5" of Hg.

5.3.9 When the vacuum gauge (#6) reaches +5" of Hg, return toggle switch (#16) to center position and depress the Stop pushbutton (#19).

5.3.10 Depress the Evac pushbutton (#17) and watch the vacuum gauge (#6) drop to 0" of Hg.

5.3.11 When vacuum gauge (#6) reaches 0" of Hg, depress the Stop pushbutton (#19).

5.3.12 Depress Pump pushbutton (#18) and wait for thirty (30) seconds.

5.3.13 Depress Stop pushbutton (#19).

(N 5.3.14 Press up the Gas Purge , toggle switch (#16) and wait three (3) minutes.

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. DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/17

[L' j ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Check Action 5.3.15 Return the toggle switch (#16) to the center position.

5.3.16 Turn Selector switch (#9) to Solution Changeout.

5.3.17 Record the Radiation Monitor (#3) reading as a background reference: R/hr 5.3.18 Depress Activate pushbutton (#10).

5.3.19 Depress Flush pushbutton (#22) and hold five (5) seconds.

5.3.20 Depress Purge pushbutton (#23) and hold ten (10) seconds.

5.3.21 Depress Empty pushbutton (#21) and hold for thirty (30) seconds.

5.3.22 Move the Refill toggle switch (#24) to ON (up) position and wait two (2) minutes and then move the toggle switch back to the Off (down) position.

(N 5.3.23 Turn Selector switch (#9) to Dilution Volume Evacuation.

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5.3.24 Depress the Activate pushbutton (#10) and watch the vacuum gauge (#6) drop to -25" of Hg.

5.3.25 When the vacuum gauge (#6) reaches -25" of Hg, turn Selector switch (#9) to Sample Recire.

5.3.26 Depress Activate pushbutton (#10) and wait for five (5) minutes.

5.3.27 Record sample line temperature reading (#4): *C 5.3.28 Record sample inlet line pressure (psig) reading (#5):

Psig 5.3.29 Depress Sample pushbutton (#11) and wait for ten (10) seconds.

5.3.30 Depress Trap pushbutton (#12) and wait for thirty (30) seconds.

5.3.31 Enter time of sample trap: (ex. 1355) 5.3.32 Turn Selector switch (#9) to Sample Lilution.

5.3.33 Depress Activate pushbutton (#10).

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! 5.3.34 Depress Slow pushbutton (#13) and watch'the vacuum gauge (#6) rise to 0" of Hg.

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.- DUKE POWER COMPANY CATAWBA NUCLEAR STATION

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(' ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES

, Check Action 5.3.35 When the vacuum gauge (#6) reaches 0" of Hg, depress the Stop pushbutton (#14).

5.3.36 Depress the Recirc pushbutton (#15) and wait for five (5) minutes.

(SP) 5.3.37 Disconnect the quick connect on the gas bomb outlet side, wait five (5) seconds and disconnect the gas bomb.

Replace the quick connect connector.

5.3.38 Depress the Stop pushbutton (#14).

5.3.39 Turn Selector switch (#9) to Solution Changeout.

5.3.40 Depress Activate pushbutton (#10).

i 5.3.41 Depress the TS Sample pushbutton (#25).

5.3.42 Depress and hold the Empty pushbutton (#21) for five (5) minutes. Thiosulfate should transfer into the TS sample bottle.

5.3.43 Depress Purge pushbutton (#23) and hold thirty (30) seconds.

5.3.44 Depress TS Sample Grab pushbutton (#26).

5.3.45 Turn Selector switch (#9) to System Purge.

5.3.46 Depress Activate pushbutton (#10).

5.3.47 Repeat steps 5.3.6 through 5.3.15 as needed until no noticeable decrease is observed on the Radiation Monitor

(#3) from one purge to the next. Check blank in steps 5.3.6 through 5.3.15 each time the step is performed.

5.3.48 Record the Radiation Monitor (#3) reading: R/Hr 5.3.49 Turn Key Lock switch (#48) to Off.

(SP) 5.3.50 Disconnect and tightly cap the " Iodine Sample" bottle.

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• DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/17 9 ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Check Action 4

5.3.51 Determine the Thiosulfate Sample Volume (TSV) and record this value as TSV: ml 5.3.52 Using standard chemistry laboratory techniques and under a sample hood, transfer 50 ml of the " Iodine Sample" into the 60 ml Nalgene bottle. Contact Radwaste Chemistry for instructions on disposal of excess sample.

5.3.53 Place the 60 ml " Iodine Sample" bottle and the gas bomb 1, into a shielded container.

5.3.54 Transfer the " Iodine Sample" and gas bomb to the Health Physics Counting Room for isotopic analysis.

5.3.55 Using a monitoring instrument (such as the R02A or PIC-6A) take a contact dose rate reading on the top of the gas bomb and on the side of the " Iodine Sample" bottle:

R/hr gas bomb, R/hr " Iodine Sample" i

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/ ENCLOSURE 5.4 SAMPLE OF POST-ACCIDENT CONTAINMENT AIR SAMPLE DATA SHEET Date/ Time: / Unit Prepared By: Emergency - Drill (Circle One)

First Radiation Monitor Reading from 5.3.17 R/hr Sample Line Temperature from 5.3.27 'C Sample Inlet Line Pressure from 5.3.28 psig Sample Trap Time from 5.3.31 Second Radiation Monitor Reading from 5.3.48 R/hr Contact reading on gas. bomb from 5.3.55 R/hr (Top)

Contact reading on " Iodine Sample" bottle from 5.3.55 R/hr (Side)

Containment Sample Volume --

293 K (14.7 psig + psig)

CSV = 1.4 ml X (273 C + 'C)*K 14.7 psig

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= ml at standard temperature and pressure Section volume of CSV trapped in " Iodine Sample" bottle --

SV 50 ml X 1.0101 = ml I= ml (CSV) X ml (TSV) where: 50 ml sample size + Thiosulfate Sample Volume fro'm 5.3.51 1.0101 = 1 + .99, thiosulfate is 99% efficient for removing iodine 7

Section volume of CSV trapped in gas bomb --

SVg = ml (CSV) X .009 = ml where: .009 = 100 ml gas bomb + 11194 ml volume of dilution Station Health Physicist Date

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, DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/17

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ENCLOSURE 5.5 POST-ACCIDENT CONTAINMENT AIR SAMPLING SHUTDOWN Date/ Time / Unit Check Action 5.5.1 Turn Selector switch (#9) to Off.

5.5.2 Turn Radiation Monitor (#3) Off.

(SP) 5.5.3 Replace the top to the TS tank.

(SP) 5.5.4 Close all four (4) service valves DI, VI, N2 and TS by 1

turning handles one-quarter turn clockwise.

5.5.5 Request that Operations complete the Shutdown Section for Post-Accident Containment Air Sampling of procedure OP/1/A/6450/10 or OP/2/A/6450/10 (see Reference 2.4 or 2.5).

5.5.6 Notify Shift Supervisor of sampling completion and that the H2 Analyzer used during sampling is not required for sampling.

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DUKE POWER COMPANY CATAWBA NUCLEAR STATION s HP/0/B/1009/17 ENCLOSURE 5.6 POST-ACCIDENT CONTAINMENT AIR SAMPLING CONTR01. PANEL (PACP) DIAGRAM

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Page 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION

', HP/0/B/1009/17 ENCLOSURE 5.8 LOCATION OF PACP AND.PASP Rx.#1

~. J -

=a

- = i .

_ t_ _ x

- O 238 . \ nit U 1 PASP N Unit 1 PACP 1 200 O ' Unit 2 PACP y

oy _

r- -

t _

l g a n Rx.#2

, O -

Form 34731 (3-84) (1) 10 No. HP/0/B/1009/18 OUKE POWER COMPANY Change (s) O to PROCEDURE PROCESS RECORD 0 Incorporated

[,]/

y PREPARATION .

(2) STATION CATAWBA (3) PROCEDURE TITLE OFFSITE DOSE PROJECTIONS (4) PREPARED BY -

a> DATE /d[1//N (5) REVIEWED BY 2 s DATE / / 5 Cross-Disciplinary Review B N/R (6) TEMPORARY APPROVAL (If Needssary) u By (SRO) Date ,

By ^ -

Date (7) APPROVED BY W* ,

DATE ',' ,

(8) MISCELLANEOUS Reviewed / Approved By Date sq Reviewed / Approved By Date COMPLETION (9) DATE(S) PERFORMED (10) PROCEDURE COMPLEfTION VERIFICATION O Yes O N/A Check lists and/or blanks property initialed, signed, dated or filled in N/A or N/R, as appropriate?

O Yes O N/A Listed enclosures attached?

O Yes O N/A Data sheets attached, completed, dated and signed? ,

O Yes O N/A Charts, graohs, etc. attached and properly dated, identified and marked?

O Yes O N/A Acceptance criteria rnet?

VERIFIED BY DATE (11) PROCEDURE COMPLETION APPROVED DATE (12) REMARKS O

O

O HP/0/B/1009/18 DUKE POWER COMPANY CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTIONS 1.0 Puroose To describe a method for projecting dose commitment from a noble gas and/or iodine r elease, through the containment, the unit vent and/or the steam relief valves, during an emergency.

2.0 References 2.1 HP/0/B/1000/10, Determination of Radiation Monitor Setpoints 2.2 HP/0/B/1009/06, Alternative Method For Determining D:se Rate Within The Reactor Building 2.3 HP/0/B/1009/14, Health Physics Actions Following an Uncontrolled Release of Liquid Radioactive Material 2.4 HP/1/B/1009/17 Unit 1 Post-Accident Containment Air Sampling

{)}

s System 2.5 HP/0/B/1009/21, Abnormal Unit Vent Sampling 2.6 CNS Technical Specification 3.6.1.2 2.7 Offsite Dose Calculation Manual (ODCM) 2.8 Regulatory Guide 1.4, " Assumptions Used For Evaluating The l

Potential Radiological Consequences of a Loss of Coolant Accident l For Pressurized Water Reactors" l 2.9 Regulatory Guide 1.109, " Calculations of Annual Doses to Man From l Routine Releases of Reactor Effluents For The Purpose of Evaluat-ing Compliance With 10 CFR Part 50, Appendix I" 2.10 NuReg-0396, EPA 520/1-78-016. " Planning Basis For The Development

- of State and Local Government Radiological Emergency Response l

Plans In Support of Light Water Nuclear Power Plants" 2.11 NuReg-0654, FEMA-REP-1,Rev.1, " Criteria For Preparation And l

Evaluation of Radiological Emergency Response Plans And l Preparedness in Support of Nuclear Power Plants" 2.12 Letter from F.G. Hudson, September 30, 1985, re: Release Rate

[^'N Information for McGuire and Catawba Nuclear Station (File:

(s ,/ CN-134.10) l 2.13 Catawba Nuclear Station Class A Computer Model Validation (File:

NUC-O306)

I l

HP/0/B/1009/18

[s_'/} Page 2 3.0 Limits and Precautions 3.1 This procedure is an alternative method of dose assessment to the Catawba Class A Atmospheric Dispersion Model computer code.

3.2 This procedure applies to releases made from Catawba Nuclear Station only. Many of the values contained in this procedure are site specific.

3.3 It is assumed that the whole body dose from an iodine release is very small compared to the thyroid dosei therefore, iodine whole body dose is not considered here.

3.4 This procedure considers all releases to be ground level releas-es and that meteorological data are 15 minute. averages.

3.5 Once a zone has been added to the list of affected zones, it shall not be removed except under the direction of'the Dose Assessment Coordinator.

3.6 Once the Crisis Management Center (CMC) has been activated, the doses calculated by the Technical Support Center (TSC) dose

/ assessment group, should be compared with those calculated by the

(_}/ CMC before an evacuation recommendation is made.

4.0 Procedure 4.1 Meteorology Assessment 4.1.1 Acquire the following information and record on the Dose Assessment and Meteorology Worksheets (Enclosures 5.1 and 5.2, respectively):

4.1.1.1 Lower tower wind speed (WS) in miles per hour.

4.1.1.1.1 Use upper tower wind speed .i f lower tower wind speed is not available.

4.1.1.2 Upper tower wind direction in degrees from North (North =0 ).

4.1.1.2.1 Use lower tower wind direction if upper tower wind direction is not available.

4.1.1.2.2 If the wind speed or wind direction can not be obtained from plant sys-tems, obtain them from the National Weather Service (phone 704-399-6000).

[N s.

If the NWS information is unavailable, then obtain data from McGuire Nuclear Station Control Room (73 or 78, then 875, then ext 4262, or 4263, or 4264).

HP/0/B/1009/18 O. Page 3  ;

4.1.1.3 Temperature gradient (L1T) in degrees centigrade.

4.1.1.4 Using Enclosure 5.3, record the stability class based on L1T.

4.1.1.4.1 If the temperature gradient is unknown, the following applies:

If between 1000 - 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, use stability class Di If between 1600 - 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, use stability class G.

4.1.1.5 If hecessary, use forecasted meteorological data for calculating doses due to changing meteorolog-ical conditions.

4.1.2 Determjne the atmospheric dispersion paramters, X/Q (sec/m ), for .5, 2, 5 and 10 miles (record on Enclosure 5.1):

('"3 4.1.2.1 Using 41T, determine the two hour relative

(_,) concentration value(CH) from Enclosure 5.3.

4.1.2.2 Convert the CH * "**

X/Q = H' WS 4.1.3 Using Enclosure 5.4, circle on Enclosur e 5.1 the protective. action zones (PAZ), based upon wind speed and wind direction.

4.1.4 Recheck meteorology conditions approximately every 15 minutes to ensure that other sectors have not been affected.

i i 4.2 Source Term Assessment - Steam Relief Valve (Enclosure 5.5) 4.2.1 Determine the Sub-Noble Gas Release Rates, SQ sec),

NG by the following method:

4.2.1.1 For Unit 1-EMF 26, EMF 27, EMF 28 and EMF 29 or for Unit 2-EMF 10. EMF 11, EMF 12. EMF 13:

50 = R/hr X 1 X LBM X CF Ci VOPEN lbm R/hr

\ where:

j R/hr = EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10.

EMF 11, EMF 12, EMF 13 reading VOPEN = time the valve is open in seconds LBM = lbm released for the time the

HP/0/B/1009/18 Page 4 valve was open CF = the correction factor per Enclo-sure 5.6.

4.2.2 Determine the Noble Gas Release Rate, O IC' NG G 6) + SONG ' *

• NG NG " SONG NG

(" '

4.2.3 Determine the Iodine release rate, Q g(C1/sec):

O g =0  % Irat 99 where:

Irat = ratio of 1131eqv./Xe133eqv. from Enclosure 5.7.

4.2.4 Record O " "C "" * *

• NG "" I 4.3 Source Term Assessment - Containment (Enclosure 5.8) 4.3.1 Determine the Noble Gas Release Rate, QNG(Ci/sec) based on one of the following methods;

'g 4.3.1.1 Based on an EMF reading, wherei Q *

• NG "

wherei EMF = 39(L), if EMF 39(L) < 1E7 cpm, EMF = 39(H), if EMF 39(L) is offscale and

. EMF 39(H) > 100 cpm, EMF = 53A or 53B, if EMF 39(H) is offscale, CF = the correction factor per Enclosure 5.9.

LR = Leak Rate,(ml/hr),

by one of the following methods:

based on containment pressure:

LR = RLR (from Enclosure 5.10) based on an opening in containment:

LR = OIC (from Enclosure 5.11) based on design leak rate:

LR = 2.449E6 (Reference 2.13) b is ,) 4.3.1.2 Based on PACS sample, wherei Q *

• NG "

where;

e"S HP/0/B/1009/18 Page 5 PACS = uCi/ml (Reference 2.4)

CF = 2.78E-10 Ci hr sec uCi LR = Leak rate, as determined in step 4.3.1.1 above

4.3.2 Determine the Iodine Release Rate, Qg(Ci/sec) based on one of the following methods; 4.3.2.1 Based on Q I NG Og = Q #*

NG where:

O NG

= Noble Gas Release Rate as determined in step 4.3.1 above Irat = ratio of 1131eqv./Xe133eqv. from Enclosure 5.7.

4.3.2.2 Based on EMF 40; Og = /\ CPM x, 9.82E-20 Ci he min x LR 41 min sec ml cpm where:

. LiCPM = reading from EMF 40 l

Limin = the time interval for EMF 40 ob-i servation(normally 15 mjnutes) l 9.82E-20 = 4.OE-5 uCi/ cpm x .25 min /ft i

(inverseftog/mEMF 3.53E-5 l xflow rate) x 1Ci/IE6uci x

( 1hr/3600sec.

l 4.OE-5 = correlation factor for ENF40 from Reference 2.1.

LR = Leak rate, as determined in step 4.3.1.1 above 4.3.2.3 Based on PACS sample; Og = PACS x CF x LR g

where; PACS =.(uCi/ml) (Reference 2.4)

CF = 2.78E-10 Ci hr l sec uCi l

?

HP/0/B/1009/18  !

Page 6 .

~

LR = Leak rate as determined in step 4.3.1.1 above 4.3.3 Record O NG "" " "' '" * *

• I 4.4 Source Term Assessment - Unit Vent (Enclosure 5.12) 4.4.1 Determine the Noble Gas Release Rate, QNG(Ci/Sec) based on one of the follwing methods; ,

4.4.1.1 Based on as EMF reading, where; d

, O gg = EMF x CF x CFM where; EMF = 36(L) if EMF 36(L) < 1E7 cpm, EMF = 36(H) if EMF 36(L) is offscale and EMF 36(H) > 100 cpm, E

EMF = 54 if EMF 36(H) is offscale, CF = the correction factor per Enclosure 5.13 k CFM = unit vent flow rate (ft / min)

?

4.4.1.2 Based on unit vent sample, wherei [

Q = Unit Vent Sample x CF x CFM -

NG _

wherei

• Unit Vent Sample = (uCi/ml) per reference 2.5 CF = 4.72E-4 Ci min _mi set ft" uCi CFM = unit vent flow rate (ft / min) r 4.4.2 Determine the Iodine Release Rate, 0 7(Ci/sec), based on one of the following methods; .

4.4.2.1 Based on Q NG I T

I NG l

i where; s

O = Noble Gas Release Rate as determined in NG step 4.4.1 above -

Irat = ratio of 1131eqv./Xe133eav. from Enclosure 5.7.

4.4.2.2 Based on EMF 37; --

9

-s .

[k HP/0/B/1009/18 N, / , Page 7

, /SCBM_ ' X 1.11E-13 Ci min min x CFM =0 V .

r. .\

Limin sec ft" cpm V where:

3 /\ CPM = reading from EMF 37 Limin = the time interval for EMF 37 ob-pervation(normally 15 minutes)3 4 1.11E-13 = **.OE-5 uCi/ cpm x 0.1667 min /ft (inverse of EMF flow rate) x ICi/1E6aCi x 1 min /60sec.

4.OE-5 = correlation factor for EMF 37 from 4

Reference 2.1.

CFM = unit vent flow rate (ft / min) 4.4.2.3 Based on unit vent sample:

. O g = Unit v'nt e sample x 4.72E-4 Ci min m1 x CFM sec ft" uCi 7

where:

, Unit vent sample = (uCi/ml) (Reference 2.5)

CFM = unit vent flow rate (ft / min) 4.4.3 " "U '"#'

Record QNG "" I 4.5 Dose Assessment (Ecciosure 5.1) 4.5.1 Determine the tocal Noble Gas and Iodine Release Rates l,.

1 (TO NG I' # ** #' ******

l 4.5.2 Determine the Projected Whole Body Dese Rate, DRwb (rem /hr), due to ' neble gases f or .5, 2, 5 and 10 miles:

3 t DRwb = 33.6 rem m x TO NG

• hr C1 where:

I '

33'.S is the ad'lt u whole body dose 5 ""*r5' "

factor from Reference 2.9 in rem m hr Ci l

. 4'.5.3 Determine the Projected Whole Body Dose, Dwb(rem),.due to noble.. gases for .5, 2, 5 and 10 miles:

'0wb = DRwb X 2 hr

/~' where:

( ,)g dese is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period s

4.5.4 D?termine the Projected Thyroid Dose Rate, DRct(rem /hr),

d'u e to iodine for .5, 2, 5 and 10 miles:

, . , - , , - - . . , . _ _ _ _ _ . , _ . , . - . , , - . _ r, . . _ . . , _ _ . _ _ . _ _ _ . _ _ _ . _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _

)

i

/ HP/O/B/1009/18

( Page 8 3

DRct = X/O x TQ g x 2.26E6 rem m hr Ci where:

2.26E6 is the child thyroid dose cogversion factor from Reference 2.13 in rem m hr Ci 4.5.5 Determine the Arojected Thyroid Dose, Det(ree), due to iodine for .5, 2, 5 and 10 miles:

1 6 Det = DRct X 2 hr where:

dose is integrated over 2' hour time period 4.6 Protective Action Recommendations (Enclosure 5:14):

4.6.1 Record the next sequential report number.

4.6.2 Circle the PA2s and the actions for the current and pre-vious protective action recommendations.

4.6.3 If the projected dose in a P 2 is < 1 rem whcle body or < 5 rem thyroid, then recommend no protective action (action A).

4.6.4 If the projected dose in a PA2 is 1 - 5 rem whole body or 5 - 25 rem thyroid, then recommend evacuate children and pregnant women and shelter others(action B and E).

4.6.5 If the projected dose in a PA2 is > 5 rem whcle body.

or > 25 rem thyroid, then recommend evacuate everyone (action C).

4.6.6 If the dose rate at the site boundary is >= 5.OE-4 rem /hr whole body 4 1 then recommend an Alert. \ 'a 4.6.7 If the dose rate at the site boundary is >= .05 rem /hr whole body or >= .25 rem /hr thyroid, thenirecommend a Site Area Emergency if readings last 30 minutes.

4.6.8 If the dcse rate at the site boundary is >= .5 rem /hr whole body or >= 2.5 rem /hr thyroid, then recommend a Site Area Emergency if readings last 2 minutes.

4.6.9 If the dose rate at the site boundary is >= 1 rem /hr whole

/~5 body or >= 5 rem /hr thyroid, then recommend a General

( ,)- Emergency.

l 4

\ HP/0/B/1009/18

. Page 9 5.0 Enclosures 5.1 Sample of Source Tern and Dose Assessment Works.heet 5.2 Sample of Meteoro1gy Worksheet 5.3 Two-hour Relative Concentration Factors (CH' -

5.4 Protective Action Zones Determination 5.5 Sample of Source Term Assessment - Steam Relief Valves 5.6 EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, EMF 11, EMF 12, EMF 13 Noble Gas N Correction Factor

' 5.7 1131eqv./Xe133eqv. Ratio g' 5.8 Sample of Source Term Assessment - Containment

, 5.9 Containment Noble Gas Correction Facter 3.10 Containment Leakage Rate versus Pressure 5.11 Containment Leakage Rate varsus Pressure and Size Opening 5.12 Sample of Source Term Assessment - Unit Vent

,, 5.13 Unit Vent Noble Gas Correction Factor 5.14 Samp le o f Recommended Protective Action Report ap i

)

1 3

4

_.v . ._m.

4

~

DUKE POWER COMPANY

~

. CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.1 Meteorology, Source Term and Dose Assessment Unit Repo r. t #

Reactor Trip / Projection based on data on /

(cate/ time) (date/t,ime)

Prepared By:

Meteorology Assessment Current Hypothetical Wind Speed mph Wind Direction degrees from North Temperature Gradient (L1T) C Stability Class A C D E F G Miles .5 1  ? 4 5 7 8 PAZ AO B1 El Al C1 D1 F1 B2 A2 C2 D2 E2 F2 F3 A3 Total Source Term Assessment Current Hypothetical Steam Relief Containment Unit Vent Total (Ci/sec)

Ehc1. 5.5 Encl. 5.8 Encl. 5.12 Ci/ set + Ci/sec + C'i/sec = = TO NG Ci/sec + Ci/sec + Ci/sec = = TQ I

O C Dose Assessment Ji = X/O WS

<---< Adult whole body <---< >---> Child thyroid >--->.

Ehr -- 2hr Dose = 2 x DRwb = 33.6 x TO N *#U x . 6E6 = DRct x 2 = Dose (rem) (rem /hr) (Ci/sech (sec/m3) (Cf/sec) (rem /hr) (rem)

Distance miles "2 x = 33.6 x TO NG *5 I

• -

• x 2=

2 x = 33.6 x TO NG TQ y x 2.26E6 = x 2

~

2 x = 33.6 x TO NG 4 TQ x 2.26E6 = x 2

7

2 x = 33.6 x TQ NG g TQ x 2.26E6 = x E

7 Field Data Adult whole body Child thyroid Location Dose Rate 2hr Dose Location Dose Rate 2hr Dose rem /hr rem rem /hr rem C

d .

Emergency b 3 Drill

r O

i DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/ LOO 9/18 Enclosure 5.2 Meteorology Unit . Report #

Reactor Trip / .

(date/ time)

Prepared By:

Wind speed _______ mph Wind direction _______

"N L1T _______

• C O Default data wind speed _______ mph 1000 to wind direction _______

• N 1600 hrs.

stability class ___D___

wind speed _______ mph 1600 to winJ direction _______

'N 1000 hrs, stability class ___G___

Note: If the wind speed or wind direction cannot be obtained from plant systems, obtain them from the National Weather Service (704) 399-6000. If I the NWS information is unavailable, then obtain data from the MNS Control km Room.

l O O O-HP/0/B/1009/18 .

nurE rouum couraur l Enclosure 5.3 Tue-hour Relative P--tration Factors (Cg )

Temperature Stability Distance (Miles)

.5 2 3 4 5 6 7 8 9 10 Credient (C) Clase 1 i

1) A T< .6 & 1.4E-5 1.2E-6 5.9E-7 4.1E-7 3.2E-7 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7

2) .6< & T < .5 C 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.1E-6 8.3E-7 7.85-7

3) .5< & T < .2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-3 9.2E-6 7.3E-6 6.0E-6 5.OE-6 4.3E-4

4) .2<a T<+.4 E 6.95-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 1.1E-5 9.7E-4

5) +.4< a T 4 +1.2 F 1.1E-3 5.3E-4 2 0E-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5

6) +1.2< & T C 1.85-3 1.1E-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 MPTE: If AT is umsve11able use: 1000-1600 hears Use Stability Class D 1600-1000 bears Use stability Class C I

l

• DUKE POWER COMPANY

\, CATAWBA NUCLEAR STATION HP/0/B/1009/10 Enclosure 5.4 Protective Action Zones Determination Determine the affected zones (based on wind direction) from the table below and record on Enclosure 5.1 NOTE: If wind speed is less than or equal to 5 mph, the affected zones for 0 - 5 miles shall be AO.A1,B1.C1,D1.E1 F1 Wind Direction PA2's (degrees from North) 0 - 5 miles 5 - 10 miles 0.1 - 22 AO.C1,D1, C2,D2 22.1 - 73 AO,C1,D1,El C2 D2,E2,F2 73.1 - 108 AO,C1,D1,E1,F1 D2,E2,F2,F3 108.1 - 120 AO,D1,E1,F1 D2,E2,F2,F3 120.1 -

159 AO,E1,F1 D2,E2,F2,F3,A2 159.1 - 207 AO,E1.F1,A1 E2,F2,F3,A2,92 207.1 - 247 AO,F1,A1,81 F2,F3,A2,B2 247.1 - 265 AO,A1,B1 F3,A2.82 A3,C2 265.1 - 298 AO , A1, B1,C1- A2,B2,A3,C2 298.1 - 338 AO,B1,C1 92,A3,C2,D2 338.1 - 360 AO,B1,C1.D1 B2,C2,D2 i

O

4 DUKE POWER COMPANY

' CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.5 Source Term Assessment - Steam Relief Valves Report n Reactor Trip / Projection based on data on /

(date/ time) (date/ time)

Calculations based on Mejted Core LOCA NOBLE GAS based on EMF 26 or EMF 10 SO gg lbm X Ci = qi R/hr X 1 X sec lbm R/hr sec

-- -- (Encl. 5.6)

+

based on EMF 27 or EMF 11 R/hr X 1 X lbm X Ci = gi sec lbm R/hr sec

- -- (Encl. 5.6)

+

based on EMF 28 or EMF 12 R/hr X 1 X lbm X Ci = gi sec

, O --

sec lbm R/hr (Encl. 5.6)

+

based on EMF 29 or EMF 13 R/hr X 1 X lbm X Ci = Qi sec lbm R/hr sec

-- - (Encl. 5.6)

Total from all Steam Relief Valves, O NG = sec IODINE l From all Steam Relief valves I

l l

l Q X 1131eqv./Xe133eqv. ratio = Ci/sec NG (Encl. 5.7)

Emergency b Drill Prepared by:

!O l

l I

O DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.6 EMF 26, EMF 27, EMF 28, EMF 29 or EMF 10, EMF 11. EMF 12, EMF 13 Noble Gas Correction Factor Time Since Trip (hrs) Correction Factor

. based on Melted Core 10 3.622 12 3.971 14 4.041 18 4.029 i

a 124 3.332 148 2.647

, 1100 2.438 1250 2.438 1500 2.438 ,

1720 2.438

• units in Ci ibm R/hr

" f*c' " P*r "'f*r'"c' 3*

• Enclosure 5.6 41 is th5 M

cX "r*h*** -

2.83E4 m_l g X ft lbm 1E6 ml

.41 = specific gravity of steam per Reference 2.13 I

1

(

i i

l 0

e O DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.7 1131eqv./Xe133eav. Ratio Time Since Trip (hrs) Ratio based on Ratio based on LOCA Melted Core

. (Column 1) (Column 2) 2.74E-3 2.24E-3 10 3.42E-3 9.66E-3 12

>4 3.82E-3 1.59E-2 4.34E-3 2.85E-2

[8 4.79E-3 7.52E-2 124 4.84E-3 1.11E-1 i 148 J

5.06E-3 1.33E-1

. 1100 1.80E-1 i

1250 6.55E-3 1.02E-2 2.90E-1 1500 4.33E-1 1720 1.44E-2

• Enclosure 5.7 is from Reference 2.13 i

Note: For unit vent releases in which Irat is utilized to determine 1-131 equiv. concentration, apply the appropriate correction from the table below:

s

' 1. LOCA, use column 1 (based on LOCA).

i

! 2. LOCA throuch charcoal filters, divide column 1 value by 100.

3. Core damace, use column 2 (based on Core Melt).

i

4. Core damace throuch charcoal filters, divide column 2 value by 100.

I 5. Tube ruoture, divide column 1 value by 1,000.

I 6. New fuel accident, divide column 2 value by 600.

7. Old fuel accident, divide column 2 value by 600.

[ 8. Gas decav tank, assume no radiciodine released, only noble gases are

! considered to be released from gas tank.

8 l

t i

l i

l I

O-/

DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.8 Source Term Assessment - Containment Report #

Reactor Trip / Projection based on data on /

. (date/ time) (date/ time)

Calculations cased on Melted Core LOCA Containment p essure osig LR = ml/hr LR based on Realistic Leak Rate (check one) g .. 2 4" 6" 8" 12" 18" 34" diameter opening (circle one) Personnel Hatch opening Equipment Hatch opening Design Leak Rate (2.449E6)

NOBLE GAS based on (check one)

EMF 39(L) EMF 39(H) EMF 53 b) if < 1E7 cpm if > 100 cpm if 39(H) is off scale

/~' EMF CF LR Q NG cpm ml/hr =

or X X Qi R/hr (Encl. 5.9) sec based on PACS sample uCi/ml X 2.78E-10 Ci hr X ml/hr =

Ci sec uCi sec IODINE based on I

NG gi X 1131eqv./Xe133eqv. = gi sec ratio (Encl. 5.6) sec based on EMF 40 LR

/\ cpm X 9.82E-20 Ci he min X ml/hr = [1

/\ min sec ml cpm sec based on PACS sample n

\ ,/ uCi/ml X 2.78E-10 Ci hr X ml/hr = Ci sec uCi see Emergency Drill Prepared by:

9

! O O O' HP/0/B/1009/18 DUKE POWER COMPANY

) Enclosure 5.9 4 Catauba Containment Noble Gas Correction Factor 1

EMF 39(H) EMF 53

! Time Since EMF 39(L) ,

Trip (hrs) based on based on based on l

LOCA Melted Core LOCA Melted Core LOCA Melted Core 6.394E-18 6.672E-17 5.56E-14 1.429E-13 3.781E-10 1.190E-9

) >0 5.894E-10 6.394E-18 4.448E-17 5.56E-14 1.003E-13 3.ll4E-10

[2 i

' >4 6.394E-18 3.058E-17 5.56E-14 1.232E-13 2.780E-10 4.726E-10 6.394E-18 2.I13E-17 5.56E-14 1.195E-13 2.446E-10 3.392E-10 18

>24 6.394E-18 1.ll2E-17 5.56E-14 7.339E-14 2.335E-10 1.890E-10 6.394E-18 1.056E-17 5.56E-14 6.060E-14 2.335E-10 1.668E-10 l 148 j >100 6.3:< 4E-18 1.390E-17 5.56E-14 5.699E-14 2.335E-10 1.612E-10 l >250 6.394E-18 1.446E-17 5.56E-14 5.588E-14 2.335E-10 1.557E-10

>500 6.394E-18 9.730E-18 5.56E-14 5.560E-14 2.335E-10 1.251E-10 6.394E-18 6.394E-18 5.56E-14 5.560E-14 2.335E-10 1.056E-10 j [720 units in Ci he units in Ci he units in Ci hr

! sec si cpm sec al cpm sec al R/hr i

3 l

l Enclosure 5.9 is the correlation factor per Reference 2.13 b600 sec X IE al

\

I s

6 i

DUKE POWER COMPANY CATAWBA NUCLEAR STATION KP/0/B/1009/18 Enclosure 5.10 f' Containment Leakage Rate Versus Pressure PSIG ml/hr 10 2.330E4 12 3.175E4

14 5.821E4 i 10 9.779E4 110 1.114E5 111 1.164E5 l 112 1.199E5 l 113 1.235ES t

114 1.260E5 115 1.285E5 3

• Enclosure 5.10 fsXthe realistic leakage rate (m /sec) pe- Reference 3600 sec/hr. X O.07 (0.07 per Reference 2.6).

2.12 X IE6 ml/m i

i t

J i

l t

I

- - . . _ . . - _ _ _ - _ _ . _ _ _ _ . - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ , _ _ _ . . _ _ - _ _ _ _ _ _ _ _ _ . , _ _ . _m.-_-, _ _ _ _ _ _ , . , _ _ _ _ , _ , - , , . _ , _ _ - .

e n

O DUKE POWEA COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.11 Containment Leakage Rate Versus Pressure and Size Opening For 1" opening -

PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.209E8 >5.0 3.900E8 >12.5 5.862E8

>2.50 2.889E8 >7.5 4.588E8 >15.0 6.287E8

>3.75 3.483E8 >10.0 5.268E8 For 2" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 8.496E8 >5.0 1.512E9 >12.5 2.243E9

>2.50 1.121E9 >7.5 1.784E9 >15.0 2.464E9

>3.75 1.342E9 >10.0 2.022E9 For 4" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 3.144E9 >5.0 5.692E9 >12.5 8.496E9

>2.50 4.248E9 >7.5 6.797E9 >15.0 9.176E9

>3.75 5.098E9 >10.0 7.731E9 For 6" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 7.137E9 >5.0 1.291E10 >12.5 1.937E10

>2.50 9.516E9 >7.5 1.529E10 >15.0 2.124E10

>3.75 1.138E10 >10.0 1.716E10 For 8" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 1.257E10 >5.0 2.243E10 >12.5 3.381E10

>2.50 1.648E10 >7.5 2.634E10 >15.0 3.568E10

>3.75 1.971E10 >10.0 3.042E10 For 12" opening PSIG ml/hr PSIG ml/hr PSIG. ml/hr

>1.25 2.719E10 >5.0 5.012E10 >12.5 7.476E10

>2.50 3.738E10 >7.5 5.947E10 >15.0 0.156E10

>3.75 4.452E10 >10.0 6.712E10 For 18" opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 5.522E10 >5.0 1.OO3E11 >12.5 1.529E11 3

>2.50 7.476E10 >7.5 1.189E11~ >15.0 1.665E11 1 >3.75 0.836E10 >10.0 1.351E11 For 34" opening l

[

PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 1.869E11 >5.0 3.398E11 >12.5 5.132E11

>2.50 2.583E11 >7.5 4.078E11 >15.0 5.607E11

>3.75 3.093E11 >10.0 4.588E11

!' For Personnel Hatch opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.379E12 >5.0 4.690E12 >12.5 6.967E12

>2.50 3.398E12 >7.5 5.573E12 >15.0 7.646E12

>3.75 4.111E12 >10.0 6.372E12 For Equipment Hatch ope'ning PSIG PSIG PSIG O >1.25

>2.50 ml/hr 1.121E13 >5.0 1.478E13 >7.5 ml/hr 2.022E13 2.379E13

>12.5

>15.0 ml/hr 3.059E13 3.398E13

>3.75 1.767E13 >10.0 2.719E13

• Enclosure 5.11 is the containment leakage for an gpening size in

[

standard cubic feet per min (sefm) X 2.83E4 ml/ft X 60 min /hr.

I l

o

,. o -

(O

\'

) DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.12 Source Term Assessment - Unit Vent Report #

Reactor Trip / Projection based on data on /

(date/ time) (date/ time)

Calculations based 3 n Melted Core LOCA CFM = ft / min NOBLE GAS based on (ceck one)

EMF 36(L) EMF 36(H) EMF 54 b] if ( 1E7 cpm if > 100 cpm if 36(H) is offscale EMF CF CFM C NG cpm 3 or X X ft = qi R/hr (Encl. 5.13) min sec based on i Unit Vent Sample 3

O' uCi/ml X 4.72E-4 Ci min _ml X ft = Ci sec ft" uCi min see IODINE l based on O I NG Qi X 1131eov./Xe133eqv. = Ci sec ratio (Encl. 5.6) sec based on EMF 37 CFM Licpm X 1.11E-13 Ci min _ min X ft = G1 Limin sec ft" cpm min sec based on Unit Vent Sample 3

. uCi/ml X 4.72E-4 Ci min _ml X ft ,

C1 I see ft" uCi min sec j

U Emergency O Drill Prepared by:

1

l >

O O-HP/0/B/1009/18 DUKE POWER COMPANY l

i Enclosure 5.13 Catawba Unit Vent Noble Gas Correction Factor i

j Time Since EMF 36(L) EMF 36(H) EMF 54 l Trip (hrs) based on based on based on

}

LOCA Melted Core LOCA Melted Core IACA Melted Core

>0 1.086E-Il 1.133E-10 9.44E-8 2.426E-7 2.358E-4 1.887E-3

[2 1.086E-11 7.552E-11 9.44E-8 1.704E-7 2.358E-4 1.179E-3

>4 1.086E-Il 5.192E-11 9.44E-8 2.091E-7 2.358E-4 9.905E-4 1.086E-11 3.587E-Il 9.44E-8 2.030E-7 2.358E-4 6.367E-4

{8

{ >24 1.086E-11 1.888E-11 9.44E-8 1.246E-7 2.358E-4 2.931E-4

>48 1.086E-11 1.794E-11 9.44E-8 1.029E-7 2.358E-4 2.405E-4 ,.

1 9.44E-8 9.676E-8

>100 1.086E-11 2.360E-Il 2.358E-4 2.358E-4 '

>250 1.086E-11 2.454E-Il 9.44E-8 9.487E-8 2.358E-4 2.358E-4

>500 1.086E-Il 1.652E-11 9.44E-8 9.440E-8 2.358E-4 2.358E-4

! >720 1.086E-11 1.086E-11 9.44E-8 9.440E-8 2.358E-4 2.358E-4 l units in ci min units in ci min units in Ci min 3 3 3 I see ft cpm sec ft cpm sec ft R/hr Enclosure 5.13 is the correlation factor per Reference 2.13 X 2.83E4 al min m

) ft 60 sec IE6 al i

j l

O k ,) DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/18 Enclosure 5.14 Recommended Protective Action Report i

To: Emergency Coordinator Report # .,

The recommended protective actions for the public are:

Current Previous Miles PA2 Actions Actions

.5 AO A B C E A B C E 1 B1 El A B C E A B C E 2 Al C1 D1 F1 A B C E A B C E 4 B2 A B C E A B C E 5 A2 C2 D2 E2 F2 A B C E A B C E 7 F3 A B C E A B C E 8 A3 A B C E A B C E A - No protective action is recommended at this time.

B - Remain indoors with windows clcsed, turn off air conditioners and other ventilation, monitor EBS stations. Control access. (Action E also).

I C - Evacuate all affected zones, seek designated shelter.

'# E - Pregnant women and children evacuate and go to designated shelter.

• - based on field data.

Emergency Clasc. .ation based on Radioloalcal Data Recommend Alert Recommend Site Area Emergency if readings last 30 minutes Recommend Site Area Emergency if readings last 2 minutes Recommend General Emergency Comments:

/

Dose Assessment Coordinator Date/ Time Emergency

/

(m/ ) Drill

_ . - _ _ _ , . . _ - - , _ . . - . , - . - . . _ . , _ . . , - . , . . _ . _ .- , - . .