Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures PT/O/A/4600/06 Re Exercises & Drills & PT/O/A/4600/11 Re Function Check of Emergency Vehicle & Equipment
	ML20065A583
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/17/1983
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20065A538	List: ML20065A568; ML20065A583;
References
	PROC-830117-01, NUDOCS 8302220093
	Download: ML20065A583 (117)
	v • d • e

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Form 34731 (Fonwrty (10-81)

SPD 10021 } _ _

DUKE POWER COMPANY (1) ID No:Op/0/A/6200/48 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station -

(2) PROCEDURE TITLE: APERATING PROCEDURE FOR THE OPERATION OF THE POST ACCIDENT LI ID AMPLE S? STEM r\

(4) PREPARED BY: DATE: Il~ 1 b (5) REVIEWED BY: ,. Mk DATE: I ?,- 3o-92 Cross-Disciplinary view By: N/R: M' .

(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

/ By:_ -

Data:

(7) APPROVED BY: $% .) /Mk >J Data: / /J/h O'

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

8302220093 830214 PDM ADOCK 05000369 F PDR l

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OP/0/A/6200/48 gw DUKE PONER COMPANY McGUIRE NUCLEAR STATION OPERATING PROCEDURE FOR THF OPERATION OF THE POST ACCIDENT LIQUID SAMPLE SYSTEM 1.0 Purcose The Post Accident Liquid Samaling System (PALS) provides the capacity to promotly obtain a reactor coolant samole under a nuclear reactor accident condition-.

Sample acquisition during accident conditions (noncal sampling area being inaccessible) will help evaluate information related to:

1) The extent of core damage which has occurred or is occurring.

2) Types and quantities of fission products released to containment liquid and gas phases.

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3) Reactor Coolant chemistry and radiochemistry.

2.0 Limits 2.1 The PALS will be used to sample pMmary systems under the following conditions:

2.1.1 Posti accident sampling 2.1.2 Inaccessibility of the Primary Sampling Lab due to radiation levels.

2.1.3 Request from the Station Chemist or designee.

2.2 The undiluted sample volume is 1.25 ml. and the final dilution volume shall be controlled betweer 250-3500 ml.

2.3 Health Physics personnel must perform continuous radiation monitoring during sr&pling at the liquid sample or control panel on the 716'el and 750'el Auxillary Building respectively.

2.4 Samples will be collected in 1 ml. and 5 ml. lockable glass syringes to be found in the Hot Lab.

l 3.0 Initial Conditions 3.1 In order to maintain the PALS in an operable condition at all times, the following requirements on Enclosure 9.1, PALS ftonthly Checklist, must be done monthly and be current prior to sampling.

3.2 Verify with Operations that lKC "A" Train is in operation when ;

sampling is to be perfc.med and list on Enclosure 9.2. l s ,./

. 2-p 3.3 If the containment building has been isolated due to an SI or SIS signal, no' sample is to be obtained until the On-Site Support Center can uccide how to un-isolate one of the sample lines.

3.4 Verify with primary chemistry personnel' that no sangling is in progre'ss in the NM Lab.

4.0 Panel Preparation 4.1 Valve Alignment for Liquid Sampling 4.1.1 Contact Operations and request the following valves be opened to obtain the sample desired:

NC HOT LEG A NC Hot Leg #1 Sample Line Inside Cont. Isol INM22A NCHot Leg Sample Header Outside Cent. Isol INM26B NC HOT LEG D NC Hot leg #4 Sample Line Inside Cont. Isol INM25A ,

NC Hot Leg Sample Header Outside Cont. Isol INM26B ND PUMP OISCH 1A

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ND Pump 1A and HX Miniflow Step 1N068A NO PUMP DISCH 1B

ND Pump 18 and HX 1B Miniflow Stop 1N0678

Flow should be verified in this piping prior to samoling by verifying with operations that *.he respective A or B .

train is in service. Sign off Enclosure 9.2.

4.1.2 Notify Health Physics of samoling and ask for surveillance prior to going to the Control Panel. Sign off Enclosure 9.2.

4.1.3 Notify Radwaste Chemistry that panel will be operated.

4.1.4 Record specific Conductivity of buffer solution on Enclosure 9.2 from Primary Chemical Data Log and take a j step watch and panel keys (located in Cold Lab Key Box) to Control Panel.

4.2 Control Panel (750'el. Aux. Bldg. Cable Roem) 4.2.1 Turn the main selector knob (on centrol panel) to " Reset".

Place key in System Pcwer Switch and turn to the right.

Press " Reset" button.

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4.2.2 For ND Pump Discharge Sample, place' the " Remote / Local" switch on the PALS Control Panel in the " Local" position and press "Open" switch for INM39 or INM40 to ifne up for an ND "IA" or "18" Pump Discharge sample respectively.

This is to be done after Operations has opened IN068A or IN0678.

4.2.3 Place the toggle switch for the dilution water meter and the nitrogen dilui. ion meter on "0N".

4.2.4 Place the toggle switch for the radiation monitor to "0N" and turn the scale select to " rem /hr".

4.2.5 . Place the temperature probe selector (Tc) to position 1.

4.2.6 Place the conductivity meter to " Measure".

4.2.7 Push in the pH probe " standardize" knob.

4.2.8 Select the system to be sampled with the system selector -

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Reactor Coolant System (refers to NC Hot Leg), Reactor Building Nor. Sump (refers to ND Pump Discharge).

5.0 Panel Operation 5.1 Panel Prep (position 1) v 5.1.1 Turn.the selector knob to " Panel Prep", position 1.

5.1.2 Press the " Selection Power - Activate" button.

5.1.3 Press the " Panel Prep. - Purge" button and hold for 1 min.

and release.

5.1.4 Press the " Panel Prep. - Drain" button and hold for 30 sec. and release.

5.1.5 Press the " Panel Prep. - Calibration" button and hold until the conductivity and pH meters stabilize.

(Approximately 1 minute) 5.1.6 Pecord the specific conductivity reading on Enclosure 9.2, the measured specific conductivity should correspond with the specific conductivity of the pH standard which was

, prepared in the lab. If not, repeat section 5.1.3 and 5.1.5. Contact the Station Chemist or Primary Supervisor j if this measure does not work in the sent of an accident.

(If this is a routine test, replace the probe and then submit a work request as a final repair measure.

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NOTE: Multiply conductivity meter reading by 1000 to l

obtain proper specific conductivity value.

5.1.7 Adjust the pH meter to the known pH of the standard.

5.1.8 Press the " Panel Prep - Purge" button and hold for 30 s I seconds then release.

,- 5.1.9 Press the " Panel P. rep Flush" button and hold until the

conductivity and pH meters stabilize (specific t

l conductivity and pH of demineralized water) approximately 2-3 minutes, then release.

5.1.10 Press tne " Panel Prep . Purge" button for 30 seconds and release.

5.1.11 Press the " Panel Prep - Drain" button for 60 seconds and release.

5.1.12 Repeat Steps 5.1.9, 5.1.10, 5.1.11 and then continue to Section 5.2.

5.2 Sample Collection (Position 2) 5.2.1 Turn the selector knob to " Sample Recirculation", position l

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5.2.2 Set the temperature selector, located on the instrument panel, to Tc 1.

5.2.3 Record the radiation monitor reading on Enclosure 9.2 (Background).

5.2.4 Press the " Selection Power - Activate" button. Record the starting time on Enclosure 9.2. The radiation monitor ,

should show an increased activity level and Tc 1 should 1

show temperature increase as samole enters the liquid panel.

5.2.5- If Tcl goes above 190*F, sample is not being cooled sufficiently. Turn selector to " Reset". Press" Reset"

button and turn Power Key to vertical position. Call I Station Chemist or his designee.

) 5.2.6 Turn the selector knob to " sample", position 3, when the sample temperature at Tc l- stabilizes. Record the-

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i temperature on Enclosure 9.2. (Acoroximately 7-8 minutes)

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l NOTE: Tc 3 monitors KC Coolant outlet from the PALS HX

, and can be monitored during Tc 1 and Tc 2 l

! stabilization.

l 5.3 Sample (Position 3) 5.3.1 Turn the temperature selector to Tc 2.

5.3.2 Press the " Selection Power - Activate" button.

5.3.3 Monitor the temperature gauge and when Tc 2 stabilizes record the temperature and radiation readings on Enclosure 9.2. (Approximately 7-8 minutes) 5.3.4 Subtract initial background activity from sample activity found during Tc 2 stabilization and record reading on Enclosure 9.2. This is the radiation due to the sample.

5.3.5 Press the " Sample - 1 Tc 2 Stabilize" button. When pressure stabilizes record the reading on Enclosure 9.2.

5.3.5 Press the " Sample - 2 Pressure Stabilize" button. Record' -

the time sample flow stops on Enclosure 9.2. ,

5.3.7 Turn the selector knob to "Depressurization", position 4.

O 5.3.8 Request Operations to close the valves opened in section'

() 4.1. If an ND Pump Discharge sample is being taken, press "close" switch for t!ie ND Pump Discharge Isolation Valve, either lhD39 or IND40 and place the " Remote / Local" switch' in the " Remote" position. -

5.4 Depressurization (Position 4) 5.4.1 Press .the " Reset" button on the nitrogen ficw totalizer to zero the readout. Preset the counter on the totalizer to .....

99999.

5.4.2 Press the " Selection Power - Activate" button. Verify the

. level gauge on the instrument panel indicates a vacuum of

-25 inches of mercury (-P.5 level). Wait 60 seconds and insute 3000 psig pressure gauge indicates O psig pressure.

j 5.4.3 Press the " Start" button on the nitrogen flow totalizer and monitor the level gauge. Press the "Stoo" button on

} the totalizer when the Level gauge needle first begins to

, move (approximately 5 minutes). Press " Start" button and l "Stop" button to add small amounts of nitrogen and l i m. continue small adds until level meter reads 0-2 inches in

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! > level. If 5 inches is exceeded, a new stripped gas sample

! will need to be taken (ie) start from Section 4.1.

5.4.4 Turn the selector knob to " Liquid Sample", position 5.

5.5 Liquid Sample (Position 5)

~ 5.5.1 Press the " Selection Power - Activate" button.

5.5.2 Press the " Liquid Sample - 1) Conductivity" button and l hold until the conductivity meter stabilizes (approximately 5 seconds). Record the specific conductivity on Enclosure 9.2.

f 5.5.3 Press both the " Liquid Sample - 1) Conductivity" and Liquid Sample - 2) Log pH" bottons and hold until th'e pH meter stabilizes. If meter does not stabilize in 30

! seconds, release both buttons and take a reading. Record the pH on Enclosure 9.2.

l 5.5.4 Press the " Gas Sample - 1) Activate" button. Notefevel l gauge should decrease.

! 5.5.5 Press the " Gas Sample - 3) Diluted Gas Sample Grab"

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l 5.5.6 Turn the selector '< nob to " Liquid Sample Prep.", position l 6.

! 5.6 Liquid Sample Prep (Position 6) 5.6.1 Press the " Selection Power - Activate" button.

5.6.2 Press the " Liquid Sample Prep - B Activate to desired ml.

vo;ume" button and wait 5 seconds, after depressing. This deposits I.25 mi nf sample for dilution.

, 5.6.3 Press the " Reset" button on the dilution water flow totalizer and preset the meter for 250 mis of dilution water.

) Press the " Start" button and let dilution continue to completion. Record the dilution volume on Enclosure 9.2.

5.6.4 Press the " Liquid Sample Prep - 3) Activate Mix" button and hold for 10 seconds.

5.6.5 Turn the selector knob to " Liquid Sample", position 7.

5.7 Liquid Sample (Position 7)

. 5.7.1 Press the " Selection Power - Activate" button.

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( ~s 5.7.2 Press the "Liouid Sample - Activate" button. Wait 15 seconds.

5.7.3 Immediately after 15 seconds press the " Liquid Sample -

Diluted Sample Grab" button.

5.7.4 Turn the selector knob to " Flush", position 8.

5.8 Flush (Position 8) 5.8.1 Press the " Selection Power - Activate" button.

5.8.2 Press the " Flush - Activate" button and wait 4 - 5 minutes,1st flush cycle.

5.8.3 Press the " Flush - Activate" button and monitor pH and conductivity meters until they reach equilibrium of demineralized water, 2nd flush cycle. ( Aoprox. 10 minutes.)

5.8.4 Press the " Flush - Activate button and wait 3 minutes, 3rd flush cycle.

5.8.5 Press the " Flush - Activate" button. The "Comolete":

. light must illuminate. If light doesn't illuminate

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continue and write a work recuest after sampling is, completed.

5.8.6 Turn th'e selector knob to " Drain", positien 9.

5.9 Drain (Position 9) 5.9.1 Press the " Selection Pcwer - Activate" button.

5.9.2 Press the " Drain - Activate" button. Wait 120 seconds.

5.9.3 Press the " Drain - Activate" button. Wait 120 seconds.

l 5.9.4 Press the " Drain - Activate" button. Wait 13 minutes.

5.9.5 Press the " Drain - Activate" button and the " Complete" light should illuminate.

j 5.9.6 Turn the selector knob to " reset" and oress the " reset" button, 5.9.7 Turn the System Pcwer Key to th.e left to operate the sump '

pump: Allow pump to run for 15 minutes to insure sump is pumpet dry.

5.9.8 Turn the System Power Key to the right to re-erergize the PALS. Record the radiation level on Enclosure 9.2.

5.9.9 If the field at the panel is greater than 3 Rem /hr, continue to section 5.10, otherwise turn the System Pcwer

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{3 Key to the vertical off position and proceed to section 6.0.

5.10 Decontamination 5.10.1 Turn the selector knob to " Panel Prep", position 1.

5.10.2 Press the " Selection Power - Activate" button.

5.10.3 Press and hold the " Flush" button for 2 minutes.

5.10.4 Repeat Panel Flush and Drain modes starting Section 5.8 through 5.9.8.

5.10.5 If radiation level is less than 3 Rem / hour, turn the System Power Key to the vertical position and continue to Section 6.0. If however, the radiation level remains greater than 3 Rem / hour, go back to step 4.1 and repeat the sequence using a larger dilution volume. See Enclosure 9.3 to determine the dilution volume. If with a 3500 ml dilution volume the radiation level is still greater than 3. Rem / hour, contact the Station Chemist or his designee.

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6.0 Samoling

' 6.1 Verify the operability of 2-1 ml and 2-5 ml glass locking syringes located in the Hot Lab and label them.

6.2 Contact Health Physics Surveillance and Can. trol Group and request surveillance while taking gas and liquid samples from the sample portion of the PALS located on 716'el. Aux. Bldg. FF-54.

6.3 Collect 2 - 1.0 mi stripped gas samoles at the gas sample panel septum located on the north side of the sample panel and place syr.inges 'in plastic bag.

6.4 Collect 2 - 5 m1 liquid samples from the liquid sample septum located on the south side of the sample panel and place syringes in plastic bag.

6.5 Replace the septa after collecting the syringe samples prior to returning to the Hot Lab, time permitting.

6.6 Take syringes to Hot Lab in a samole carrier and place in operating fume hood behind a lead brick shield to await analysis.

7.0 Samole Analvsis l 7.1 One syringe of stripped gas will be analyzed via Chemistry procedure l CP/0/8/8100/31, Chemistry Procedure for the Analysis of Gases Fron the Reacto.- Coolant System Gas itixtures. fic averaging of gas

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9 samples will be done as in the procedure as only one syringe of sample will be pulled. Analyze the sample for ", H2 and 02 and report results as follows:

%H x 1000 cc x 1 = cc/kg H 2 2 (ie)%H2x 58.3 = cc/Kg H2 0.170 kg 100

, %02 x 1000 cc x 1 = cc/kg 02 (ie) %02 x 58.3 = cc/Kg 02 0.170 kg .100 Where: % gas is determined via CP/0/B/8100/31 1000 cc = stripped gas bomb volume j' O.170 kg = reactor coolant sample size 1/100 = conversion of percent to decimal Report cc/kg H2 and 0 2 n Enclosure 9.2. ,

7.2 Take the remaining 1 ml. syringe with stripped gas sample, withdraw I ml air from septum stoppered glass vial and load 1 mi stripped gas. Analyze by GeLi Spectral Analysis following CP/0/A/8200/05, Chemistry Procedure for Radioisotope Analysis.

'- Report the actual sample volume on the botton of the sample analysis form under remarks and submit to Health Physics so that they may

adjust isotope acitivities from diluted samples to reflect reactor coolant activity. The calculation is as follows

Sample Volume = 170 ml. = 0.17 ml.

1000 Where: 1000 cc = stripped gas bomb volume 170 cc = reactor coolant sample size

'i 7.3 Take 1 ml of liquid sample and dilute to 50 mis with Super Q Water in a 60 mi poly bottle. Analyze by GeLi Spectral Analysis following CP/0/A/8200/05. Report the actual sample volume being counted on the

- bottom of the sample analysis form under remarks and submit to Health Physics so that appropriate adjustment of isotope activities )

'f occurs. The calculation of sample volume is as follows:

Sample Volume = 1.25 ml i Total Oilution /olume Where: 1.25 ml. = Reactor Coolant Volume v

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Total Dilution Volume = mis water added in Part II #11 of Enclosure 9.2 + 1.25 mls.

Example: 250 ml. dilution water added i Sample Volume = 1.25 ml = 4.98 x 10-3 ,j, 251.25 ml

7.4 Take 2 ml. of liquid sample and analyze for Boron using i CP/0/8/8100/5E, Chemistry orocedure for the Determination of Baron in Water and Wastewater, Colormetric Method.

The value received must be corrected for dilution as follows:

ppm Baron in reactor coolant = ppm measured x Total Oilution Volume 1.25 ml.

4 Where: ppm Baron measured = value obtained via CP/0/B/8100/5E Total Oilution Volume = mis water added Part II all of I

Enclosure 9.2 + 1.25 ml.

1.25 ml. = reactor coolant sample

] 7.5 If dilution proves inadequate for any of the above analyses, contact

( Station Chemist or his designee. ~

i 7.6 Report all results in the Primary Chemistry Data Log and Enclosure 9.2.

i 7.7 A minimum of 3 mis of liquid will be needed for halide analysis (chloride). If insufficient sample remains after that needed for Baron and GeLi Spectral Analysis, the panel will be operated again j within 10 hrs. after initial sampling and 2-5 ml. syringes of liquid ,

i sample taken for halide analysis. One technicon cup of liquid j sample will be analyzed via CP/0/A/8100/06, Chemistry Procedure for

the Detemination of Chloride in liigh Purity Water. Results must be

) adjusted via the calcu.lation in Section 7.4, substituting ppb Cl-for ppm 8, so that dilution is taken into account. Record value in Primary Chemistry Data Log.

NOTE: Chloride sample to be taken only in an accident situation.

7.8 Clean 5 ml. syringes with Super Q Water after use.

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3.0 Referances 3.1 Duke Pcwer Company Nuclear Station Post Accident Liquid Sample i

Panel.

8.2 MC-1572 a.0 LL, Rev. 1 (V -

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[s 8.3 CP/0/8/8100/31, Chemistry Procedure for the Analysis of Gases from Reactor Coolant System Gas Mixtures.

8.4 CP/0/8/8100/05E, Chemistry Procedure for the Determination of Baron in Water and Wastewater.

8.5 CP/0/A/8200/05, Chemistry Procedure for Radioisotope Analysis.

8.6 CP/0/A/8100/06, Chemistry Procedure for the Determination of Chloride in High Purity Water.

9.0 Enclosures 9.1 PALS Monthly Checklist 9.2 PALS Data Sheet 9.3 Correction of Dilution Volume 9.4 PALS Control Panel Diagram 9.5 Directives for Personnel Conduct in the Hot Laboratory, the Atomic ,

Absorption Laboratory, Unit 1 & 2 Primary Sampling Laboratories, And .

the Radwaste Operating Center.

10.0 General Information 10.1 PALS Breaker - Breaker Box IKJ Breaker #34 located on 750' el. MM56

'. 10.2 Phone at Control Panel - Ext}

10.3 Phone at Sample Panel - Ext.I d

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OP/0/A/6200/48

. ENCLOSURE 9.1 (m .

PALS MONTHLY CHECKLIST

1. pH 7.0 buffer solution must be replaced once a month. Prepare pH 7.0 buffer (4 liters) as per CP/0/8/8100/43. Measure specific conductivity and log in ,

Primary Chemical Data Log.

buffer expiration date:

specific conductivity: umhos/cm Technician /Date: /

2. Verify that the 1000 pom Boren Standard Stock Solution used in CP/0/8/8100/05E, Chemistry Procedure for the Determination of Baron in Water and Wasterwater, will not exoire prior to next mont5y inspection. If so, replace as stated in the above procedure.

1000 ppm Saran std. expiration date:

Technician /Date: / , ,

Carminic Acid and 10 ppm Baron std are to be made prior to sampling.

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3. The following valves should remain open: Locatien Date x Instrument Air. Supply Isolation IVI231 716 el' FF-54 _

Nitrogen Supply Isolation -

IGN124 716 el' above NB Panel KC Supply Isolation to PALS HX 1KC329 733 elin front of "A" train pumps DI Water Supply Isolation 1NM376 716 el' FF-54 Panel DI Water @let Isolation LATER 716 el' south side of panel Panel Nitrogen Inlet Isolation LATER 716 el' south side of panel Panel Instrument Air Inlet Isol. LATER 716 el' south side of panel Panel Sample Return-Isolation 1NM411 716 el' inside panel Panel KC Inlet to HX Isolation 1KC957 716 el' FF-54 Panel KC Outlet from HX Isolation .LATER 716 el' inside panel KC Return to System 1KC873 733 el' by EMF 46 4 pH and conductivity meters must be checked when buffer solution is renewed. !

Complete PALS operating procedure sections 4.2.1, 4.2.6, 4.2.7, 5.1.1, 5.1.2, 5.1.3,~ 5.1.4, 5.1.5, 5.1.6 5.1.7, 5.1.8, 5.1.9, 5.1.10, and 5.1.11.

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i Turn System Power Key to vertical position to deenergize panel. I calibration date:

'achnician: ,

5. Go to section 3.0 and take a reactor coolant samole using the PALS, .

analy::ing the samole as stated in the procedure. !

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ENCLOSURE 9.2

'p OP/0/A/6200/48 PALS DATA SHEET PART I (Complete prior to going to control panel)

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Time 1 - Verify 1KC "A" Train is in operation.

2 - Sample valves opened as per 4.1.1 for the respective sample.

j 3 - Health Physics notified for monitoring support.

4 - Specific Conductivity of pH 7.0 buffer (reference i Primary Chemistry Log). umhos/cm PART II (Complete at the control panel) 1 - Specific Conductivity of pH 7.0 buffer (measured), umhos/cm 2 - pH meter standardized. ,

< 3 - Radiation field (presample background) rem /hr 4 - Time sample purge started. hrs 5 - Temperature: Tc 1 *F Temperature: Tc 2 'F -

6 - Radiation field (at sampling) rem /hr

- Radiation field (background) rem /hr Radiation dua to sample rem /hr

_ 7 - Pressure at Isolation . psig 8 - Time sample purge isolated h r .,

9 - Specific Conductivity ef sample umhos/cm 10- pH of sample (measured) 11- Dilution volume (mis. H O added) mis 2

12- Radiation field (postsample) rem /hr 13 *pH of sample (boron corrected)

NOTE: If baron is present in sample, pH can be adjusted for boron by referring to baron curve in CP/0/8/8100/43. If this is a post accident sump samole, do not correct pH for boron.

PART III (Complete in Hot Lab) 1 - Gas Analysis cc/kg H

, 2 I cc/kg 0 2 2 - GeLi Spectral Analysis (Gas) 3 - GeLi Spectral Analysis (Liouid) 4 - Baron Concentration opm B 5 - Chloride Concentration opm Cl-

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ENCLOSURE 9.3

,- x. OP/0/A/6400/48 CORRECTION.0F DILUTION VOLL'ME To correct th,e dilution volume, divide the final radiation reading (Section 5.10,5) by 3 rem /hr, then multiply this by 250 mi to obtain desired dilution volume in Section 5.6.3.

Example: Reading in Section 5.10.5 = 10 rem /hr then 10 rem /hr x 250 = 833 ml 3

Go back to Section 5.2 and repeat the sample sequence, using a dilution volume of

.833 ml in Section 5.6.J instead of 250 mis.

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ENCLOSURE 9.4 i

OP/0/A/6200/48 ,

I PALS CONTROL PANEL DIAGRAM i,

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PALS CONTROL PANEL DIAGRAM

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l DCLOSURE.9.5 OP/0/A/6200/48 DIRECTIVES FCR PERSC10G1 CONDUCT U M HOT LABORATORT, THE ATOMIC ABSCRPTICN LA3CRATCET, UNIT 1 & 2 PRDfARY SAMPLUG LABORATORIIS, AND M RADWAS'lE.OPERATU G CZ3TD.

i

1. tassas. desatsas. and e s uma at taasens are ymmenksame. l

. tammy and emst fram en f-= aanLL emm&y was empses sen&a Parudas Premmensus.

3. se poems ama&1 uses waam er amar ressammmese amournais stamma em pumper endsey amasse unden immandem en ad rester

g&ss e . Las amas, and are ymmemamaan. ^

l

6. P8 = ==*== **=11 aus be dann er ammet ammmaa. A andeur ynges f112mr er sta== ande shaLL be emed. .

!. *=d*===*ue 18ande umsee sam &1 he 4faemand ed la ar==884= samme enLy. Lemmad rentammetse emeia sm&amme. tremand ummer (T3.15. Sour q) fisum. ama dissemak ed ame=emdsammesse Lfemnes are a he smammanand as enanmenL as poemsMa ta emner es Limbs umseas reguamass r=dd====*= ummes pseammenas.

(A) tea.'.aternemer L. tame um&& esak = mda saan la for his esmestar (Mace sum U2" tems 12 ok toesia) 11emsd unnema enLy., ihm emena la rename as me ChenanL Deman *.mh ad eks enemmmes emma undungo ens 4Ly ==2td4*a==t='m as tsumm uns as anLid umsems. tan aestvtsy er mmW- maasta&a ame mes to to 4dagemme ed la sans stas.

3. 3mme ma&L esas aus fem huma samme a tamme stamm ame for las amavtsy (4100s aus U2= tume LM mL toes &al umseas. These demans ame rumens a the Fleur 3meda Tammi.

l

3. 1emmassa tasaaremano enlausde emmemn ama en&2ammen ta teammma meal filand. een stor are enemmemused as can Sa&id samen Steem ist disemme&. Es ammmmuna sanasymmmme la es he 'W em er mean emuda.

(3) &amaa Anmarnes s latern e rE

1. wd-= maartaAs ed amr type stall ame be ===*e==d to amens adata esame une emmaan ame romend 41sumsLy as tan ams===== (danna es ymme damna en tems en sammer w sam,tas ummer pose.

2. andammmesse 11ansd amens amo es&ammems sa -r==aamd ammaaaamma ens apesas :.ame as ampumpasaan Eos Lahmes=

tuer asan as mammmmary.

(Q Pesamrr SamL1am *.ateveesties I & *!

1. Siah damsam for all amens ame romand as saa sessa tenemesser femd tank.

i, 1. Ande ungens tumm flam&ar 3samm&ves Ourgem amm&yssa ame =11==a-d la spemadies emmastaamm, tsumand as per pumamemme CF/0/3/41Mf91 ame disemane ed ta a Pramany f,as 31am.

- en&F.

6. wi====*= mm&&& ummems and ammmmammmme naamma&s amo es to en&&ammad la seen&#$ad redisemmest umsen meemuta&s ame aos em to etapaams ed sa che russammesse weem - La. esser em Sc h ue or _

adanmaan asLid ummes psummundas.

7. Saddammesse amammia&s ame emmmmmassend seamsta&s em he tempummm&1F sammed a8 '="'1====d lemmatans is the lateneemanas.

smaLL summen sa tem t-a======= uname woundssa ame=ammamammame by sankta

a. All asemmens used sa es t-=

nymam pemmumet for rumuset.

9. Same bemanamenes pousmaams sam && to semeses as aLL tamms, tam &sesas ===a== poemmassammy ametrasy sussure.

12. !a tse suma ed r=d====*= 11amed se&Llaga, the fa42mmeas same amo es he puedommes (M 3e tsamad ta to to tassame es umme rumene s&ssus ame seem ausmus. Cemensa tem spaal es as senLL as amma as ymmes&&a.

(11 all '*"t= esammamas emmamamment Dr tan se&LL and tas elanums pommmes are to be '=f==d==d is a russammate vues .

(C *he amma ed the ses11 la es be idemmadias e&ammir and en type ammarter '==8==== 12

rumsas.

(D) Camamms smakam Fermans far serem1Lamme and de-emummmemmedan.

11. 12. La the amuss ed uses, peammmmmL ~ !a h - a muger wast a ampuevesame assertcy demanese se to be emme tammatammky. This ===Ad be faCJuma ty rammeses _ ~ eamannas and asserter

12. ALL ummmas. soalla er eense emmagemesas amo es be reemesme as Emm&am Physses tumumanaam&y.

12. 12 fue base a cas esu ummme, er sena lamsam. seesky a Chenaamy searramme yrsar en hetL&as mer rassassette me= i tarta&.

14. Sadows amtesas a taasemeser, ammme Waa- er stamme ed ase& vistas as to presums ~. smuus&a er unear

! .w - - ^.er sm o&a saa as. Camo&ame aLL - 7 paper uses prise to amts.

12. Pan a===a saaLL to ia e,mrmsses as all tamme wome tse peesses1&gy si a&resens r=d*==*= ausses.

14. 1e ramamassive =amesmia are p==n *'ad in the Cald. ^====** 2aueLlag er usear *rumemme f.amerammetas.

l l

l .

,,,m__,,,,m.,---,_,--.

w O

Form SPD-1002-1 1

DUKE P0bT.R CG3PANY (1) ID No: HP/0/B/1009/08 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD C Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE:

Evaluation of a Reactor Coolant Leak Inside Containment (4) PREPARED BY: 4 M A _ M [# o DATE: 7 C d ,,, f2 1 (5) REVIEWED BY: Ct f. / - / DATE: / //a/# 4 y

Cross-Disciplinary Review By: N/R Q ,# 2 V

(6) TEMPORARY APPROVAL (IF NECESSARY):

l

) _

By: (SRO) Date:

By: . Date: .

(7) APPROVED BY: .#...,_/

.,e

/ T h ~ // Date: /I /C (8) MISCELLANEOUS:

Reviewed / Approved By: Data:

{ e I

C$

l l

+__,_,---gy --

-m.e.vg,.w.-mg -gwy-e w,w.---e,

.~

l i p- .

I i

,q HP/0/B/1009/08 l- (- .

DUEE PWER COMPANY il '

McGUIRE NUCLEAR STATION E7ALUATION OF A REACTOR COOLANT LEAK INSIDE CONTADDENT

. 1.0 Purpose li This procedure describes the method for evaluating the offsite dose

rate and does in the event of a reactor coolant leak inside i

cone =4===nt. In addition, this procedure can provide warning l

j message information to be given to State / Local agencies.

2.0 References 2.1 Station Health Physics Manual. Section 18.2; Environmental Monitoring for Emergency Conditions.

l 2.2 TID 14844.

j 2.3 HP/0/B/1009/02, Alternative Methods for Dete M =4=- Dose Rate t

! Within the Rasctor Building. '

i

2.4 Offsite Dose Calculation Manual (CDCM).

2.5 EP/0/B/1009/05 First Responsa Evaluation of a Rasctor Coolant

{

j

. -.s Laak Inside Cone =4===at.

! \

2.6 Unic Data Book. 3

\ --

//

3.0 Limits and Precautions g' j 3.1 This procedure is being used in an emergency situation which i could result in evacuation of areas surrounding the plant.

1 j The procedure shall be fully understood and a=Ta=1=tions shall

] be done carefully and accurately.

] 3.2 This procedure is written for use under abnormal conditions

'which could involve extremely high radiation levels. Only the Station Health Physicist or his designes should authorize the

] use of this p..c.edste when needed and should provide l a ry.-y. late surveillance and control of people taking the samples.

3.3 Check that the counting equipment to be used has been j calibrated and daily response checks have been performed.

f 3.4 Indiv1 duals collecting the samples should be aware of the-l possibility of airborne cour==ination and high radiation j levels in sampling areas. Use protective clothing, gloves.

,- respiratory protec,tive equipment, portable shielding, high l I 1

v i

Page 2 i

d

,w range dosimeters, and survey instruments as determined by ]

i /

l ( Health Physics supervisor.

- 3.5 If action is taken in the 4-10 mile radius area per reference j 2.5, then wind direction should be rechecked every fifteen i

1 (15) ainutes to ensure that additional sectors have not been i affected. Once a sector has been added to the list, it cannot f be removed from the list.

3.6 Projected doses should be compared to the Environmental l Protection Agency Protective Action Guides to determine levels of protective action.

f' 4.0 Procedure 4.1 Acquire the following information and record on Enclosure 5.4 i sad 5.5.

NOTE 1: Some of the following information can be obtained

! from the ' Tech Specs 04' program of the Operator Aid Computer (OAC). All information availmhle in ' Tech -

} Specs 04' will be denoted in the following procedure l by a '(TS)' to the left of the section number. See l 'x Enclosure 5.9 for steps to access ' Tech Specs 04'.

l NOTE 2: Se== rimed warning message information t a given to j state / local agencias will be denotefl'in the

following procedure by a '(WM)' to the left of the f

. section number.

NOTE 3: Noteorological data should be obtained in the order of preference listed in Enclosure 5.4.

i NOTE 4: Use fifteen (15) ainutes averages for all anteorological data.

1 .

j 4.1.1 Time of Reactor trip / shutdown (hours after midnight) l sad date.

4.1.2 Time of ~1 ~ f= tion (hours after midnight) and date.

I j' (*) 4.1.3 Wind direction recorded in degrees from North (upper cover). Lower cover wind direction should be used only if upper tower data is unavailable. ,

I } 4.1.4 Lower tower wind speed (MPH) (W). Upper tower wind speed should be used only if lower tower is 1

unavailable.

(

u I

. Pge 3 4.1.5 Vertical temperature gradient or a T*C (Lower to x

Upper tower) from the -4 to +8 scale on the meteorological temperature strip chart recorder.

NOTE 1: The above information is used along with the Table on Enclosure 5.6 and may provided in TSC to determine areas affected by release.

NOTE 2: Plume direction is 180" opposite wind direction.

(*) 4.1.6 Stability class (A, B, C, D, E. F, or G) from Table I (Enclosure 5.1).

(*) 4.1.7 Ambient air temperature (*C) . Record in *F where:

F = 9/5 x *C + 32.

( ) 4.1.8 Precipitation.

(*) 4.1.9 Ralease height is 33 feet above yard elevation.

4.1.10 Laak rate, which is either known leak race or design leak rate.

= Cones 4 - t Volume x Design Leak Constar

% design leak rata l = 2.9 x 1010,g ,.0020 g m..

x 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

= 2.42 x 106 al/luli.

NOTE: Enclosure 5.8 should be used in determining leak rate if other than design leak rate is used.

4.1.11 Reactor Building dose rate (EMF 51 A or B, whichever

) is higher or reference 2.3).

NOTE: Information in sections 4.1.12, 4.1.13, and 4.1.14 is not cornally used. It is available if needed for working with outside agencies.

4.1.12 talasseconcentrations(gg and C7 ) f m H M eh l Physics sempling of the Post Accident Cone =4n==nc Air Sampling System; or EMF data if sample results are not available, as follows:

If EMF 39 (H) < 100 eps, )

' = EMF 39 (L) cpm x 3.8 E-8 C

NG U

l 1

I i

- , - - - - - - - , - -- - - , . - . - . . . , . , ~ , - - - - . - - - - - - - - - - - - - - - - - . - - - . - - . - ,

l

l * -

Page 4 h--~

or if EMF 39 (H) > 100 cpu j C, = EMF 39 (H) cpu x 2 E-4 '

C = EMF 40 A cpa/A cias x 2.34 E-10 7

j Where:

3 Cg = noble gas release concentratiou in uC1/mi Cg = I-m eqdv. release concentration h UC1/mi 3.8 E-8 = EMF 39 (L) correlation factor in uci/al/cpa from reference 2.6 i

2 E-4 = EMF 39 (H) correlation factor in

! uCi/a1 cys from reference 2.6 j 2.34 E-10 = EMF 40 correlation factor in uC1/al/cpa/ min from reference 2.6 i .

4.1.13 Calculate radiological release race (Q) in C1/sec' using the following formula:

4,=C,= tax 7.86E-6

m at - c rx ta x 7.86 E-6 k_1 h=(Cg + C )7 x La x 7.86 E-6' j,

Where: g' hg = noble gas radiological release rate in C1/sec 4

hg= I-131 equiv radiological release rate in C1/sec k=radiologicalreleaseraceinC1/sec La = leak rate in al/hr (section 4.1.10) 7.86 E-6 = 2.83 E4 cas jggs = 2.78E-4 hr/sec x IE-6 Ci/uci All other variables same as previously stated.

N) 4.1.14 Calculate dose conversion factors in 1/hr/C1/a8 for whole body and child thyroid using the following formulas:

l, "

DCFgg = 0.5 x 3.7 E10 x 3600 x Y 1.3E3 x 100 x 6.25E5 ,

j ,

I t

1

- . . . - , . _ . . . - ~ . - - .,,-.,,_..,.,-.--.,,.n._ _ _ , , , , _ _ , , , . . . . , . . , - , . . . - - - _ _ , , _ , _ , , _ , -

- - Page 5 DCF WB

= 820 x i fm i

( l Where:

1

~

DCF WB

= le body dose conversion factor in R/hr/C1/m8 I

! 0.5 = conversion from infinite cloud to semi-infinite cloud whole body dose I = average Nev/ dis from Count Room data NOTE: If I cannot be obtained from sample I results, the follwing values should

-be'used.

I 4 s

Hours from Trip ,

I in Mav/ dis I

< 12 0.40

) 12 - 48 0.20 .

[' . > 48 0.10 s 1.3 E3 = density of air in g/m 8 Conversion factors: -

ds 3.7 E10 dis /sec

C1 g' 3600 sec/hr .

100 erg /g

rad 6.25E5 Mov/ erg DCFg = 4.39E-3 r. LE12 x LE-3 x 0.422 DCFg = 1.85 E6 l Where: j DCFg = ehild thyroid dose conversion factor in

. R/hr/Ci/m8 4.39E-3 = inhalation dose factor for child thyroid in aren/pci, from reference 2.4

. N -0,A22. = child breaching rate in m 3/hr, from reference 2.4 Conversion factors

i .- 1E12 pCi/Ci

' / 1E-3 rad / mrad J

e

p 1

f Page 6 4.1.15 Two (2) hour relative concentracion (CH) in sph

3 i,

sec/as from Table I (Enclosure 5.1) at the site boundary (0.5), 2, 5 and 10 mile points. Record on Table I and Table II of Enclosure 5.5.

4.1.16 (*=le=1=ce the dose rate and two (2) hour Dose 1

4 Ccamitment (Rea) at the site boundary (0.5), 2, 5.

1 and 10 mile points using computer progrsa EPIPOS 4

^

(Enclosare 5.10) and Enclosures 5.4 and 5.5, or the I

usuaal a= Tant =tions shown in the following sections t

! of this procedure.

I J

(UK) 4.1.17 Determine the child thyroid dose race at the site boundary (0,5), 2, 5, and to mile points using the

! fallowing fcrmula:,

t l

Dg =D g x LR x TDCF 7 x1xG g

4 -

! Where:

i Dg = ehild thyroid dose rate in Rem / hour

-3.>

. ,s ,

\... ,

Dg =reactorbuildingdoserp'inRem/ hour (section 4.1.11)

LR = leak rate in al/hr (section 4.1.10)

TDCF7

= I-131 equiv. time decernined conversion i factor (from Table on Enclosure 5.2) and:

l 1 ,

TDCF 7

= A x 1.17E-4 x IE3

. D

t 7 1 Where

g = I-131 activity vs. time in uC1.aren al* PC1 l 1.17 E-4 = child breathing race in 3 8 see 1E3 = conversion factor in pCi* Rea

' uCi

mRea b7-I-131 dose race vs time in R

' hr

4 7

Page 7

, W = windspeed in uph (section 4.1.4)

G = Two (2) hour relative concentration in aph

sec/m8 (section 4.1.15)

NOTE: This can be rapidly accomplished by storing in e=1e"1= tor memory the result of all numbers, excepting G,

, and then ree=114== this number to nultiply by each G value for the 0.5, 2, 5, and 10 mile points (as shown on Table I on Enclosure 5.5).

} 4.1.18 Determine child thyroid dose at the site boundary (0.5), 2, 5, and 10 mile points by multiplying the dose rates at these points (as done in section 4.1.17 and shown on Table I on Enclosure 5.5) by the dose assessment period (in hours). -

NOTE: G values based on a two (2) hour

dose assessment period.

I 4.1.19 Determine the whole body gamma dose rate at the site 3

) -

W i 7 (0.5), 2, 5 and 10 mile point ' usiss the

/s following formula: g' bgg =D g x LR z TDCFNG *W1

Where:

D WB

= whole body gamma dose rate in Ram /hr.

TDCFg = Noble gas time determined conversion factor (from Table on Enclosure 5.3) and:

1 TDCFg = A , x 0.23E-6 l D3g ;

Where: I A

NG

= noble gas activity vs. time in uCi*Mov al

dis

.03 x 10 rad 38 dis = (k) (3.7 x 10' d/s/uci) (1.6 x 10-6 ,,,f3,7 3

uCi see MeV (100 erg /g. rad)(0.00129g/cm )(1 x 10 cm3/m 8 )

e

4 1

- Page 8

~

Dgg - nobi. gas dose race vs time in a_

! hr f All other variables same as previously stated.

NOTE: This can be rapidly accomplished by I

storing in calculator memory the result of all numbers, excepting CE, and then rea=11 h- this number to uniciply by each G value for the j 0.5, 2, 5, and 10 mile points (as shown on Table II on Enclosure 5.5).

} 4.1.20 Determine whole body gamma dose at the site boundary (0.5), 2, 5, and 10 mile points by multiplying the

dose rates at these points (as done in section 4.1.19 and shown on Table II on Enclosure 5.5) by ,

the dose assessment period (in hours).

l

, NOTE: CE values based on a two (2) hour dose assessment period. 3 4.2 determine potentially affected zones based onf W direction using the table on Enclosure 5.6, and record on Enclosure 5.6.

4.3 Determine levels of protective action by comparing projected doses to EPA Protective Action Guides (page 2 of 3 on Enclosure 5.6) and record on Enclosure 5.6.

4.4 Determine if non-stagnating meteorological conditions exist by observing meteorological strip chart data. If:

(1) Instantaneous wind direction has not varied over 90* in the past tuo (2) hours, and (2) Instantaneous wind speed has not fallen below 10 MPH in the past two (2) hours, then

, non-stagnating conditions exist.

Record result on page 5 of 5 of Enclosure 5.1.

4.5 Check results and inform Emergency Coordinator of your recommendations.

4.6 Whenever possible, utiliza environmental data in comparison with calculated results to better determine plume i

( -

l l

. . . . , . ..% , . e. * -e- -* = - - - * - - - - 9 e '

,e - ,, --n- , - , - , - - -,,

- Pge 9 i

dispersions. Record environmental data on Enclosure 5.4 when t

available.

./

NOTE: De=aadiat on meteorologic conditions, field I monitoring tesse may experience diffic'tity in i

! finding the plume. Therefore, negative field j ,

results do not necessarily mean that radioactivity l 1s not being released.

i

. 4.7 Calenlaced results should be compared with those from the

! Crisis Management Center (if accessible). Any discrepancies i

should be resolved through re,.tentations and calculation step comparisons.

I l 4.8 Historical data shall be retained so that offsite dose trends can be analyzed.

! 4.9 Insure that Enclosures 5.4, 5.5, and 5.6 are properly completed and results presented to Station Health Physicist or l

i his designee. -

4.10 Actual field measurements of whole body doses will be compared to whole body dose projections by the Data Evaluations j

' -] Coordinator. .

1 :

! 5.0 Enclosures

r j

e 5.1 Table I, Two Hour Relative Concentration d

} 5.2 Table of I-131 Equivalent Time Determined Conversion Factors t

5.3 Table of Noble Gas Time Determined Conversion Factors

, 5.4 Projected Exposure Data Sheet j 5.5. Projected Exposure Work Sheet j 5.6 Table of Affected Areas 4

l 5.7 Accident Assumptions Based on Potential 5.8 Estimating Cone =4n=ent Release Eates (P.F. 9. 4. 2) f l, 5.9 OAC (Tech Specs 04) User Documentation l 5.10 EPIP08, User Documentation j; 5.11 Offsite Dose Projections (Sample of Computer Printout) 1 I I

l !,

i

i a

i * "A l

+ .. , . ,-.

.-,+.___mm - - - - --,--.,t- - . - , - , , _ _ . _ , - - - -

.4,-. -, ,- - - + - - - - , - . - - - - - - . - + - .,,.-m,..,--,w..,_ e.-y,. -- ,.,---... .- -.u.-., -- - - - - - . _ , - --.-y. - - . -- _,--w,- .,- m

. . . _ _ _ _ _ _ _ _ . . _ . _ . . _ . . __ _ -____ __ _. __ . _ _ _ . _ _ ~ _ - . - _ - - - - . _.

q k,' N. ,

i Enclosure 5.1 HP/0/8/I009/08 TABLE 1 2180UE eel.ATIVR CONCENTRATION (CH)

Stability Distance (in miles)

Temp. Diff(*C) Clase 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0

(

I l

l 1. < -0. 6 A 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 j 2. -0.5 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.lE-6 8.3E-7 7.8E-7 1

j 3. -0.4 to -0.2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6

4. -0.1 to +0.4 E 6.9E-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.!E-5 9.7Z-6

5. +0.5 to +1.2 F 1.lE-3 5.!E-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.3k-5 3.8E-5 3.3E-5 3.0E-5 I 6. > +1.3 0 1.8E-3 1.!E-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 The temperature differential is the difference in temperature

] between the upper and lovar temperature sensors and is in degrees centrigrade.

l These values are site-specific for McGuire Nuclear Station.

~

8 9

l .

1

. \

i HP/0/B/1009/08 ENCI.0SURE 5.2

(

PAGE 1 0F 1 Table of I-131 Equivalent Tina Decernined Conversion Factors (TDCF7 )

Time (hours after trip) TDCF g 0-1 1.93 E-7 1.1 - 3 2.68 E-7 3.1 - 5 3.30 E-7 5.1 - 7 3.84 E-7 7.1 - 10 4.68 E-7 .

10.1 - 15 5.59 E-7 .

15.1 - 20 6.55- E-7 20.1 - 30 8.14 E-7 .

- 30.1.- 40 -

9.20 E-7 !

, 40.1 - 50 9.75 E-7 /I' l

l 4

M

% 8

I t

EP/0/B/1009/08 ENCLOSURE 5.3 PAGE 1 0F 1 Table of Noble Gas Time Determined Conversion Factors (TDCFg)

Time (hours after trip) _TDCFgg 0-1 1.57 E-9

~ ~ ~ '

1.1 - 3 1.53 E-9

~

3.1 - 5 1.35 E-9

. 5.1 - 7 1.31 E-9 7.1 - 10 1.56 E-9 10.1 - 15 1.78 E-9 15 . 1 - 20 1.90 E-9 20.1 - 30 1.93 E-9 30.1 - 40 1.94 E-9 40.1 .- 50 1.84 E-9 j,

. [

e l

t l

t I

5 0

w -

EP/0/3/1009/08 l

5, S ENCLOSURE 5.4

~

1 PAGE 1 of 2 i

i PROJECTED EXPOSURE DATA SHEET 2

Time of trip / shutdown hours after midnight. Date .

l Time of a=1 ~1= tion hours af ter =4d=4ght. Date .

(All meteorological data is 15 minute average)

]

] Time (15 minute period ending time) hours after midnight.

1 (W) Wind Direction 1) Upper tower degrees from North.

l.

I or 2) Lower tower degrees from North.

. (W) Wind Speed 1) Lower tower *2R l or 2) Upper tower MPE l AT 1) Lower to Upper tower *C

2) For 1000 - 1600 -0.2 *C

] or ,

or 3) For 1600 - 1000 +1.3 *C

'l (W) Stability Class (AT and Enclosure 5.1)

N ~ (W) Temperature *C l

. Convert *C to *F: *F = (9/5)( *C) +32 j, (W) Precipitation [#

(W) Release Height = 33 feet Laak Rate al/hr Rx. Bldg. Dose Rate R/hr i

UNENDEN RELEASE CONCENTRATIONS (CNG ** I}

(EMF DATA) 4 If EMF 39 (H) <100 cym, Cg uci/af = EMF 39 (L) cpm x 3.8 E-8 uC1/al/cpa l Or if EMF 39 (H) > 100 cya

! Cg uCi/mi = EMF 39 (H) cpm x 2 E-4 uCi/al/cys C uC1/mi = EMF 40 A cya/A time x 2.34 E-10 uC1/mi 7

epa / min N

. ---s.mm, .- .-e.- . . ~ - . . - , , , . - . . - . ,.

]

. .m HP/0/B/1009/08

( Enclosure 5.5 Page 1 of 2 1

l MNHL CALCUMTION WORKSHEET l

l

+

Eadiologfcal release rate (q)

J l

j (W) .

1 Q ,.

Ci/sec = C.,. -.

x LR x 7.86 E-6 (W) .

Q7 Ci/sec = C7 x LR x 7.86 E-6 1

~

(W) Q C1/sec = (C g +C 7 ) x LR x 7.86 E-6

?

i i

l Dose Conversion factors for whole body (DCFyg) and child thyroid (DCFg)

I

_ -)s j }DCFh, 1/hr/C1/as = 820 x E ['-

1

') <

I III DCF CT

= 1.85E6 R/hr/C1/m3 i

i 1

i NOTE: The information on this page is not normally used. It is j tveilable if needed for working with outside agencies.

5 l

' j t

1

's; I

l

- - ~ ~ ~ * * * *

._._s .m.- -m.. ..e--n e- - - -

-e, ---

_ y ,y,--.9- -g-- , - - - - ----v----w- , . , - - - - -

'1 l

N HP/0/3/1009/08 k Enclosure 5.5 Page 2 of 2 Dose Rate and Dose cale=1=tions Child Thyroid (Record all G values for 0.5, 2, 5, and 10 miles in Table I) bg =bg x LR x TDCF 7

x 1 xG I

t Store in e=lentator memory Table I - Child Thyroid Dose Rate and Dose (101) ,

Stored Dose Rate Time Dose .

Distance G Calc. Value (Res/ hour) Period (Rem)

S.5. 0.5 a1. x = x =

- 2 mi. x = x =

's 5' a1. x " = .

x "

=f 3 10 mi. x " = x "g[

G values based on a two (2) hour dose assessment period.

Whole Body (Record all G values for 0.5, 2, 5, and 10 miles in Table II).

l D =D z L1 x TDCF3g x 1 xG WB RB W

Store in e=1e=1= tor memory Table II - Whole Body Dose Race and Dose >

(Uti) ,

j Stored Dose Rate Time Dose

! Distance G Cale. Value (Rem / hour) Period (Rem) <

l

, S.B. 0.5 mi. x = x -

! 2 d. x = x = l 5 31. z = x =

10 31. x = x = l l

l l

e a G values based on a two (2) hour dose assessment period. l l

t l

i l

s .

j . _ . . _ . . . _ .

] HP/0/B/1009/08

\ ,_, . Enclosure 5.6 Page 1 of 3 I

Determine affected areas based on wind direction from the table below:

Wind (degrees from 0-4 4 - 10 Direction North) Mile Mile Recommendation Recosumendation 0- 22.5 See Note 1 R T.S.E.F.U 22.6 - 45.0 R.T S.E.U,P 45.1 - 67.5 R.T.S.E.U,P 67.5 - 90.0 R.T,5,U,P,N,0 90.1 - 112.5 R.T.S.P.N,0 112.6 - 135.0 R.P,N,0,L

~

135.1 - 157.5 I.P.N,0,L 157.6 - 180.0 I,N,0,L.T,J,H

.. 180.1 - 202.5 I 5,L.J,H G j 202.6 - 225.0 I,5,L,J,H,G 225.1 - 247.5 ,/d,H.G,F 247.6 - 270.0 N/,H,G,F 270.1 - 292.5 H.G,F,E 292.6 - 315.0 G,F,E

~

315.1 - 337.5 G.F.E.U 337.6 - 359.9 F,E U.S BOII 1: Areas A,3 C.D,Q,7,M will be the reemded areas if any action is taken in the 0 - 4 mile radius of the plant.

This recomandation is independent of wind direction.

i e

l v) l l

l

! ~

s . i

_m .-.,e .-++r w .n = ; se e y* rege r ese *er* me w* == ** . *-* v*e w e w w ***M*M****.**r*.**** - .* * * * * ' *-**-***~

1

. Helolshoos/co Em.lasare 5.4 m

Pne z of 3 i 4

! i,

' sus E 122

5 t ? 4 . . ..

- 1':t r58 - g::1s2 :- 1 1 a v 18

.5:

s--81 :: v.eL

- :j:y t

I.. :: g -

11:- 3 22 2 i t a s i ~a .42 l, .

ti b i il111 -

4115 'ict i 4.173:=!! =

E i2 rI: ! *,i t r:-

2]r 12 ee :

. a r

t,1

.e .u. el 21 a n.l =2.31l:.: - -

i . . -

1 1

a. s.

- r- 1 -

I : 2 s g a

g - 3-2)

-En g

=

14 1

4 1 e

.t :

u ::=- ::t *

.:-t3 s 5- : :

= = I I.- = :s -

e T I41 : 1 4

%* <!3 1: 1 .4

1 g,s*

-1= -

i 2: -

5 : .: -:

1

-Y 32.3 g::

.: 3 11

f: - r;l .*

f } ..

j;* =2

2 $3

-j

.I ::

.-q

1 _:: 1:;g!

1- -

g..

.u I-t -I .s - ::. es -

=le : 4 es s-[2=g 12s l: 1- f g-. -

8 g:-

- , 2

_ ':g g3: g 1.i 1

e e, :s. 1.3 13 s .,. -: :

l.gt! 231 :

I:.:-4 t:: [.: s ' 1: 1:.-

=

3 :::

-: !:r ,

i

- '2: !:: .a t

- 2 s'-i -

t1~85. i1.3- , -2t2 .gI

.t 12- > 11 =2 =: ,- 3 i 1:L: -: - 111 -:1=

2 - -

I 44 1 13 11 11 I I li s *:

t. ,,I

3er 1 -- i

] _

. ,. (( _

s. n a ].2

j. In s: 1I II

el 23

, 23 e -- -c .. *. E y 2,5 13 1 t

- a s. - - - - - - + ::

, I.. , I. I. 3. .

1g.

I, 1 21 2

,s:

1 1 .

1 . 7 t I. - -

2,:. ,e t-

- e

- I e- ie ie- -eI 1 e. i 3.2 Aseta.d im

[

e

- -wm- -= a ge--e

--,-_-ap- -

l l

l t

w ,

HP/0/5/1009/08 l

(. Enclosure 5.6 l

Page 3 of 3 l

0 - 4 miles Recommended Areas Recommended Population-4 - 10 miles Reco-dad Areas Ree m ded Population Non-stagnating meteorological conditions do _ /do not exist.

. Signature r

d NOTE TO EMERGENCY C009DDIAT01:

If the release is projected to .end within one-half ( ) hour, and non-stagnating meteorological conditions exist, consider not reco M ing an evacuation if the plume will have left the Emergency Protection Zone (EPZ) before3the population could evacuate.

69 G

0

\

% 4

,--ee- - . . m em ., assewy.w% n6e+++ e...e-.- y .g= e,-f me 7 -gew e =. e e ,c ye , o w v enom-pee,e- e - = ,,-

e-

EP/0/3/100f/08 -*

. ,- r. . -

IBC105URI 5 1'? .

m

- Page 1 of 3 ,

t I

i ACCIDEIZ Amauanwas BASED ON PCIIIIIAL .

. -- Desteir Basis Accident assians TID-14864 release of fission products to the com-221===e atmospheras . . . . - .

(1) 100E of all core noble gas , activity .

-- '- t; (2) 503 of all core Indiner asti.vity with place out of half of chas . .

-- - **

P- released. Ihms-C ., 252 of the Iodine activity will be. in .ths ..

~==e=4 -e e -- -: - :- .:-

l

--"" 9 ~~ 1hesFof'Imactor Coolanc. asemme char release of one reactor coolans volums with- .:..

- - - --' noble gas and. Indina activity ===a-4 =e=d with o==-=-d- as. wu*. pause WEE II" .

faal failure before t5e relanse. g .. ..

t

- -- --- ~ telease of the Gas Activity assumes that chars is -T add * !. failure sufficiant to. .

--- - !? ' release;is11 fission products in the gas gap of the fuer pinsWcontasamenY'-~ .

- - - ' 6. Assamed is also ines of 101 of all cars noble gas. activity.and 101.. .:

of all cars Iodine activity to the co=e=4-==e -

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

cone =4-==e lank. rate is, assumes to bas ...

i l

(1) 0.2=/ day for 0 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

(2) 0.Iz/ day for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months - 30 days .. ..

l ,

I e .

, ...& . :: :., m.:Ihe 0.2%/dar is the Tech. spes. leak rata ==a-4 = =d with, the. danigs. .

pressues of 14.8 peig.

- . : 3,c. ; , , : ,. .:.

i

. ... m . g= = Pti g in a.,= -+ _ tha concribucion to the...to. __. a h.. .. ... ... .

u. :. g amerse==r ore 9"-- system (zccs) 1.ekage aires.

c . ..: ;,, .

-- - : = -- - (a) 7520 auhr Iankage from the pump seals and valves of the .sces,in. , .. . , .

the -4 9 4- y h 4 4 A4~. . . . .

a :-- - -

- .a :. - Or) As Iodine partition factor of 0.2. is M to dach the_W.of.I53' ii.

3: released em the - -4=-7 h-di d4 - -

aer-:. .u.. ..

...s .--.... ..- _ .

' '5;- =' "' (c) En. credir. is takes for the 7A charcoal filcars because ths.Ya . a .. .. .... . . .

system is nec safety related. ... m a ... ,,.. ,

7 *-- '

'- 3ys simit 2ankage is, the fraction, of the total cone =4-e laskage,,that. bypasses.=,. . .

tha -ta= and ==-=p== to. thm ==a=ph=-s unfilmaced. , ..

.. .- - . ... u -_.s .. .... .. . . . .

Samm aumplan of bypass Taalr= gar paths are .. .. -u .. . . . . . ..-..,s... . .

6. -(ygy- Lankage - 4 aane=4-==e '=af **4a= valves- thac do not. sen.c. properly. .. . .. ...

1 (2), tankaan aroums, the equipsac hatch seals. . 3,..,., . . -.-. . ..

.. :- ..-kMcGuire the aa=e=4-==e bypass. lankage is 7% of the total cone =4===e lankage. . .,

(Tech. Spee. 2.4.1.2, Revision 401 - ,. .,; , . , . ..

1 I .

1 l v' .

1

'1

_ _ _ - - - - ,.-- __ , . - . - - - . - . _ , , , , _ , , ,.p

Mr/0/s/100s/or "

i

. - . *t* --

13CLOSUIE 5e7 t

'.' Page 2 o$ 3

[

i a i ACCIDENT ASSUXrTIOES .

l

Dosa contr4he4- are as fa11aust - - :- :;.: . . .: .. ....-

Thyroids

801 from hypass lankage - - .. ---

105: free ICC5 7 ==Irmga -- .

' 10E from VE system lankage . : -::~ .

Whela 3odys 44E from bypass Iankage . . ,

33 framr ICCS Taalrege .

33E from VE system lankage

a-

-- - * - At-Mtsuite only 83% of the ---414=+7 W id47 ventilation system;is safety . . .

~

- ~ - talhead.' Therefore, whom calculating relaamas following .am ~4d-*,

credit -

m -is bot-takes for the VA charcoeL f11 tars. However,ths.YA.syst.amisprovidad[. - .

- - ' with emergency power and any bypass lankage or ECCS lankage to .tha ---d147 Hw- will be relaneet through the unit vent. The onLY. source .qf J4-dvik - .

- : ' - - -that-deer ~not go one the unir vens would be bypass lankage amound the equi,pmaat. ..

- - - ;"--haceh' semis (see Fig.1) wenich is only a small fraction of thes tocal releass. I .

1

's 4 4

i

. ds I

.. / /.

9 D 8 1

. t 4

.~ . ;

1 e

l l

m# O e e en- - - -

, .m .

A.=

l I

I O

C

.g McGulM NacLCAR SDMN

_h

e

'J e i.

n4 =

3

.g

g --

' ' ' ' ' ~~

.i's='I C... K,. .. 7 2 @ ."~ 7.. 7.. 7,7.G. 7,. ,.7 C [* "~ T ,"~ D i.7, ~,""g,'

%)

=.,. -

e-A- ,e vv-e:--

m. .

s.=

. . rs- . . . - "

s- 1 t

4--_r . = s-_ r h j-. _ vm _ s p _- . _ _ 1r se- .r

^

11 __xz

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

je,f y _ - - . . ,r- =-____.-=2____, -.

. ._-..- 1 -_-----.x__-r__x__=---._-_ - _ __ - - _ _

-____**_='-_2__--_._=---._--:=_----- -

I :tr= _ . . _ . _ _ _

0 "

l -

l o

?

j i ! -

y =ammungsummeness i

l

~, ..

a-- ,-.-

_. __ m s _ ...

Z",~.-~A*

m -r - .= - n.n -._. _

M"ll'Ew- M C.~4= -e

,# r r ,- .1J.h~ , ; C. ,"C i,".; . i LJi' ,% -m ' ' =*. . e

L r. =."_7""_'_-

m-

- u w e g g s4 w - a. r -

r +www -

__j__2._g_-__A__7_____7v r -. w-- rr- --

_ __ ___m mes _2 _ ~ = _

S p _-_-r-u ._1_.. 7____A -_- _ _e--

_ __ --3^ ^e_-- - __ _ _

q e :^._&_--^r_-~---- -

' L'"~'~i'-2-- ._ .- - _ . - - - _ - _ ^^~~ -

'-~---^h:___y~~^^-^=*-'-~~~=-~~--

t -

$ ' [ '*, O { ' e *1, m -~~*um., 7. ;, ,m s- -

- * =- _ _7-* - -t8-I n,',

,_- -" ___ *_;QQ3, V* , ,,-ym g , ., , .

., a ,. . . - - - *.-A_ ' _ _ . - _ . __ _, __ ' _ _ _

1

.J,""-_. -- S m.__ at _ - 1***

4:.:-n.r.

- -2. _._ . .

L

% : a x _x u = 1 = -- = = == = ==13

=

-= x=m=___ __ - - :-:= ,=.-2 _-

=2-- _ = - ._-_----a -

M "

y

. 3 l -

. .- , , .. c .. -...n -., n . a . . . - -= . , w :__..

-e

- - :._a. m. .._ -_~ : . -*

u 3*

. .. . . . .v..-~,-..-

. . . _.._:_.a__ _

"* ' **4'W**# &

u_.~_ ::. :. :. .

y h

._"8"*".'..""."**.*."*#.__.***^#'.**m*W"""."""_a"'.."&.

_ Ax. . 4 ,__ u 3 _ . . __ - . . - - , - -

. ' _ . ' - - c'..'~""a.-_i_=-i

_z-,,_,."_'"'

m.-_ gr ,1-y -_

t -v _ . _ . ____

- ,--- r- # , - =_ y :

- r"_"- _ _ _'

,,, ,, Z_7_2. M _ N ^ _ -'-

= _

C C f bX - - [_.-- ~

__ - - - y- _^'-~'.- M..__-__-Z

~~ [ .

x_

___[ _OC_

ug - _ _ _

Q c ; .: v m

. . - . ., . ~r... .

- - - ' - ; ^.' n u :.

..- .= . = _ _ _

n . '

& _a

- ~--

p-nr

% = -

_x n -- . , _, - ,-,c .- - . _ - ,t-

,_ 1

. a .

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

,1- - -

S

_, --- - -- E, 7y _ - - - , - -g __-- '__g_-

E_7"--_

_[ -_-[---

~_ _ = ~ _ - = = __ ----- -_- -. ___ __= ---_x__:_-_-_--_v._-.-._=-------_=_-__x.=r--

-.- - - - - - ,- - _ - ~=:-_-----_-.-'=-::==-_--~,-

'35 c.

ae 5 . .-

N.

M e

4

_-'w--' 2-* _-r _ c .: . _ _ h ahv ~ e- ._ 7 e .a m - - ' r.,en, m.r.g,e,_ _ y . . -

C ~ 'C-l .. . . .el . . _ . . ~ ~ " ' M ,_v l *

^ Ma 2. '." - .

w. m. ., we- me.:<_

1

- . < u-

,=- . .

__--_._2

v -

i 4- --

an.r . _- _ su. m w- = , -

r,-

ru m -

f-w x.

J re , .---

2._

=

--e-e.rw,x n a z__.mm

- -_, - .% -- r,. v.

- =

r

=~,1_m

,< ... .w____.._.rz__-

m,_ .z-- _-_ - _ - -

e __b -~ b k - _ [E -- - - E ' F

-~

i. --[ -

T P ."".' C : :- . . . ~ =C'">TT5 Y'*C.' N = 2 EUp"i:.G nc fP . .'* sc : -

, '*"L e I ',; i .," =-- J,_g--%-gM E!P *M"ty:j_gg _ r 1

- qy- g y ,

L*=_ -4. .= , _.:L;

, _ -. . _ . --. ~~~a""" _ _ .

1 i.

~

.d o-39% 4 a e 4 m e Am a j ya% 4 & e M N mm

R Q &g a e m a a. , e n .

e *

, _ , _ . . .- . .=

i 7- _ , , ,

.o a3 I

4 g .

I43

. . 4k A

3 . ". .!

%c .

$S M omu

=*

t

, O

. % q ?.

8 M m

& 3a* Bl } #'

w.

I k 2 g.

gy - - .

. . . . , 1

. se aus a an* a a N SS 3 $h e t . aC D # .

I O

e

. = 1

. _ ; = 4

. - , e He i

s 5 g

tb -

M em 4

. - e WG

. .. 5 -* h* A .

5

. == . g *g 5" A

e. Ma S E h !

. g a gE S W ftw "b' *

>s

.- M e.s S J. --

,=

. . , 2 -

- - D. .h , . .

9, . ;

. e s

-! .. g . #b g

='*

4 - .E., g ._

j ge .J ,

_ , a.s 8-N .

/

w. * . ' / .

3 7 A

f 6 > =

)

3 S

1.

m .

S S

- 3"1 3

$ a le -

_ e

g. _D .

.. G n1 q -

% b ~%

V

. l .

4 h a e 92

.- O u "g"' .I.

Ea c" " g = . --

ym 3 C4 O= W EE

. .

E d,

. i m .q .D. E T S --

g3 ed m i= E E l

. ,l

v. w . .

. e . .

6 em .em. .e. ei.e M*

' ' ~

m,, . , . _ - . ~ - - , = -

_- - .- , ~ , . , . . . - - , , c +- -- -.- - - - . , - --

-=-y

1

, , , , EP/0/5/1009/08 )

Enclosure 5.8 '

Page 1 of 7

)

_'N

( ESTDfATED IZAKAGE HATES IN C1SE OF CONnDRfENT FAII.3E i AT IITIER QCONIE NUCI.ZAR STATION OR McGUIRE NUCI.ZAR STATION In any accident situation involving a release of fission product activity to

, the cone =4a==at atmosphers, there are two major concerns: l

1. Being able to predict pocancial offsita doses in the event containment does fail. The Raw w y Manages may base a decision to evacuate or not on the po* = H =1 effect to the public without any indication of offsite ralsases. -

1. If cone =4n==nt does fail, it is necessare to estimata actual release rates in order to calculata actual offsita doses.

To do either of the above requires an estimata of CEi leakage ratas versus siza for a range of J:entainment pressures. In order to calenlata now, either instantaneous or on a time basis, several basic assumptions must be made concerning the process. These assumptions will cand to give the most conservative answer.

To calculata instantaneous flow through a short pipe, as in Oconee's case, or through a \" thich "orifica", as in McGuire's case, several assumptions are required. These assumptions, with,an explanation, are:

1. Fullv Turbulent now - In Oconee's case, since the piperfriction factor secreases with ing:is.asiz:3, v.slacity, the most rasazietive case -

is fully.turbulant flow. In McGuire's case, the nowgcoEfficient is most restrictive in the fully unrbalant region.

2. Mnemum Exceeted Temperature - In both cases, since camperature is the i

sole factor affecting density of air, at a given pressure, a max 2. mum tamperatura should be assumed. Since density decreases with increasing

] tempersture, the higher the camperature the higher the flow.

3. 957. Relative Humiditv .In both cases since the highest flow rata is ootained wita tan lowest specific gravity, the lowest specific gravity

' should be assumed. Since the specific gravity of an air-water vapor is most closely approximated by the ratio of the density of water vapor to that of air, the higher the relative humidity the lower the specific gravity.

t I

In addition. to the p.,--:+%= assumptions, several other assumptions must be made before one can calculate time dependant flow. These assumptions, with an explanation are:

1. Uniform - Stata. Uniform - How Process - This type process applies in 4

born crses and Lt is based on una following:

A. The control volume remains constant relative to the coor:iinata frame.

s 3. The state of ,.he mass within the control volume :nay change with time, but at any instant of time the state is uniforn throughout the entire control volume.

S

. . , . + ~ ~

--3--- m--.. ---- - - - - w- -

_---r '

a j

2 EP/0/B/1009/08 .

l , Enclosure 5.8 Page 2 of 7 j

w C. The state of the mass crossing each of the areas of flow on tha control surface is constant with time although the mass flow ratas may be time varying.

t 2. Rapture Occurs At End of Accident - In both cases this is assumed in order to have a basis for initial conditions inside containment, i.e.,

h an= pressure and temperature and negligible heat input.

3. Process occurs AA4=batically - In both cases, since it was previously l assumed that no neat would be added daring the releas,e, the adiabatic j assumption is the most limiting case. This is shown by the Second I.aw l of h=~'ynamics for a control volume, which for this case is: .

[2; sg -m y s]g

+ I s, s, a f* dt.

Considering the a.hoicas, either Q,, = 0 or Q < 0. If the lat ar is i assumed, it would cand to decreas4*m'

which vodll'not be as limiting as 1

Q c.v. = 0.

i i 4.. Flow occurs Isentronically - In both cases since frictional effects are

} negligible and it is being assumed no heat transfer occurs, it is "

) intuitively obvious that flow can be assumed isentropic.

i -

5. The litzture Behaves As An Ideal Gas In both cases this can be assumed i becausa at low pressure, regarclass of tasperstarc, the Ideal Gas Law j

yields good accuracy. :

i h r i

! Actached are graphs that illustrata the estimated laskage da as for Ocones i

and McGu1=e. In Oconee's case the flow versus time graph illustratas the

! ttas dependent flow that would occur if the cone =4-e was pressurized i to 60 psig at he tina of the failure. Ir. McGuire's case the flow

! versus tina graph illustrates the tima dependent flow that would occur if l

the come=4==nc was pressurized, to 15 psig at the time of the failure.

j In both cases the opening sizes are that of Schedula 40 pipe.

I i

l I

I l

s 6

l

EP/0/B/1009/08 Enclosure 5.8 1

Page 3 of 7 s

4 x EQUATIONS YOR McGUIRE

! ( i t t Instantanects now q'* 3678 Td 2 l 39. .

j, (Refer to Crane Tech. Paper M10)

Q%

i b re: q',= Standard cubic feet per minute

! T = Net expansion factor (from Table A-21) 1 d = Inside pipe disseter, inches C = l l How coefficient (from Table A-20) '

l

F'=

t Absolute pressure inside con *M - t, psia -

},

TI = Absolute temperature, 'R

, 5 5

= Specific gravity of the gas

! s=1- .37803 P 1

39 5 p.

1 I ~

l Eg = Relative humidity -

,/

l P37 = Saturated vapor pressure of steam at t, conditions [

j Assumptions:

P 1

{ 1. In der =*ag C, it is assumed there exists fully turbulent flow:

i j n ow Versus Time P7 = mRT R = 53.34 Pvk = Constaan k = 1. 4-I TV = Constant (Refer to Crane Tack Paper M10) W = .525 Td2 g l

.I N N l'

Were: W = Ifasa flow rate lha/sec i Y = Net. expansion factor (from Table A-11)

<t = Inside pipe diameter, inches C = now coeffient (from Table A-44) v = Specific volume Assumptior. - The mass flov rate remains constant with a short interval of time.

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, HP/0/B/1009/0-Enclosure 5.S l Page 1 of 1 OPERATOR AID COMPUTER (TECH SPECS 04)

USER DOCUME3TATION

1) ' Tech Specs 04' can be accessed thru OAC terminals in either the 1)

Te-64 e= 1 Support Cancer (TSC) or the 2) Computer Room.

i There are OAC ta=4a=1= for both Units 1 and 2. Be certain to use the OAC terminal for the appropriate Unic.

All necessary data on the ' Tech Specs 04' computer printout will be under the ' Environmental Systema' heading.

2) Procedure .

a) Check to see if the READT key on the princar is fully ON/0FP LINE illuminated. If not fully illuminated, press the key one ti:me and release.

b) Press the Tech Soecs key of the OAC terminald F(Kay will illuminata).

c}- Type 0 4 using the blue numeric keys of the OAC terminal.

d) Press the Print key of the OAC terminal. (Kay will 411,-4 .g.) ,

e) Press the Enter key of the OAC terminal. (Kay will

< ti,-4..te) ,

Upon pressing Enter, printer will print data.

f) When printer stops, press the READY key on the printer to ON/0FF LINE 411'=4"=ta only the " READY" portion of the key. .

s g) Press the TOP OF FORM kay on the princar three (3) times to advance paper. Tear off data sheet.

%.- ~

HP/0/B/1009/08

, Enclosure 5.10 Page 1,of.4 EP1P08 USER DOCUMENTATION -

~

1.0 Purpose This program is designed to calculate potential offsite dose in the event of a reactor coolant leak inside containment.

2.0 Procedure 2.1 All computer responses will be shown inside double bold lines.

User responses will be shown underlined. The + character signifies a carriage return (CTRL S pressed simultaneously on the Teletype term 4 = 1 and the return key used on the Texas Instruments high speed terminal.) i 2.2 VAX Logon procedure .

2.2.1 Dial (Plant Ext) or (Microwave line) and make connection between terminal and computer.

. 2.2.2 Type CDc7320 +

2.2.3 Enter password DOSE +

2.3 When LOGON is complete, type : EPIP08 +

I 2.4 VAX will respond:- j ENTER TIME OF TRIP (MM.DD,YY,HHSS) l' ,

?

Enter the date and time of reactor trip / shutdown in formac

shown.

EnMPLE: 03.15.81.0800 +

2.5 VAI will respond:

ENTER FRESENT DAIE AND TIME 7

Enter the present date and time in the same format as 2.4 2.6 VAX will respond:

ENTER RI. BLDG. DOSE RATE (R/HR)

? .

Enter Reactor Building dose rate in R/hr as determined from Reactor Building monitor or alternative methods described in HP/0/B/1009/02.

8 EIAMPLE: 3.4E3 +

~, J l

L I

i

.,4.- p.e . ep ae esame-e* . *,*m=****gy**=t

r*w*****'******"*""*""***8***'* * *****""***' ' * * *N**** ** ** ~ '

a. a .

. 1 i

~ * #

--' HP/0/3/1009/08 4 Enclosure 5.10 Page 2 of 4 l

2.7 VAX will respond:

ENTER WIND SPEED (MPH), WIND DIRECTION (DEG. FROM NORTH) 1 Enter wind speed in miles per hour (use 15 min. average or standard National Weather Service observation) and wind direction (direction from which wind is coming) in degrees from North. (Use 9.9 as directly North).

RYAMPLE: 4.@,125.$ +

2.8 VAX will respond:

IS THIS NWS DATA (NWS) OR PLANT DATA (MNS)

If National Weather Service temperature differential is used, '

enter NUS + and proceed to 2.10. If plant temperature differencial is used, enter MNS + and proceed to 2.9.

-l 2.9 VAX will respond: -

so, ENTER TEMP DIFFERENTIAL (DEG'.C.)

?

Enter ths temperature differential in degrees Centigrade.

EIAMPLE: -0.4 4 2.10 VAX will respond:

USE DESIGN LEAK RATE (DLR) OR KNOWN LEAK RATE (KLR)

If design leak rate is used, enter DLR + and proceed to 2.12.

If leak rate other than design is used, enter KLR + and proceed to 2.11.

2.11 VAI will respond:

ENIER KNOWN LEAK 2 ATE (ML/HR) i

?

Enter the leak rate in ML/HR.

S'YAMPLE: 1.4E4 +

2.12 VAX will respond:

l 1

l

. _ . . - . . - _ . , . . - - - ~.-S...--, - , --.,-.-- .- ..r~, . - - . . . , - - - . - . ~ ~ - - - - .. . --. - - - -.. -

v

~

~ ~ '

EP/0/3/1009/08 Enclosure 5.10

\

Page 3 of 4 i

I WHEN READY FOR PRINTOUT,

, ADVANCE TO TOP OF PAGE i . AND ErfER 'Go' Advance to top of page and enter g t 2.13 VAX will print, and the program will end, ready for next execution.

e D

}s f f 4

r

't J

e

_,s,e , e e no w- .- w -mme*y- e,a==nem^9 % ~ ' * * * ^ * ' e '

%'**'**** **% ***H'"'**~ * ~ ~ ~ ' ' * ' * ' "

1**"*

EP/0/3/1009/08 e

. F.nclosure 5.10

. Page ,4,, of ,4, i .

( *l 0

4 a

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= 3 == mm -

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= 4 = J & la.

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== >= 4 5 E M SJ X og 4 m 4 w 3w

== m o Lad >= w 3C 24 l

@ w 4 6 4 Lad => a

. 6 O >= Oe ab B == 1&B 28 )

I o OE O .a us a a 34 ew ,Oa as l W O UD ** A 3 b 2 3 mw *

O. 2 2 C

= = mas == x == w a

>= S' A G3 m 3 tr1 W. >= U3

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= = = = === ba.d es = e- g >= 0 U3 se e gag g ik 2 ME M X e X

09 X X O U3 .a

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NC6ulkE NUCLEAR SI4Tl0N .- .. .

SFf8815 606E P40 MCIIONS j NP/4/8/1049/A) ...*

. EELOSUAE 5.11 t

! PLilNE bikECil0Ws 345.0 M6kEEE LE4K R41Es 2 4M e64 E /Ils NINb6tEEDs 46 Iltli kg DLD4 DSSE Reigt 3.40E*43 g/ lit i MLl4 IENfs -0 4 M4 C. N0btE SAS DOSE R41Es 4 44E*44 R/ lit letIK petE SAIEs 4.StE645 R/NR i

]i IINE SF F.lf t 4/l5/86 tot AfDs 3. Alf te2 UCI-ilEV/itL-tig ACbFs 5.41Et44 KI-il3EN/ill.-PCI 1 IINE OF CALCl 1/14/84 1840 1

't-

.t .

d SIE1ANCE $44E B4TE Al POSER 4[E,AT 2IIR54H -

ti b0UNUINb F4ESENI'llM FRESENI IINF t 2 il8NRS CSINilIINENI J INILESI IREN/Niti ikEN/likt itEN) ,

4 I

/ l'ROMCIED llHOLE 4.5 l.75E-43 1.7BE-43 3.4&E-43 -

I 4 i A.45E-44 4.2tE-44 - 1,27E-43 2 3.24E-44 2.2K-04 4.4&E-94 4

S 3 1.24E-34 1.hE-44 2. E-44 4 4 7.84E-45 &< -05 . 5E-44 i 5 5.5M-45 5. E 5 8.etE-44 -

l ; & 4 24E-45 4. E-6 8.37E-45

, ; 7 3.37E-45 3 SE-45 4.45E-45 j'

8 3 7?E-45 .74E-45 5.4&E-45 9 2.31E M ,

. 25E-45 4.5M-45 ,

j to 1.tBE- 1. 3E-45 3.flE-45 l

4.5 42~

Pku.lECIED INV4088 9.44E-41 g l i i I 3 6 -41 3.48E-el ]h.flEtte 2E-4)

, ; 2 . l. 4E-41 1.22E-el J.4&E-$f i 3 7 . E-42 4.78E-42 1.35E-44 I

. 4 <

p E-42 4.22E-42 4tSM-42 l i

i 5 .44E-42 2.98E-42 4.42E-42 i & 2.3M-42 2.2fE-42 4. ale-42

-) 7 1 8M-42 1.8tE-42 3.4&E-42 i 8 1 52E-42 1.4tE-42 3.etE-42 i f 1.27E-02 l.24E-42 2.5tE-42 i le 1.0fE-42 1.07E-02 2.14E-42 NEABf

,..m . . .,

7

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}

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L Forn SPD-1002-1

, DUKE POWER COMPANY (1) ID No: HP/0/B/1009/09 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated (2) STATION: McGuire Nuclear Station i

Release of Radioactive Materials Through Unit Vent (3) PROCEDURE TITLE:

Exceeding Technical Specifications (4) PREPARED BY: [M A. /N Y DATE: 7 dCet 93 t

(5) REVIEWED BY:O [. - DATE: / he/P3 y i Cross-Disciplinary Review By: N/RN 8/,

0 -

(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: Date:

(7) APPROVED BY: /-a .e3 M9 b.sf/ Date: // Mf 6

(8) MISCELLANEOUS:

Reviewed / Approved By: ,

Date:

Reviewed / Approved By: Date:

1 9 - *+**--p : . . _ mewey == w e e eveo >= .. ;mq,s eg w- e= eme . % p., - . , e g e; ww w weg, , . . ; ,. _ , , , . , ,,,,

I

^

HP/0/B/1009/09 l DUKE POWER COMPANY McGUIRE NUCLEAR STATION RELEASE OF RADIOACTIVE MATRE M A THROUGE UNIT VENT EXCEEDING TECHNICAL SPECIFICATIONS 1.0 Purpose This procedure describes the method for calculating the potential offsite dose race and dose following a release of radioactive

, asterials through the unit vent. In addition, this procedure can

- provide warning message information to be given to state / local agencies.

2.0 References +

2.1 Station Health Physics Mamsm1, Section 18.2; Environmental Monitoring for Emergency Conditions.

2.2 HP/0/B/1009/07, Unic Vent / Waste Effluents F1.ow Data Collection.

2.3 10CPR20, Appendiz B, Tabis II. .

2.4 McGuire System Descriptions. I 2.5 Unit Data Book j s

2.6 NRC Regulatory Guide 1.4 i

1 2.7 Offsite Dose Calculation Manual (ODCM) .

2.8 HP/0/B/1009/05, FirstResponseEvaluationof[ ctor Coolant Laak Inside Contaf== ant.

3.0 Limits and Precautions l 3.1 This procedure is being used in an emergency situation which could result in evacuation of areas surrounding the planc.

The procedure shall be fully understood and a=t~1=tions shall I i

be done carefully and accurately. ;

3.2 This procedura is written for use under abnormal conditions !

I which could involve extremely high radiation levels. Only the i Station Health Physicist or his designee shonid authorize the use of this procedure when needed and should provide ,

appropriate surveil. Lance and control of people taking samples. I 3.3 Check that the counting equipment to be used has been i calibrated and daily response checks have been performed.

3.4 Individuals collecting the samples should be aware of the possibility of airttorne cont ==4nscion and high radiation

.. levels in sampling areas. Use protective clothing, gloves, l respiratory protective equipment, portable shielding, high range dosimeters, and survey instruments as determined by, Health Physics.

" ' ' ~

,y, e.-- :,3- r .a .= ' . v . m w 5

.+..a.-e.-ggwey*-e*e=w**-- e *-e ' h ad ~ " * * * * * ' * " " * * ' * * ' " ^ ' ' * ~ ' ' # * * ' ' * '

%-- ,g

-,, ,--,.__% , -_im -p., , - , ,- ,.-*--y

Page 2 3.5 If action is taken in the 4 - 10 mile radius area per reference 2.8. then wind direction should be rechecked every

(

15 minutes to ensure that additional sectors have not been affected. Once a sector has been added to the list, it cannot be removed from the list.

3.6 Projected doses should be compared to the Environmental I Protection Agency Protective Action Guides to determine levels of protec.tive action.

4.0 Procedure 4.1 Acquire the following information and record on Enclosure 5.2 and/or 5.3.

NOTE 1: Some of the following information can be obtained from the ' Tech Specs 04' program of the operator Aid Computer (OAC). All information available in ' Tech Specs 04' will be denoted in the following procedure by a '(TS)' to the left of the section number. See Raelnaure 5.4 for steps to access ' Tech Specs 04'.

NOTE 2: S.andard warning message information to be given to state / local agencies will be denoted in the -

, .i following procedure by a '(WM)' to the ft of the

r section number. g4 NorE 3: Meteorological data should be obtained in the order of preference listed in Enclosure 5.2.

NOTE 4: Use 15 minute averages for all meteorological data.

() 4.1.1 Wind direction recorded in degrees from North (upper tower). Lower tower wind direction should be used only if upper tower data is unavailable.

I*) 4.1.2 Lower tower wind speed (MPH) (W). Upper tower wind direction should be used only if lower tower data is '

unavailable. !

4.1.3 Vertical temperature gradient or AT*C (lower to upper tower) from the -4 to +8 scale on the ,

meteorological temperature strip charr recorder. ,

NOTE 1: This information is used along with Table a on Enclosure 5.4 and map provided in Technical Support Center (TSC) to l determine areas affected by release.

P 9

-- -... _. ., _ r , ~.-......-.,_-.-v,,...---,. c., - ..-.,,, m- . . - .. -- ;,,. ..,, ., .-. . ,

Page 3 m NOTE 2: Plume direction is 180* opposite wind T

l direction.

(*) 4.1.4 Stability class (A.B.C.D.E.F. or G) from Table I (Enclosure 5.1).

I (*) Ambient air temperature (*C). Record in *F whIre:

4.1.5

F = 9/5s'c + 32.

(*) 4.1.6 Precipitation (TS) 4.1.7 Discharge flow rate (F) from unit vent which is obtained by multiplying the fractional flow from coralizar by 170,500 to get flow in CFM. (i.e. 951 flow = 0.95 fractional flow).

NOTE 1: If the unit vent flow toratfrer is inoperable, flow can be determined by reference 2.2.

(E) NOTE 2: Release height of unit vent is 142 feet above yard elevation.

NOTE: Information in sections 4.1.8, 4.1.9, and 4.1.10 is

not normally used. It is availa: ale if needed for working with outside agencies. j, -

'* e ! !

d 4.1.8 Discharge concentrations (CNG *" I) r a Health Physics sampling of unit vent; or DIF data if sample results are not available, as follows: . j If DtF36(H) <100 cpa, C

NG

= DtF36(L) cpm x 3.8 E-8 or if EMF 36(H) >100 cpa, , l Cyg = EMF 36(H) cpu x 2 E-4 C7 = EMF 37 A cps /A time x 2.34 E-10 Where:

C,g = noble gas discharge concentration in uC1/mi 3.8 E-8 = EMF 36 (L) correlation factor in g uC1/al/cym from reference 2.5 2 E-4 = EM'36 (H) correlation factor in l uC1/ml/cym from reference 2.5 l 2.34 E-10 = EMF 37 correlation factor in uCi/ml/ cpu / min from reference 2.5 s

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

---~~..----e-

1 Page 4

- N ) 4.1.9 Calculate radiological release rate (Q) in Ci/sec using the following formula:

Q,, - Cg, x r x 4.72 E-4 Q7 =C x F x 4.72 E4 7

Q = (CNG + C 7 ) x F x 4.72 E-4 Wherei QNG = noble gas radiological release rate in Ci/sec

' Q = I-131 equiv radiological release rate in Ci/sec 7

Q = radiological release rate in C1/sec 4.72 E-4 = 2.83 E4 cm 8

/ft 8 x 1,67 E-2 min /sec x IE-6 Ci/pc1 .

I All other variables same as previously stated.

) 4.1.10 Calculate dose conversion factors in R/hr/C1/m 8 for whole body and child thyroid' using the following

, ~

~

formulas: /,

r r

-. O DCFg = 0.5 x 3.7 E10 x 3600 x E 1.3E3 x 100 x 6.25E5 DCFg = 820 x E Where:

DCFg = Whole body dose conversion factor in

)

R/hr/Ci/m8 l 0.5 = conversion from infinite cloud to !

semi-infinite cloud whole body dose !

I = average Mev/ dis from Count Roca data

?

_ i NOTE: If E cannot be obtained from sample results, the following values should be j used.

s

. - i ;

- -e=m ,e + . . - . .,,m

- ,_v

Page 5 N

Hours from Trip E in Nev/ dis

< 12 .

0.40 12 - 48 0.20

> 48 0.10 1.3 E3 = density of air in g/m 8 Conversion factors

3.7 E10 dis /sec

C1

. 3600 sec/hr 100 erg /g

rad 6.25E5 Mav/ erg DCFg = 4.39E-3 x IE12 x IE-3 x 0.422 DCFg = 1.85 E6 Where:

DCFg = child thyroid dose conversion factor in R/hr/Ci/a84.39E-3 = inhalation dose '

factor for child thyroid in ares /pci, from reference 2.7 0.422 = child breaching race in m3/hr, from reference 2.7 /,

r e Conversion " factors: //

LE12 pCi/Ci 1E-3 rad /arad 4.1.11 Two (2) hour relative concentration (CH) in sph

f sec/a8 from Table I (Enclosure 5.1) at the site boundary (0.5), 2, 5, and 10 mile points. Record on '

Table I and Table II of Enclosure '5.3. I I 4.1.12 Determine chitri thyroid dose race using one of the {

following for=n1==: }

bg = 874 x F x g x 1 x CH

, W NOTE: rstm.1=tions are not required after discharge concentration is less than f, 10CFR20, Appendix B. Table II (I-131, 1E-10 uCi/al; Ie-133, 3E-4 uCi/al Where:

bg = child thyroid dose rate in Ram /hr.

874 = 0.422 d x 4.39E-3 mrem x LE6 pCi x 1E-3 rem x 472 al/sec/CTM hr pCi uC1 mren

, [ ,' ,** gM ,eN8- E E e

Page 6

-s F = discharge flow rate in CFM (section 4.1.7) -

C7 = I-131 equiv. discharge concentration in uCi/ml (section 4.1.8)

W = windspeed in sph (section 4.1.2)

CH = Two (2) hour relative concentration in sph

sec/a8 (section 4.1.11)

SE NOTE: If EMF readings are being used, determine child thyroid dose rate using the fo11owing farmula:

D = 2E-7 x EMF 37acpm x ' x 1 x G atine Y Where:

2E-7 = 874 rem *m1*m3* min x 2.34 E-10 ucI*nin 3 al

cpm uC1*hr*ft *see EMF 37acom = change in cpm per change in time (min) -

Atime NOTE: If ' Tech Specs 04' data is used, determine ,

s ,

a cya from two runs of the program 5 minutes apart (A Time = 5 es)'. 1 r

All other variables same as previoupil stated.

4.1.11.1 Using one of the above equations, determine the child thyroid dose rate at ;

the site boundary (0.5), 2, 5, and 10 mile i points. f NOTE: This can be rapidly accomplished r i

by storing in calculator memory ,'

the result of all numbers, excepting CH, and then recalling this number to multiply by each !

t CH value for the 0.5, 2, 5, and 10 mile points (as shown on [

Tabla I on Enclosure 5.3).

I 4.1.13 Determine child thyroid dose at the site boundary (0.5), 2, 5, and 10 nile points by multiplying the dose rates at ehese points (as done in section 4.1.11.1 and shovu on Table I on Enclosure 5.3) by the dose assessment period (in hours).

1 l

I Page 7 .

j 'O NOTE: CH values bascd on a two (2) hour dose assessment period.

(WM) 4.1.14 Determine whole body gsama dose rate using one of

-se following for=ilma:

i bg

= 0.387 z F x CNG *- *hxCH Where:

i bg - Whole body gassa dose rate in Rem /hr.

0.387 = 820 R*al' dis x 4.72E-4 38* min hr*uci'May ft3 *sec I = average May/ dis from Count Room data

.E NOTE: If E cannot be obeninad from sample l 3

results, the following values should be used.

Hours from Trip I in Mov/ dis f

< 12 0.40 : I

), i 12 - 48 0.20g e

> 48 0.10 ?

All other variables same as previously stated. :

i E I NOTE: If EMF readings are being used, determine l whole body dose rate using one of the following formulas:

If EMF 36(H) < 100 cpm.

bg= 1.43E-8 x EMF 36(L) cpu z F x I x 1 x CE W

Where: !

1.471-8 = 0.387 R*a8 'al* dis

min x 3.8E-8 uCi/al/cys l

hr'sec*uci'Mav'ft 8 -

1 All other variables same as previously stated. !

Or if EMF 36(H) > 100 cpa, bg = 7.74E-5 x EMF 36(H) cpm x F z; I z 1 x CH 4 ,

W Where:

i i

-- - 7; - g

Page 8 7.74E-5 = 0.387 1"m8 'al* dis *ain x 2E-4 uC1/al/cys l

I D '

hr'sec*uci'Mov'ft 8

(

~

All other variables same as previously stated.

!- 4.1.13.1 Using one of the above equations, determine the whole body dose rate at the site boundary (0.5), 2, 5, and 10 mile points.

NOTE: This can be rapidly accomplished by storing in calculator memory the result of all numbers, excepting CH, and then recalling

~

this number to multiply by each !

G value for the 0.5, 2, 5, and !

l 10 mile points (as shown on l Table II on Enclosure 5.3).

I ) 4.1.15 Determine whole body gamma dose at the site boundary ,

[

(0.5), 2, 5, and 10 mile points by multiplying the ,

dose rates at these points (as done in section 4.1.13.1 and shown on Table II of Enclosure 5.3) by the dose assessment period (in hour

~

EDII: CH values based on a twovi(2) hour dose i assessment period. ;

4.1 Determine potentially affected zones based on wind direction ;

using the table on Enclosure 5.4 and record on Enclosure 5.4. lj, 4.3 Determine levels of protective action by comparing projected !

doses to EPA Protective Action Guides (page 2 of 3 on !

l Enclosure 5.4) and record on Enclosure 5.4. 'i I 4.4 Determine if non-stagnating meteorological conditions exist by l

[ observing meteorological strip chart data. If: ,,

(1) Instantaneous wind direction has not varied over 90* t ,

[

in the past two (2) bours, and l (2) Instantaneous wind speed has not fallen below 10 MPE l in the past two (2) hours, then non-stagnating conditions exist. :

1 Record result on page 2 of 2 of Enclosure 5.4.

l 4.5 Check results and inform Emergency Coordinator of your l

recommendations. !

. l

.s 7

. I

.: . .=- -- _ . - - . -

6

a -

i

! Pge 9 i

N 4.6 Whenever possible, utilize environmental data in comparison

\ with calculated results to better determine plume dispersions.

l

! Record environmental data on enclosure 5.2 when available. )

1 i NOTE: Depending on meteorologic conditions, field i '

monitoring teams may experience difficulty in l finding the plume. Therefore, negative field results do not necessarily mean that radioactivity is noc being released.

i

! 4.7 t'=le=1sted results should be compared with those from the Crisis Management Center if accessible. Any discrepancias

, should be resolved through ree=1ent=tions and calculation step comparisons.

4.8 Historical data shall be retained so that offsite dose trends.

can be analyzed.

! 4.9 Insure that enclosure 5.2, 5.3, and 5.4 are properly completed

) and results presented to Station Health Physicist or his -

! designes.

4.10 Actual field measurements of whole body doses will be compared; l

j

^

to whole body dose projections by the Data Evaluation Coordinator. / , i 1

5.0 Enclosures [

5.1 Table a. Two Hour Relative Concentration

5.2 Unit Vent Release Data Sheet i i 5.3 Manual Calculation Worksheet i f 5.4 Table of Potentially Affected Zones }

i 5.5 OAC (Tech Specs 04) User Documentation I

i

, i

! 1 I

l i

?

[ }

o

'- ,' 6

"'- ~

W

L. )

Enclosure 5.1 HP/0/B/1009/09 TABLE 1 2 HOUR RELATIVE CONCENTRATION (Cil)

Stability Distance (in miles)

Temp. Diff(*C) Class 0.5 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0

1. < -0.6 A 1,4E-5 1.2E-6 5.9E-7 4.!E-7 3.2E-7 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7 i 2. -0.5 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.lE-6 8.3E-7 7.8E-7

3. -0.4 to -0.2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6

4. -0.1 to +0.4 E 6.9E-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.lE-5 9.7E-6 ,

~

5. +0.5 to +1.2 F 1.!E-3 5.lE-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.lE-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5

6. > +1.3 G 1.8E-3 1.lE-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 s

The temperatura differential is the difference in temperature between the upper and lower temperature sensors and la in degrees centrigrade.

These values are site-specific for McGuire Nuclear Station.

Y e

i i, . . . . - . . . ... .. ..._.___ _ _ _. . .

_________-______________i

HP/0/3/1009/09 Enclosure 5.2 Page 1 of 2 UNIT VENT RELEASE DATA SHEET '

Time of trip / shutdown hours after midnight. Date Time of a=1 -1= tion hours after midnight. Date !

Sample Time hours after midnight. Date (All asteorological data is 15 minute average.) '

Time (15 min. period anMng time) hours after midnight.

(WM) Wind direction 1) Upper tower degrees from North. ,

or 2) Lower tower degrees from North.

(WM) Wind Speed 1) Lower tower MPH or 2) Upper tower MPE AT 1) Lower to Upper tower *C l or 2) For 1000 - 1600 -0.2 *C or 3) For 1600 - 1000 +1.3 *C (WM) Stability Class (AT and Enc. 5.1)

(TS)(WM) Temperature *C ,

F = (9/5) (*C ) +32 = *F (WM) Precipitation (TS) Unic Vent Flav (F) CFM (Totalizar fraction x 170,500) '

(WM) Release Height = 142 ft.

ENDEN RELEASE CONCENTRATIONS (CNG and C7)

(Vent Samples) !

3 #

Gross Gas (Cg) uCi/al j, }

I-131 Equiv. (C 7) uCi/mi [ f Gas E May/ dis r

UNINOWN RELEASE CONCENTRATIONS (Cg and C7) [l (EMF Data) i !

IF EMF 36(H) < 100 cpa, Cg uC1/al = EMF 36 (L) cpu x 3.a E-8 uCi/al/cyn f i

Or if EMF 36(H) > 100 eps ;

-l Cg uC1/mi = EMF 36(H) cpm x 2 E-4 uC1/al/cpa ,i C uC1/al = EMF 37&cpa/Atime z 2.34E-10 uCi/mi 7

cpa/ min

' ~ .

T r

1

HP/0/B/1009/09 s

Enclosure 5.2 Page 2 of 2 Two (2) Hour Dose Commitment Iodine Noble Gas (Child Thyroid) (Whole Body) 0.5 mi. Ram 0.5 mi. ~

Ram 2 at. Ram 2 a1. Ram 5 mi. Ram 5 mi. Ram 10 mi. Ram 10 mi. Ram ENVIRONMENTAL DATA (If Available)

Point # Dose Rate Iodine Concentration i

Dose Assessor Date I

'~]' .

/ .s f.

g i

l 9

i I

?

i 2

f, Il l

J g

.=*e 4

= , - + .

- - - , , - - - - - -- g. ,- , - - - - - - o-,--,, , - - , e, , --n.. - - - r--- ,, e ,m o

v O

a m .

HP/0/B/1009/09 i T

'y , ,,

Enclosure 5.3 Page 1 of 3 MANUAL CALCULATION WORKSHEET l Radiological release rate (Q) 1 (W) .

Q3e C1/sec = CNC xF x 4.72E4 i

(W) .

!*** " x x . E4 I I

(

Q C1/sec = (gg + g) x F x 4.72 E4 I

Dose Conversion factors for whole body (DCFgg) and child thyroid (DCFg)

)

\

R/hr/C1/m3 = 820 x E

( }DCFC .

8

(

3 DCF CT

= 1.85E6 R/hr/C1/a8 f I.

i i I NOTE: The information on this page is not normally used. It is l*

! available if needed for working with outside agencies.

I 4

- I a

4 e

5 t

. 59 l ./ . n*

t 5

. _ . . _ __ __ J l

l y . HP/0/B/1009/09

, ,, Enclosure 5.3 l

. ., Page 2 of 3 s

Dose Rate and Dose Calculations Child Thyroid (Record all G values for 0.5, 2, 5, and 10 miles in Table I).

Dg = 874 x F xC x 1 xG 7

W i

Store in calculator memory If using EMF 37 reading, (use only if sample results are not available) i I

e Dg = 2E-7 x EMF 37acpu xF x 1 xG A Time f'

Stors in calculator memory :

J./ !

r t g Table I - Child Thyroid Dose Rate and Dosa a

(E) e l Stored Dosa Bata Time Dose g

Distance G Calc. Value (Rem / hour) Period (Rem) :

i S.B. 0.5 mi. x = x =

l 2 " " i

d. x = x =

5 d. x = x = 1 10 mi. x * =

x = l

I

i CE values based on a two (2) hour dose assessment period.

a whole Body (Record all m v=1na. for 0.5, 2, 5, and 10 miles in Tabla II). .

l 5 l

- i D

WB

= 0.387 x F xC *E

1

NC W

l

'

Stora in calculator memory ,

a-I

= 4 e

-W~ * * ~*

7~~

. .e. = . ..==.e,e=ea===g-+ --+ sus- e*=*& W g u e M * * * * - ' * * '

"W"'***T9"'4*- 7*+"'"'**~~

__ _ _ . .- ~ --., . - _ , , _ _- - , . , . , . - .

HP/0/B/1009/09

~~'s Enclosure 5.3 l Page 3 of 3 _ l NOTE: Use EMF 36 only if sample results are not available. Use E listed below.

If using EMF 36 reading and EMF 36(H) < 100 cym, Dg, = 1.47E-8 x EMF 36(Low) cpu xF zI x 1 xG j W l Store in calculator memory If using EMF 36 reading and EMF 36(H) > 100 cym, 4

s -

Dg3 = 7.74E-5 x EMF 36 (High) cya xF xE x 1 xG

- W Store in calculator memory Table II - Whole Body Dose Rate and Dose 1

(UM) Stored Dose Rate Time / , Dose ,

Distance CH Calc. Value (Rea/ hour) Periodg' ' (Rea)

S.B. 0.5 mi. x = x =

2 mi. x = x =

5 d. x = x = . l t

10 mi. x = x =

l 6

I CH values based on a two (2) hour dose assessment period. l NOTES: l

1) If Hi-Range EMF reads greater than 100 cya, use Hi-Range reading.

If Hi-Range EMF reads less than 100 cyu, use Lo-Range reading. j t

2) Use E data from sample results. If sample resulta are not l

available, use the following approximations: g

?

Time From Trip E

< 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.40 MeV/ dis.

12 - 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 0.20 MeV/ dis.

> 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 0.10 MeV/ dis.

l M

. . _ _ _ _ - . . ....__,..-.._.,..,___-y-__.-._;.m._,_,.,.. ._.c._,.~..... , . . .

- ~m-- --+,-,--e-- ,,,,---w.m m-,,- , - - --,+-wnm-, a +,w-r--.w--,----mw v+rg-ww-- - , - - - - w-r--w-w-em-

'. HP/0/3/1009/09 Enclosure 5.4 Page 1 of 3 Determine affected areas based on wind direction from the table below:

(degrees from 0-4 4 - 10 Wind Direction North) Mile Mile Recommendation Recommendation 0- 22.5 See Note i R,T,S E.F,U R,T,S,E,U,P 22.6 - 45.0 R.T.S,E.U,P 45.1 - 67.5 R,T S U,P.N,0 67.5 - 90.0 90.1 - 112.5 K,T,S,P,N,0 112.6 - 135.0 R P,N,0,L ,

135.1 - 157.5 I,P.N,0,L i

1 157.6 - 180.0 I,N,0,L.T.J H N .

'. 180.1 - 202.5 I,N.L.J,3,G 202.6 - 225.0 I,Y,4..J.H,G 225.1 - 247.5 b,'J,H,G,F 247.6 - 270.0 J H,G,F H.G,F,E i 270.1 - 292.5 i 292.6 - 315.0 C,F,E 'lt 315.1 - 337.5 G,F.E,U F.E U,5 337.6 - 359.9 f I

NOTE 1: Arena A,B.C.D,Q,7,M will be the rec ded areas if ,

I any action is enken in the 0 - 4 mile radius of the planc.

This reco - ndation is independent of wind direction. ,

6 l 9 i e i

..es 4

I e

- . - W

,7

.--.-.....y,... , , , - ~ . - ,m . - , ,5 7 c. 7 _ . m mr m y.m. .w r 3,r -. ,. . t . -., y m -7 l

sele /6hoos/o9 Enclosure 5.'l P$e.1 of 3 4 :

e i

n .

- 112 .2-

I r -

4 - .

. 1 = = _I g:is :-...

8 it

-i . 5:-8 v.e-

. sj:2 2 1 1 31.: _ :

_3

2 11 4 32: s ::L e. n s .3. : e: i 3

.I.al

13 3.

i:4 4rr . .

i - : =-

. 1 3. g1 2:s s : z _:.. g , v= =: .-

- us- 12:

- 3t !=:=3.

s- - _st-- a r 4

I = a2.g = ll .1 : art]. '

23 r !!s::.:= : 2 1

& 2

- s- ,_- i

5 1 3 t . a .gt I -

is 3 :2 4 1 -

s_:

!_.g1.

3, 3* 3 5 : *f.

. 5 j*$ g ::

g

, t

. !. . }2 g_ - -

4

- 1:: , :- _2

-: 3.4 :-

L.. !-

3i 5 .

2- si e- 3:3 : 1

- r- * ,> :* l 2r+*I :2:3 : .1 8 '

i

.f- I

az - : .r a

.-2 ._

g!I:

[2.

t-r 7:

1 -} %

s.-

j . _=sg. tg -

- r -[ g 1:. g- .. .8 I.

r 1_ ,

.s:- 1. _

gf

._ l=3: i _e i-4v.ge g == _I 2 - 1.13

=- r,21 t

.e 4

j 3

ital 3 It:1. 218 2.

l:e r- * - I

.- l =: 5 :.

z 1:13l. tz.1 t!e i

- i r4

.- :s.i

.' = _: :-[s 4_3_,e r 5 . , - i s.g:

_2 _::

t 1

s.

i :ais -

s 1-}a__t

__ < _.. v e __1: :

._4 I

i ai i la.--.la El ] 1 1_. al E=,

,l: ::*

. i_

t *

sr i,: :,

2

- . n.

i1 2-e 1 13 Ir 2z 11 1 -I 12 1

i !? v -- -a :}. *E * *1 s

- 11 - - -

il . . i.t. _at2 ,

1. 1, 1, ,,5 I. 1 ;

s !

1

- : . I -

i i

A-2 LE i

i; E i

EE i le il iE i

i in j!

l .

s u.

- i s 4 u7,

!j

! 1 I

E

- - N- . e gew ee *me ., .- .,,..g,, , , , , , , . . , ,

- 7*

~% HP/0/3/1009/09 Enclosure 5.4 Page 3 of 3

' 7) 0 - 4 miles Recommended Areas Recommended Population _

4 - 10 miles Recommended Areas Recommended Population Non-stagnating meteorological conditions do /do not exist.

Signature .

NOTE TO EMERGENCY COORDINATOR: +

If the release is projected to end within one.-half (h) hour, and non-stagnating meteorological conditions a h.cbider not recommending an evacuation if the plume M have left the Emergency Protection Zone (EPZ) before the population could evacuate. ,

i

% =. .

1 I

~

g

- . . . . , .. .-. -. . ,.-,.4..,_. %. , ,, . . . . ~ . . . , . - .. . _ . . . - g %. .. . .

-e__

l HP/0/B/1009/09 3 Enclosure 5.5 l Page 1 of 1 OPERATOR AID COMPUTER (TECH SPECS 04)

USER DOCUMENTATION l

1) ' Tech Specs 04' can be accessed thru OAC terminals in either the 1)

Technical Support Center (TSC) or the 2) Computer Room. I 1

There are OAC terminals for both Units 1 and 2. Be certain to use the OAC terminal for the appropriate Unit.

All necessary data on the ' Tech Specs 04' computer printout will be under the ' Environmental Systems' heading.

2) Procedure a) Check to see if the READY key on the printer is fully i ON/0FF LINE !

illuminated. If nor fully illuminated, press the key one time and release.

s b) Press the Tech Snees key of the OAC termin=1 g(,y will ,

illuminate).

A'f .

c) Type 0_4 using the blue numeric keys of the OAC terminal.

I d) Press the Print key of the OAC terminal. (Key will illuminate).

e) Press the Enter key of the OAC terminal. (Key will i

illuminate). l i

Upon pressing Enter, printer will prine data. .

f) When printer stops, press the READY key on the printer to ON/0FF LINE illuminate only the " READY" portion of the key.

g) Press the TOP OF FORM key on the printer three (3) timas to advance paper. "'aar off data sheet.

l

_ Form SPD-1002-1 DUKE POWER COMPANY (1) ID No: PT/0/A/4600/06 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: vec,4,. w,,r1.. , se.e<nn 1

(3) PROCEDURE TITLE: vv.vr4... .na nr411.

A.s l>

(4) PREPARED BY:

lW Mika Glover DATE: January 11. 1983 l

[ (5) REVIEWED BY: M & DATE: / /7 hJ g Cross-Disciplinary Review By: N/R: '. l L/

(6) TEMPORARY APPROVAL (IF NECESSARY):

, By: (SRO) Date:

By: Date:

(7) APPROVED BY: ~ Date: / */ 7 - O

/

i (8) MISCELLANEOUS:

i l

Reviewed / Approved By: Date:

i j

Reviewed / Approved By: Date:

I l

i-1 i

l PAGE OF l

x. -

4 PT/0/A/4600/06 PAGE 10F 5 3 '

i DUKE POWER COMPANY McGUIRE NUCLEAR STATION EXERCISES AND DRILLS' i

1.0 Purpose l.

l This procedura provides for periodic exerciscs/ drills to be conducted to evaluate major portions of the emergency response capability, and to develop and maintain key skills. Corrective actions and recommendations identified as a result of an exercise or drill will be corrected, and re-cords maintained in accordance with this procedure.

2.0 References

, 2.1 McGuire Nuclear Station Emergency Plan 3.0 Time Required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4.0 Prerequisite Tests .

! N/A 5.0 Test Equipment

, N/A 6.0 Limits and Precautions 6.1 Exercise scenario's should be varied from year to year to test emergency team response to many of the initiating conditions listed in

- procedures RP/0/A/5700/01, RP/0/A/5700/02, RP/0/A/5700/03, and RP/0/A/5700/04.

6.2 Exercises should be scheduled to start between 6:00 PM and midnight and another between midnight and 6:00 AM once every six years.

6.3 Drills should be conducted more frequently than exercises and shall be supervised and evaluated by a drill instructor.

7.0 Required Station Status N/A 8.0 Prerequisite System Conditions

! N/A 9.0 Test Method N/A

.a

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PT/0/A/4600/06 PAGE 2 0F 5 10.0 Data Required Enclosure 13.1 Exercise / Drill Format and Critique Findings Enclosure 13.2 Exercise / Drill, Controller / Evaluator Report j 11.0 Acceptance Criteria i 11.1 Completion of required exercise or drill and the subsequent critique.

12.0 Procedure 12.1 Exercises 12.1.1. A full-scale exercise is an event that tests the integrated capability and a major portion of the basic elements existing within emergency preparedness plans and organizations. A full-scale exercise shall include mobilization of state and local personnel and resources adequate to verify the capability to respond to an accident scenario requiring response. A full-scale exercise will be supervised and evaluated by a qualified exercise director. A full-scale exercise will be held no less than once every 5 years.

12.1.2. A small-scale exercise is an event which tests the adequacy of communication links, e'stablishes that response agencies at the utility and local level understand the emergency action levels, and tests at least one other component (e.g. medical or offsite monitoring) of the emergency plan. A small-scale exercise will be conducted each year that a full-scale exercise is not held at the station. A small-scale exercise will be supervised and evaluated by a qualified exercise director.

l 12.1.3. An exercise will simulate an emergency that results in offsite protective actions and requires response by offsite agencies.

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PT/0/A/4600/06 PAGE 3 0F 5 12.1.4 An exercise scenario shall provide for a critique of the exercise by all concerned personnel and organizations.

12.2 Drills 12.2.1 A drill is a supervised instruction period aimed at testing, developing and maintaining skills in a particular operation. A drill is often a component of an exercise.

A drill will be supervised and evaluated by a qualified drill instructor.

12.2.2 Drills will be conducted at the frequencies indicated below:

(a) Communication drills with state and local government located within the 10 mile Emergency Planning Zone shall be conducted monthly. This communication check will include contact with the NRC headquarters via the ENS (Emergency Notification System)

~

, telephone from the Control Room. TSC and CMC. It will also include a communication check with the NRC Region II Operations Center from the Control Room.

TSC and CMC.

(b) Communication drills with Federal emergency response organizations and states within the 50 mile Injestion Pathway shall be conducted quarterly.

(c) Communication drills with state and local emergency operations centers and field assessment teams shall be conducted annually.

NOTE Sample message information for the above communication drills shall test the ability to understand the ecntent of messages.

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PT/0/A/4600/06 -l PAGE 4 0F 5 l

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(d) Fire drills'shall be conducted in accordance with Station Directive 2.11.1 and documented by the Safety Department.

(e) Medical emergency drills involving a simulated con-taminated individual shall be conducted annually.

This drill will involve participation by the North Mecklenburg Ambulance Service and the North Mecklenburg Rescue Squad and Charlotte Memorial Hospital. A conununication check to Oak Ridge REACTS as the provider of backup medical support shall be conducted during this drill..

(f) A radiological monitoring drill involving onsite and offsite radiological monitoring teams will be .

conducted annual?y. The monitoring teams will actually collect and analyze air samples, as appropriate. Soil, vegetation and water samples will not be taken as this is done on a weekly basis at the station. The exercise controllers will provide ,

them simulated analysis results indicative of contamination or plume location.

(g) Health Physics drills shall be conducted semi-annually which involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment.

(h) Health Physics drills shall also be conducted annually which involve analysis of inplant liquid samples with actual radiation levels, including use of the post-accident sampling system. I l

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PT/0/A/4600/06-PAGE 5 0F 5

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(i) Site assembly drills shall be conducted semi-annually. These drills shall provide for the capability to account for all individuals onsite at the time of the emergency and to ascertain the names of missing individuals within 30 minutes of the start of an emergency condition. The capability to account'for onsite individuals _ continuously after the initial accountability shall be included.

12.2.3 File Enclosure (s) 13.1 and 13.2 with completed procedure process record.

13.0 Enclosures 13.1 Exercise / Drill Format and Critique Findings.

13.2 Exercise / Drill, Controller / Evaluator Report t

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PT/0/A/4600/06 ENCLOSURE 13.1 PAGE 1 0F 3 N

EXERCISE / DRILL FORMAT AND CRITIQUE FINDINGS r

1.0 Classification of Exercise / Drill.- (Check appropriate box) ,

]- Emergency Exercise, 12.1

- Comunication Drill (state and local government within 10 mile EPZ and NRC Headquarters / Region II Operations Center from the I Control Room, TSC, and CMC),12.2.2, a. (monthly) l-

- 'ommunication C Drill (Emergency response organizations and state within 50 mile I.P.Z.),12.2.2, b. (quarterly) i

- Communication Drill (State and local Emergency Operations Centers and Field Assessment Teams),12.2.2, c. (annually)

Medical Emergency Drill, 12.2.2, e. (annually)

]-

- Radiological Monitoring Drill, 12.2.2, f. (annually) ,

- Health Physics Drill, 12.2.2, g. (semi-annually) 3

- Health Physics Drill, 12.2.2..h. (annually)

I

- Site Assembly Drill, 12.2.2,'i. (semi-annually) -

2.0 Drill Instructor / Exercise Director (Name)

Critique Director:

(Name) 3.0 Date/ Time Exercise / Drill to be conducted: /

(Data) (Time) i 4.0 Exercise / Drill Objectives:

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PT/0/A/4600/06 ENCLOSURE 13.1 PAGE 2 0F 3

^T ,

t 5.0 Plant system / ares (s) affected:

I E

P 6.0 Work groups to be involved: [

i 7.0 Time sequence of postulated events: !

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i .

L 8.0 Assigned Observers (Controllers / evaluators) and their stations:

i

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9.0 Critique to be conducted at: / ;

(Date) (Time) .(Location) l 10.0 Personnel to attend critique:

i

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PT/0/A/4600/06 i ENCLOSURE 13.1 i-- PAGE 3 0F 3 l l

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11.0 Critique Findings, Reconunendations, Required Action (s), Etc. :

i.

4 J

12.0 Corrective Actions taken: (List actions taken to ensure all findings in 11.0 1 above are identified and corrected):

I s

1 NOTE: Include all Exercise / Drill data or other information provided as an attachment.

(Drill Instructor / Exercise Director)

(Signature) i (Critique Director) 3 (Signature) l l

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PT/0/A/4600/06 ENCLOSURE 13.2 ;

PAGE 1 0F 1 l

--s 1 EXERCISE / DRILL CONTROLLER / EVALUATOR REPORT 1

1 l

1.0 Drill Classification:

.0 Sununary of Exercise / Drill:

.0 /

Exercise / Drill initiated:

(Data) (Time) 4.0 Observation / Comments /Reconunendations:

's ,

5.0 Exercise / Drill completed at: /

(Date) (Time)

- Controller / Evaluator (Signature) f 1

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1

N l Form 34731 (

(Formerly SPD 10ud.,

4

DUKE POWER COMPANT (1) ID No: PT/0/A/4600/11 i PROCEDURE PREPARATION Change (s)- O to

PROCESS RECORD 1 Incorporated l (2) STATION: seeGuire Nuclear Station (3) PROCEDURE TITLE: Func+4= Check of Buergency Vehicle and Equipment i

I (4) PREPARED BY: 1J $lT. Lum DATE: _F / /7- F .2.

I (5) REVIEWED IT: OL . 2. I c - O, DATE: / / 4 /FJ t

Q Cross-Disciplinary Review By: N/R:4 fL.

V j

j (6) TZMPORAET APPROVAL (IF NECESSARY):

By: (530) Data:

37: Data:

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(7) APPROVED BT: Is J #2[_.8 Date: e /-/f3 ?

(8) MISCELLANEOUS:

) Reviewed / Approved By: Date:

Reviewed / Approved By: Date:

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PT/0/A/4600/11 m DUKE POWER COMPANT McGUIRE NUCLEAR STATION :

FUNCTION CHECK OF EMERGENCT 7EHICLE AND EQUIPMENT 1.0 Purpose 1.1 To ensure that protective equipment and supplies are operational, and that communications capability exists with ,

the various emergency personnel and emergency organizations at an times in the support of an emergency condition at the station.

2.0 References 2.1 NUREG--0654 (Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants).

3.0 Time Required 3.1 Sixteen (16) manhours. .

4.0 Prerequisite Tests N/A 5.0 Test Equipment N/A .

F -

6.0 Precautions and Limitations 6.1 A =4n4== of two people shan be aboard the emergency boat when in use.

~

6.2 Emerg boat operators shan maintain radio communications with the McGuire Nuclear Station at an times and win verify this capability by performing a esdio check every 30 minutes during the period the boat is being operated.

6.3 Personnel aboard the emergency boat shall wear floatation vests at an times and semi-dry suits when Condenser Circulating Water (RC) inlet temperature drops below 60*F.,

and outside air temperature is below 55* F.

6.4 Emergency boat fuel tank level shan be maintained at >h fun at all times.

6.5 Personnel using an emergency vehicle shan wear seat. belts.

i 6.6 Personnel shan follow an FCC regulations during radio ;

transmissions.

7.0 Recuired Station Status l

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Page 2 N/A 8.0 ' Prerequisite Systes Conditions

( N/A 9.0 Test Method N/A 10.0 Data Required .

10.1 Equipment Check-Off List - Faergency Vehicles (Enclosure 13.1) 10.2 Equipinent Check-Off List - Zaargency Boat (Enclosure 13.2) 10.3 Post Accident Containment Air Sampling Equipment (Enclosure 13.3) 10.4 Protective Equipment and Supplies Lacations (Enclosure 13.4) 10.5 Protective Equipment and Supplies Check-Off List -

Recovery Kits (Enclosure 13.5) 10.6 Protective Equipment and Supplies Check-Off List -

Environmental Survey Kits (Enclosure 13.6, 13.7, 13.8..

13.9)

- 't 10.7 Protective Equipment and Supplies Check-Off List -

Personne1' Survey Kit - Construction Post #1 (Enclosure 13.10) 10.8 Per.tective Equipment and Supplies Check-Off List -

Personnel Survey Kit - Brass Shack (Enclosure 13.11) 10.9 Protective Equipment and Supplies Check-Off List -

Personnel Survey Kit - pal" Area (Enclosure 13.12) 10.10 Protective Equipment and Supplies Check-Off List -

Personnel Survey Kit - Evacuation Facility (Enclosure j 13.13) 10.11 Technical Support Center Kit Check List (Enclosure 13.14) 10.12 Medical Decontamination Kit Check-Off List (Enc.Losure 13.15) 10.13 Medical Decour =4 nation Kit Check-Off List, Charlotte Memorial Hospital (Enclosure 13.16) 10.14 Operation Support Center Kit Check List (Enclosure 13.17) l ,

10.15 Fuel Shipment Kit (Enclosure 13.18)

,e , 10.16 Verification of Emergency Communications (Enclosure

., 13.19) e b .

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Pag 3 3 10.17 National Weather Service 'and Onsite Weather (Enclosure l q 13.20) 11.0 Acceptance Criteria .

(. N/A 12.0 Procedure 12.1 Emergency vehicles Date/ Initials

/ 12.1.1 Once during each month and after emergency use, the emergency vehicles shall be inventorted per Enclosure 13.1 (Equipment Check-Off List -

Emergency Vehicles).

/ 12.1.2 With each inventory a check-off list shall be completed and any discrepancies shall be noted on the list and reported to the emergency plan group immediately.

/ 12.1.3 Preventive maintenance shall be the responsibility of the Emergency PT-ains group of Health Physics and be performed by predesignated service areas.

12.2 Emergency Boat

/ 12.2.1 Once during each month and after use, the emergency boat shall be inventoried per enclosure 13.2 (Equipment Check-Off Lia.c -

Emergency Boat).

. NOTE: Run Time (Minimum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per month may be postponed up to, but not more than 3 months due to inclement weather.

/ 12.1.2 With each inventory the check-off list shall be 1 completed and any discrepancies shall be noted on the list and reported to the emergency plan 1 i group imendiately.

2 _/ 12.2.3 Every 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months of operation, the emergency boat shall,be delivered to an authorized l service representative for routine preventative f ~,

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I Pag 2 4 l asintenance as per the owner's-operators' q manual.

t 12.3 Protective Equipment Kits

/ 12.3.1 Once during each month and after use, each

emergency kic listed in enclosure 13.4 (Protective Equipment Kit Locations) shall be inventoried per applicable enclosure 13.5 -

13.8 (Protective Equipment Kit Check-Off Lists).

/ 12.3.2 With each inventory the check-off list shall be complaced and a copy placed in the applicable kit. (The original shall be filed with the completed procedure records). Any discrepancies shall be noted on the check-off list and reported to the emergency plan group inmediately. , .

/ 12.3.3 Check all bacteries in kits monthly for strength and condition.

/ 12.3.4 Verify calibration data and functional check each instrument during inventory.

/ 12.3.5 Verify that silver zeolite cartridges are sealed air cight, and must be changed out two (2) years from date on package.

12.4 Telephone Communications

/ L2.4.1 Once per calendar quarter, all telephone numbers and pages utilized in emergen g procedures EP/0/A/5000/05-08, and Station Directives 3.8.1, 3.8.2 shall be verified correct and in working order. All jack-in telephones in the Technical Support Center will be verified in working order. ,

12.5 Radio Comunications

/ 12.5.1 Once during each month, McGuire emergency radio transmitter / receivers shall be operationally checked as follows:

/ 12.5.1.1 McGuire Emergency Base Station -

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verify capable communications with

.all county Emergency Operations Centers.

/ 12.5.1.2 Emergency Environmental Survey Team Radios - verify capable cosumanications with McGuire Emergency Base Station at a minimum distance of 10 miles.

/ 12.5.1.3 Once a month, a call will be made to the National Weather Service located at the Charlotte Airport and McGuire Control Room to obtain the wind direction, speed and cloud cover.

/ 12.5.2 verification of capable emergency communications shall be documented per enclosure 13.19 (Verification of Emergency Con-unications) and maintained on file by the Emergency Plan Group.

/ 12.5.3 A current verification letter of personnel authorized by Duke Power Company to report an emergency action level, to state and county ,

agencias,. will be used to authenticate the person or persons initiating the report. The verification letter will be updated every 6 months.

12.6 Emergency survey instruments and counting equipment shall be operationally checked quarterly per applicable Health Physics calibration procedures.

12.7 Emergency portable air samplers shall be operationally checked quarterly per Health Physics Manual, Section 15.2 Operation of Health Physics Air Samplers, utilizing their predesignated emergency vehicle and powerverter or gasoline powered generator as the power source.

12.8 Emergency pocket dosimeters shall be operacional17 checked quarterly per HP/0/3/1005/19 (Dosinater Leak and Calibration Check).

I

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4 Pcge 6 12.9 Gasoline powered' generators shall be operationally checked quarterly and preventative maintenance done as described in 3 '

l Section 4 of the owners' annual.

1 l 13.0 Enclosures l 13.1 Equipment Check-off List - Emergency vehicles i 13.2 Equipment Check-off List - Emergency Boat 13.3 Post Accident. Containment Air Sampling Equipment List.

[ 13.4 Protective Equipment and Supplies Locations j 13.5 Protective Equipment and Supp' lies Check-Off List - Recovery Kit-13.6 Protective Equipment and Supplies Check-Off. List -

! Environmental Survey Kits Health Physics Vehicle 13.7 Protective Equipment and Supplies Check-Off List -

Environmental Survey Kits Administrative vehicle 13.8 Protective Equipment and Supplies Check-Off List ,

)

Environmental Survey Kits Chemistry Vehicle

13.9 Protective Equipment and Supplies Check-Off List -

Environmental Survey Kits Maintenance Pickup (Spare) Boat l'

13.10 Protective Equipment and Supplies Check-Off List - Personnel

! Survey Kit - Construction Post #1 13.11 Protective Equipment and Supplies Check-Off List - Personnel Survey Kit - Brass Shack 13.12 Protective Equipment and Supp11as Check-Off List - Personnel Survey Kit PAP Area 13.13 Protective Equipment and Supplies Check-Off List - Personnc1 Survey Kit - Evacuation Pacility 13.14 Technical Support Center Kit Check List i 13.15 Medical Decont=1 nation Kit Check-off List 13.16 Medical Decontamination Kit Check-Off List, Charlotte Memorial Hospital 13.17 Operational Support Center Kit Check-Off List 13.18 Fuel Shipment Kits Check-Off Lise 13.19 Verification of Emergency Communications 13.20 National and On-Site Weather Information e

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PT/0/A/4600/11 Enclosure 13.1 i N EQUIPMENT CHECK-OFF LIST EMnGENCY VEHICLES Vehicle #

7632 Health Physics Vehicle 4352 Chemistry Vehicle 8031 Maintenance vehicle 7105 Administration Vehicle ITEM AMOUNT Fire Extinguisher 1 First Aid Kit 1 Vehicle Accident Form 1 .

Keys (PAP) 1 set each Discrepancies:

Signature /Date i

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PT/0/A/4600/11 Enclosure 13.2 .

EQUIPMENT CHECK-OFT LIST EMERGENCT BOAT INVENTORT TIME AMOUNT Floatation Vest (one per person) 4 Semi-Dry Suits (one per person as required) 4 Bcoyant Jacket (one per person as required) 4 Fire Extinguisher, 1

~

Paddles 2 First Aid Kit 1 Anchor and Line 1 Snake Bite Kit 1 Loud Bailer 1 r ..

OPERATIONAL CHECKS Check _ /_

Bilge Pump Loud Ha11er Horn Siren Navigation Lights Search Lights Tual Tank Level 1 4 full Run Time (Min 4-= - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months b'y log)

Discrepancies:

Signature /Date e

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PT/0/A/4600/11 Enclosure 13.3

% l POST ACCIDENT CONTAINMENT Allt SAMPLING EQUIPMENT Check L Nalgene 500 al Bottles of NADE with , Accompanying 6

Vial of NA 2 S0 23

Sg0 Nalgene 500 al Thiosulfate Sample Bottles 6 .

Stainless Steel 100cc Gas Bombs 6 Poly Bags 6 Stop Watch 1 Location:

Health Physics Shift Lab in File Drawer Labeled " Post Accident Air Sampling Equipment."

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Enclosure 13.4 PROTECTIVE EQUIPMENT AND SUPPLIIS KITS LOCATION Recovery Kits (4) Control Roon

- Station Manager's Office Training & Technology Cent.

Cowans Ford Das Environmental Survey Kits (4) Trailer #7 Personnel Survey Kits (5)

Construction Post #1 Construction Post #1 Brass Shack Construction Post il PAP Area Security - PAP Area Evacuation Facility (2) Cowans Ford Dam, and Training & Technology Center Medical Decontamination Kit Auxiliary Building First Aid Room and Charlotte Memorial Hosp.

Operational Support Center Kit Operational Support Center Technical Support Center Kit Technical Support Center Fuel Shipment Kits (2) Trailer #7 M

e .

PT/0/A/4600/11 Enclosure 13.5

^' RECOVERY KITS CHECK LIST ITEM AMOUNT Xetex Mod 3055 1 High Range Dosimeters 2

~

Dosimeter Charger l Boundary Ribbon or Rope (50 yd. roll) . 1 Masking Tape (roll) L Rain Suits (set) 2 Protective Clothing (set) 2 Poly Bass (various) 12 Caution Signs w/ inserts 2 Legal Pads 1 HP Form.#2 (Seear Survey Form) 5 Pens 2 ,

Grease Pencil 1 Norton 7600 Respirators w/7500-83 Chemical Cartridges 2 First Aid Kit

1

('~N, Potassius Iodide Tablets 475 Bottles-Cowans Ford, 150 Bottles-Control Room.

Station Manager's Office.

Training & Technology Cent.

Smears (box) i NuCon Seears 30 Soap (bar) 6 Flashlight 1 Batteries 4 Pocket Knife 1 Small Sample Bottles 200 Cowans Ford 60 Station Managers Office Training & Technology Cant.

Control Room Discrepancies:

' / Signature /Date

PT/0/A/4600/11 Enclosure 13.6 ENVIRCNMENTAL SURVIT CHECK LIST 4

HEALTH PHYSICS VEHICLE

]

ITEM AMOUNT Xecex Mod 105B and Eberline E-520 or E-120 w/260 probe i each j sam-2 w/RD.22 probe 1 Emergency i'adio Tran==4 teer/ Receiver 1 Radaco HSCbV Air Sampler ,

1 4 Trippe PVI)00FC Powerverter or Gasoline Powered Generator 1 High Rangre Dosimeter 2

! Dosimete': Charger 1 l TLD (in separate labeled container) 2 l 4

Norton 7600 Respirator w/7500-83 Chemical Cartridges 2 Potassium Iodide Tablets (bottle) 1 Protective Clothing (full set) 3 i Poly Bass (various sizes) 6 I Masking Tape- (roll) 1

) Limnological Sampler 1

] Cubitainers 6 Hand Gardening Spade 1 Stopwatch 1 j Flashlight 1 i Batteries 4 l Silver Zeolite (CP100G or GT130) Filter Cartridges and

{ Particulate Filters 30 Labels for Filter Cartridges 30 Smears (box) . 1 Nucon Samars 30

. HP Form #2 (Smear Survey Form) 10

)'

HP Form #6 (Air Survey Form) 10 Map of Ten Mile Zone Sectors 1 Legal Pad 1 Snaka Bite Kit i Pen 2 Grease Pencil 1 Dime Roll 1 Pocket Knife 1 Health Physics Manual - Section 18.2 1 Discrepancies:

Signature /Date 1

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FT/0/A/4600/11 Enclosure 13.7 m

ENVIRONMENTAL SURVET CHICK LIST ADMIN. VEHICLE ITEM AMOUNT J Ietez Mod 3058 and Eberline E-520 or E-120 w/260 probe 1 each Sam-2 w/RD-22 probe . .

1 Emergency Radio Transmitter / Receiver i Radeco H809V Air Sampler 1 Trippe PV1000FC Powerverter or Gasoline Powered Generator i 2

High Range Dosimeter 1

Desimeter Charger TLD (in separate labeled container) 2 )

Norton 7600 Respirator w/7500-83 Chemical Cartridges 2 l 1 l Potassium Iodide Tablets (bottle) ,

3 Protective clothing (full set)

Poly Bags (various sizes) 6 Masking Tape (roll) 1 1 6

Cubitainers Hand Gardening Spade 1 1

Scopvacch -

1 Flashlight 4

Batteries Silver Zaolite (CP100G or GT130) Filter Cartridges and Particulate Filters 30 Labels for Filter Cartridges 30 1

Smears (box) ,

Nucon Smears 30 HP Forn #2 (Smear Survey Form) 10 HP Form f6 (Air Survey Form) 10 Map of Ten Mile Zone Sectors 1 Legal Pad 1 Snake Bite Kit 1 Pen 2 Grease Pencil 1 Dime Roll 1 1

Pocket Knife Health Physics Manual - Section 18.2 1 Discrepancies:

Signature / Data 1

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.- i PT/0/A/4600/11 Enclosure 13.8.

ENVIRO 10 ENTAL SURVEY CHECK LIST

\ CHEMISTRY 7EEICLE l

l ITEM AMOUNT Xataz Mod 305B and Eberline E-520 or E-120 w/260 probe i each Sam-2 w/RD-22 probe .

1 Emergency Radio Transmitter / Receiver . 1 Radeco H8097 Air Sampler 1 Trippe PV1000FC Powerverter or Gasoline Powered Generator 1 High Range Dosimeter 2 Dosimeter Charger 1 TLD (in separate labeled container) 2 Norton 7600 Respirator w/7500-83 Chemical Cartridge's 2 Potassius Iodide Tablets (bottle) 1 Protective clothing (full set) 3 Poly Bags (various sizes)~ 6 Masking Tape (roll) 1 Cubitainers 6 Hand Gardening Spade ,

1 Stopwatch '

1-Flashlight 1 Batteries . ,

4 ,

Silver Zeolite (CP100G or GT130) Filter Cartridges and Particulate Filters 30

/ }i Labels for Filter Cartridges 7 -

30 .

Samars (box) - ,1 Nucon Senars 30 HP Forn #2 (Smear Survey Form)' 10 HP Form #6 (Air Survey Form) 10 Map of Ten Mile Zone Sectors 1 Legal Pad p ,- 1 Snake Bite Eit #

1 Pen 2 Grease Pencil 1

, Dime Roll ~ 1 1 Pocket Knife 1 Health Physics Manual - Section 18.2 1

'l Discrepancies:

i' Signature /Date r-n-e---- -w3 ce. - , a w ,w _.- vmsg*e r emew =reweg yn-e*=ewr=-+=- sv w= . = * = ~ * . = = = - * *j.*vr-

O PT/0/A/4600/11 Enclosure 13.9

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ENVIRONMENTAL SURVEY CHECK LIST MAINT. PICKUP (SPARE) VEHICLE ITEM AMOUNT 4 Ietex Mod 305B and Eberline E-520 or E-120 w/260 probe i each

- 1 j

Sam-2 w/RD-22 probe -.

Emergency Radio Transmitter /Raceiver 1

' Radeco H809V Air Sampler 1 Trippe PV1000FC Powerverter or Gasoline Powered Generator i High Range Dosimeter 2 Dosimeter Charger 1 TLD (in separate labeled container) 2 Norton 7600 Respirator w/7500-83 Chemical Cartridges 2 1

Totassium Iodide Tablets (bottle)

Protective Clothing (full set) 3 Poly Bass (various sizes) 6 Masking Tape (roll) 1 Limnological Sample: 1' Cubitainers 6 Hand Gardening Spade 1 .

Scopwatch i Flashlight i Batteries 4 Silver Zeolite (CP100G or GT130) Filter Cartridges and Particulate Filters 30 Labels for Filter Cartridges 30 Smears (box) L Nucon Smears 30 HP Form #2 (Smear Survey Form) 10 HP Form #6 (Air Survey Form) 10 Map of Ten Mile Zone Sectors 1 Legal Pad 1 Snake Bite Kit 1 Pen 2 Grease Pencil L Dime Roll 1 Pocket Knife L Health Physics Manual - Section 18.2 L Discrepancies:

Signature /Date I

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~ PT/0/A/4600/11 Enclosure 13.10

..g PERSONNEL SURVET KIT l CONSTRUCTION POST #1 CHECK LIST

' AMOUNT ITEM Eberlina E-520 or E-120 v/HP-260 probe i Emergency Radio Transmitter / Receiver, provided by Security i 1

High Range Dosimeters i

Dosimeter Charger Norton 7600 Respirator v/7500-83 Chemical Cartridges 1 1

Potassina Iodine Tablets (bottle)- 6 Protective Clothing (full set) 1 Boundary Ribbon or Rope (50 yd. roll) 4 Caution Signs v/ inserts 1

Masking Tape (roll) 6 Poly Bass (various) 1 Smears (box) 25 Nucon Smears HP Form #2 (Smear Survey Form) 10 '

2 Pens 1

Grease Pencil Health Physics Manual, Section 18.1 1 1

Legal' Pad 1

Pocket Knife Discrepancies:

Signature /Date O

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PT/0/A/4600/11 Enclosure 13.11 PERSONNEL SURVET KIT BRASS SEACK CHICK LIST AMOUNT ITEM Serline E-520 or E-120 w/HPi-260 probe 1 Emergency Radio Transmitter / Receiver, provided by Security I 1

High Range Dosimeters 1

Dosimeter Charger 1

Norton 7600 Respirator w/7500-83 Chemical Cartridges 1

Potassium Iodide Tablets (bottle) 6 Protective Clothing (full set) 1 Boundary Ribbon or Rope (50 yd. roll) 4 Caution Signs w/ inserts 1

Masking Tape (roll) 6 Poly Bags (various) i Smears (box) 25 NuCon Smears HP Form #2 (Smear Survey Form) 10 2 2 Pens 1 l Grease Pencil Health Physics Manual. Section 18.1 1 1

Legal Pad l 1

( Packet Knife .

. Discrepancies:

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PT/0/B/4600/11 Enclosure 13.12 PERSONNEL SURVET KIT PAP ARIA CHICK LIST ITEM AMOUal !

Eberline E-520 or E-120 w/EP260 probe 2 j Emerbency Radio Transmitter /Raceiver, provided by Security 1 i High Range Dosimeters 2 ;

Dosimeter Charger 1 i Norton 7600 Respirator w/7500-83 Chemical Cartridges 2 j Potassius Iodide Tablets (bottle) 1 Protective Clothing (full set) 6 ,

Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 .

Masking Tape (roll) 1 [

Poly Bags (various) 6 Seems (box) 1 ,

Nuccc Smears 25 EP Form #2 (Saear Survey Form) 10 ;

Pens 2

i Grease Pencil 2 l Health Physics Manual. Section 18.1 and Section 11.3 1 each i

Legal Pad 1 Pocket Knife 1 Hand Soap 10 Hand Brushes 2 l Atomic Swipes 12 t Citric Acid (1 lb.) -

1 l Disposable Towels 1 pk. i Fingernail Clippers 1 f Disposable Coveralls 40 f Phischex 1 quart i c

Discrepancies:

I Signature /Date l I

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PT/0/A/4600/11 Enclosure 13.13 i

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PERSONNEL SURVET KIT EVACUATION FACILITY CHECK LIST i ITEM AMOUNT

' Eberline E-520 or E- 120 w/EP260 probe 2 L Emergency Radio Transmitter / Receiver, provided by Security 1 High Range Dosimeters 4 Dosimeter Charger 1 Norton 7600 Respirator v/7500-83 Chemical Cartridges 4 Potassium Iodide Tablets (bottle) 2 ,

Sas11 Sample Bottles 4 Protective Clothing (full set) 6 Boundary Ribbon or Rope (50 yd. roll) 2 C.2ution Signs w/ inserts 6 Masking Tape (roll) 1 Poly Bags (various) 6 ,

Smears (box) 1

. NuCon Samars 25 HP Fora #2 (Samar Survey Form) 10 Pens 2 Grease Pencil 2 Health Physics Manual, Section 18.1 and Section 11.3 1 each

~

Legal Pad 1

'l Pochet Knife Hand Soap ,

10 Hand Brushes 2 Atomic Swipes 12 Citric Acid (1 lb.) 1 Disposable Towels 1 pk.

Fingernail Clippers 1 Disposable Coveralls 40 Phischex 1 quart Discrepancies:

Signature /Date i

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PT/0/A/4600/11 Enclosure 13.14 em '

( TECHNICAL SUPPORT CENTER KIT CHECK LIST ITEM AMOUNT Protective Clothing (set)

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6 Norton 7600 Respirators w/7500-83 Chem. Ctss. 6 Xeter Mod 3053 or PIC 6A 1 Rideco H809V Air Sempler 1 Silver Zeolite (CP-100G or GT-130) Pilter Cartridps &

Particulate Pilters 25 Labels for Filter Cartridges 25 SAM-2 w/ED-22 Probe . I Potassium Iodide Tablets (bottle) 25 Saia11 Sample Bottles 10 Caution Signs w/ inserts 3 Rad Tape 2 Samars 30 Plastic Bags 6 Masking Tape (roll) 1 Pen 2 Grease Pencil

1 Discrepancies:

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Signature /Date 4

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PT/0/A/4600/11

. Enclosure 13.15 .

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'M MEDICAL DECONTAMINATION KIT CHICK-OTT LIST ITEM AMOUNT Eberline RM-14 w/EP-210 Probe (H.P. Lab) 1 Decon Cleaner 3

~ ~ '

i Disposable Towels 10 Poly Bass 20" x 40" 2 Poly Bass 12" x 18" 4 Fingernail Clippers 1 Samars 25 j Nucon Smears 25 ,

Hand Brushes 2 Hand soap 10 i

4 j' Protective Clothing (full set)

Disposable Rain. Suits 2 j

j Tape, Radioactive Material 1 i Tape, Masking 2" 1 j Tape, Duct 2" 1

HP Torm #2 4

! AP/0/A/5500/27 1

! Swipes, Atomic (Kotex) 12 j Citric Acid (1 lb.) 1-j Phischez 1 gallon

],, Discrepancies: _ _

7 i

Signature /Date i

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2 i f 4

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', MEDICAL DECONTANTMATION KIT CHECK-OFT LIST CHARLOTIE MEMORIAL HOSPITAL ITEM AMOUNT !

Eberline E-120 w/EP210 and EP270 Probes 2 Decon Cleaner 3 .

Disposabia Towels 10 l 2 I Poly Bass 20" x 40" Poly Bass 12" x 18" 4 i Fingernail Clippers 1 -

Seears 25 -

Nucon Samars 25 Hand Brushes 2 Hand Soap 10 '

Protective Clothing, provided by Hospital 4 Disposable Rain Suits 2 ;

. Tape Radioactive Material 1 ;

Tape, Masking 2" 6 i Tape. Duct 2" 6 .

HP Torm #2 4 !

AP/0/A/5500/27 1 Swipes Atomic (Eocex) 36 Citric Acid (1 lb.) 1

/ . .' , Hair Clippers, Electric 1

\ , / Absorbent Paper . 150 Caution Signs v/ inserts 5 :

Rad Rope 1 Pocket Desimeters 0-200 mR 25 Dosimeter Charger 1 Discrepancies:

Signature /Date h P

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, PT/0/A/4600/11 Enclosure 13.17 OPERATION SUPPORT CENTER KIT CHECK-OFF LIST .

ITEM AMOUNT _,

Protective Clothing (set) 4 Norton 7600 Respirators w/7500-83 Chemical Cartridges 4 Flashlight 4

! Batteries 8 Portable Radiac Instrument (PIC 6-A) 2 Camera 1 Film Pacs .

2 Masking Tape (roll) 2 Dosiasters (0-51) (0-50R) 4 each Dosimeter Charger . 1 Rain Suits 4 Poly Bags 12 Batteries (Camera) 1 Flashbulbs (Camera) ,

8 Discrepancies: .

Signature / Data s

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- PT/0/A/4600/11" Enclosure 13.18 1

N FUEL SHIPMENT KIT ITEM AMOUNT

) 2

! Air Purifying Respirator 4

Coveralls Rubber Shoe Covers, pairs 6 6

Bubber Gloves, pairs Poly Bass 20" x 40" 12 3

Step Off Pads 4 50 yd. Roll of Barricade Tape (Magenta s Tellow)

Roll of Duct Tape 2 Box of'Scall Kinwipes 2 TLD Badges in Separate Labeled Container 5 5

Personnel Dosimeters Dosimeter Charger i 1

Steno Pad with 2 Ink Pens Nucon Samars 100 Cotton Gloves, Bundle i

Shoe Covers, disposable, pair 20 All Purpose Marker 2 Scotch Tape Roll and Dispenser 1 -

Masking Tape. I roll 1" and i roll 2" 2 3

Serline E-520 w/EP-270 probe 1 Rain Suit, disposable 2 Hood, disposable 4

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)' Weather-Proof Caution Signs with Inserts 4 Radioactive Waste Signs (4" x 6") 25 Caution: Radiation / Radioactive Material Tags 12 1

Binoculars Coins for Telephone (roll of' dimes) 1 Plastic Sample Bottles 12 Safety Glasses 5 Hard Hats 3 Contact Pyrometer 2 Flashlight and extra batteries 2 Portable Air Sampler i

< Silver Zeolite Cartridges and labels 10 each 1

Eberline E-520 or E-120 v/HP260 Probe Trippe PV100PC Powetverter or Gasoline Powered Generator 1 Discrepanciss:

Signature /Date

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PT/0/A/4600/11 Enclosure 13.19 f"x

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VERITICATON OF BG2GENCY COMMUNICATIONS This document shall serve as written verification that on the date belov l all telephone numbers and pages enclosed in emergency procedures EP/0/A/5000/05 thru EP/0/A/5000/08, Station Directive 3.8.1 and Station Directive 3.8.2 are correct and in working order, and that all jack-in telephones in the Technical Support Center are in working order. (To be done quarterly). -

Signature / Data Furthermore, this document shall serve as written verification that McGuire Nuclear Station's emergency radio transmitter / receivers have

! been successfully checked for operation at the distances prescribed by this procedure. (To be done monthly).

Signature /Date Discrepancies Note:

Corrective Actions Taken:

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PT/0/A/4600/11 Enclosure 13.20 l

WEATIER INFORMATION NATIONAL WEATIER SERVICE ONSITE DATA Wind Direction l

Wind Speed Cloud Cover Time .

Discrepancies:

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1 * % "* R }!L M k 6 DATE Original Issued 5/18/77

.^s REVISION 11 DATE / //7/7 3 I . /

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DUKE POWER COMPANY l

McGU1RE NUCLEAR STATION BOMB THREAT / BOMB SEARCH PLAN OBJECTIVE The objective of this directive is to outline a plan that will provide for the safety and protection of Station personnel and equipment in the event of a bomb l

threat and to ensurs continuity of service, if possible.

GENERAL In the event of a bomb threat, an organized plan ciast be utilized. The following is an outline of the procedure to be used at McGuire Nuclear Station in the event that a bomb threat is received or a suspected device is detected.

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HANDLING OF TELEPHONE CALL In the event a bomb threat telephone call is received, a Telephone Procedure Bomb Threat Check List (Attachment #1) has been placed at the Switchboard, the Control Room, Central and Secondary Alarm Station, Station Manager Clerk's Office, and in the Station Manager's Office; this list should be used to record all the information possible during the telephone conversation.

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1 i IMPLEMENTATION AND NOTIFICATION

In the event a bomb threat is received, the following action should be taken

l i 1) The person receiring the call should immediately notify the Operations Shift Supervisor, extenston

2) The Operations Shift Supervisor shall take the following action:

, a) Implement RP/0/A/5700/01, Notification of Unusual Event b) Notify the CAS/SAS Operator at extension 4482, 4461.

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3) The Emergency Coordinator shall proceed to assemble personnel and evacuate s' '

any affected station areas based on information available. (See Station Directive 3.8.1, Site Assembly / Evacuation).

4) In the event the bomb threat involves discovery of a suspected device or information provided leads the Emergency Coordinator /Shif t Supervisor to believe a bomb actually exists that may affect Reactor Safety Systems or potential release of radioactive materials the Shift Supervisor should consider taking the following steps:

1) Place the reactor (s) in a safe operating mode.

2) Take necessary precautions to prevent the release of radioactive ~

materials (i.e. stop all releases of radioactive materials, secure j high radiation areas). \

SEARCH AND REPORT ,

The Station will be searched by available Health Physics, Operations Fire Brigade, Security Force Personnel (to be provided by Security Shift Lieutenant)

Construction Supervision for Construction spaces outside the protected area in

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\ accordance with guidance provided in Bomb Threat Search Plan (Attachment #2) and .

f Construction procedures. If a Bomb Threat should occur during the backshifts or .

I on weekends, the Emergency Coordinator shall call-out additional Fire Brigade.

Health Physics, Security Force 'and Construction personnel thru appropriate l*

supervision to assist in the Bomb Threat search. Each individual involved in the search will report results of the search to the Emergency Coordinator, he will issue any i additional instructions.

DETECTION OF A DEVICE

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It is possible that a bomb threat could develop by mere detection of a i

suspicious device. The person discovering a suspected explosive device should Omnediately advise their supervisor of the location, time discovered, and any j pertinent information. This situation would then be handled similar to the case

, of finding the device during the response to a bomb threat phone call as 9

l outlined in this Directive.

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. CAUTION: Personnel should not move, tamper with, or handle any suspected explosive device. Do not use radio systems for communications.

FURTHER ACTION REQUIRED The Emergency Coordinator shall take appropriate action based on the existence of a suspected explosive device. If a suspected explosive device is found, the Emergency Coordinator shall ensure the following action is taken:

1) Contact the Charlotte /Mecklenburg Bomb Disposal Team after a suspected explosive device has been found. - The contacts for McGuire are:

Responding Team: Charlotte /Mecklenburg Bomb Disposal Team Telephone Number' ,

2) Evacuate the affected area and ensure that all personnel stay clear of the danger zone (300 feet).

ALL CLEAR REPORT k' hen a bomb threat no longer exists, the Emergency Coordinator will ensure that

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/ ; an "All Clear Report" is made and Station Personnel shall be allowed to return

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'5 STATION DIRECTIVE 3.7.3 1

ATTACHMENT NO. 1 w

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- REVISION 2 DATE [ ['.T[f;2 APPROVAL EYIY TELEPHONE PROCEDURES / BOMB THREAT CHECK LIST INSTRUCTIONS: Be calm, courteous, and listen; do not interrupt the caller.

CALLERS IDENTITY: Sex Approxmiate Age ORIGIN OF CALL: Local Long Distance Internal VOICE CHARACTERISTICS: SPEECH: LANGUAGE:

Loud Soft Fast Slow Excellent Poor High Pitch Deep Distant Lisp Fair Other Pleasant Raspy Stutters Nasal Foul Intoxicated Other Slurred Other Good ACCENT: MANNER: BACKGROUND NOISES Local Calm Angry Factory Machines Trains Foreign Rational Irrational Music Voices Incoherent Familiar Coherent Street Traffic Quiet f If familiar Deliberate Emotional Animals . Office

( who did it Crying Laughing Airplanes . Other sound like?

BOMB FACTS Pretend difficulty in hearing.

Keep caller talking.

If the caller seems agree **f+ to further conversation, ASK THESE QUESTIONS:

1. When will the bomb AsyL i=?

2. Where is the be.# i car. .'i

3. What kind of 10$ y ,

4. Where are you r.w ? '_ --

5. What is your name and address?

If the building is occupied, inform the caller that detonation could cause death or injury.

Did the caller appear familiar with the premirau by his description of the bomb location?

Notify the Operations Shift Supervisor. Talk to no one other than instructed by your

, supervisor.

SIGNED TIME DATE

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STATION DIRECTIVE 3.7.3 ATTACHMENT NO. .2 REVISION 8 DATE //.cs./_PJ APPROVAL 7 f # M M i

BOMB THREAT SEARCH PLAN AND CHECK SHEET In the event a bomb threat received included inforution about the location of the bomb, this area should be searched first. If the bomb threat contained no information about the bomb location, the following search plan will be utilized:

NOTE: (1) Health Physics coverage of some areas and search personnel may be required. Contact Health Physics for support in these areas.

(2) The Emergency Coordinator shall designate search plan priorities based on available information. Areas that are known to be inaccessible for long periods of time i.e.: Containment, filter and domineralizar rooms, should not be given priority for search.

(3) For locked areas where keys are not available from the Shift .

Supervisor or Health Physics, the appropriate personnel in charge of the area shall be contacted for access.

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SEARCH COMPLETED AREA RESPONSIBILITY INITIALS TIME Vital Electrical / Cable Rooms Fire Brigade All Other Station " Vital" Security Areas Unit 1, Fuel Bu!1di.ig Fire Brigade Unit 2, Fuel Building Fire Brigade

- Unit 1 Containment Bldg. Fire Brigade (all elevations)

Unit 2 Containment Bldg. Fire Brigade (all elevations)

Auxiliary Bldg. Elv 695 Fire Brigade Auxiliary Bldg. Elv. 716 Fire Brigade

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STATION DIRECTIVE 3.7.3 ATTACHMENT NO. 2 PAGE 2 0F 3

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BOMB THREAT SEARCH PLAN AND CHECK SHEET CONTLWED SEARCH COMPLETED AREA RESPONSIBILITY INITIALS TI:E Auxiliary Bldg. & Service Fire Brigade Bldg. Elv. 733 and Elv. 739 Auxiliary Bldg. & Service Fire Brigade Bldg. Elv. 750 Auxiliary Bldg. & Service Fire Brigade Bldg. Elv. 760, 767, 777 (Q.A. Darkroom, Planning, ventilation Room)

Auxiliary Bldg. Elv. 786 Fire Brigade Unit 1 Inboard / Outboard Fire Brigade .

Doghouse Unit 2 Inboard / Outboard Fire Brigade fr Doghouse s .

Unit 1, 2. Turbine Bldg. Fire Brigade Elv. 739 Unit 1, 2, Turbine Bldg. Fire Brigade Elv. 760 Unit 1, 2, Turbine Bldg. Fire Brigade Elv. 790 All Extremely High Radiation Health Physics Areas Station Grounds "Inside" Security Protected Area

, Turbine Building, Service Security Building, Auxiliary Building, and Containment Building Roof's and Structures Intake Structure Security RadWaste Solidification Health Phys 1..i r' 1 I l N

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STATION DIRECTIVE 3.7.3 ATTACHMENT 2 ,

PAGE 3 0F,3 l

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BOMB THREAT SEARCH PLAN AND CHECK SHEET CONTINUED SEARCH COMPLETED l AREA RESPONSIBILITY INITIALS TLME Contaminated Parts Whse. Health Physics Safe Shutdown Facility Security All Trailers - Inside Security Protected Area Warehouse #5 Security Interim Waste Building Health Physics Oil Storage House Security Bulk H Storage House Security .

2 Bulk N Storage House Security 2

Bulk 0 St rage House Security 2

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(>. 3 All Construction Buildings Security ,

(Inside Protected Area)

All Construction Buildings Construction (Outside Protected Area) Supervision Inside FWST Missile Shield Security (Unit I and 2)

Administrative Building Security Trailers and Grounds near Security Admin. Bldg. (Outside Protected Area) l f

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ML20065A583

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