ML20024A153

Public Version of Rev 2 to Emergency Plan Implementing Procedure LZP-1330-32, Post-Accident Sampling of Ga Wide- Range Gas Monitor. Offsite Procedure Mod Forms & Revised Index Encl

ML20024A153
Person / Time
Site:	LaSalle
Issue date:	05/03/1983
From:	COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20024A152	List: ML20024A153
References
LZP-1330-32, NUDOCS 8306150636
Download: ML20024A153 (18)

Text

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. - LaSalle Cour:v Nuclear Station Rural Route *1. Box 220

@ Commonwealth Edison Marseules. Illinois 61341 Te!echone 815/357-6761 Date &A u A / 9 f-f

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SUBJ ECT: LaSalle County Station Controlled Procedure Manuals Set # 94-/0 6*

Attached are copies of Of f-Site Notification forms that have not been l signed and returned to our office.

It is Imperative that you update your manuais and return the notification forms to our office in a timely manner.

If the Set # mentioned above has been transferred to another person, please list below who presently holds the controlled set.

Also, If you believe you have updated your manuals according to the attached notifications, please verify this by checking the notifications against your I controlled set, signing the notification forms and return them to our office.

Your immediate attention to this matter will be appreciated.

1 Office Supervisor LaSalle County Station XooT Attch.

LZP 1

8306150636 830607 PDR ADOCK 05000373 F PDR t

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1 LA7 32C-3 Revision 22 Augus: 25 I.992 8 5DIAC ATT ACHME'47 C CFF-SITE PRCCECURE MCCIFICATICN FCA."

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Please REMOVE the following pagas f rom your contrcllac cocy of tne LaSalle County Station L 2.8 ___ Procacures Manual. :ne INSEAT the new pages as incicatec anc AEMCVE anc CESTACY supersecea pages. SIGN :ni s transai ttal forn in tna spaca RETURN :nis signac snee:

provideo for Manual noicar colow.

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Cffice Sugarviscr LaSalle Ccun:y Sta icn R. n. :-c l yc ax Stasian Superintancen: -

LaSalle County Sca:icn

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9/15/82 LZP INDEX PAGE i

'R0C , NC . TITLE RE/. REV OATE CISAETT

.P ICC-1 DELETED C3 IL/80 01

.P 100-2 DELETED C* 11/80 01

.P 1C0-3 DELETED 03 10/80 01

.P 20C-1 DELETED 02 11/80 01

.P 200-2 DELETED C2 11/dC C1

.P 200-3 DELETED C2 11/80 01

.P 2CO-4 OELETEC C3 11/oo 01

'P

. 210-1 DELETED C2 10/80 01

• P

. 300-1 DELETED C4 d/dC C1

P 3CC-2 OELETED C3 11/80 01

P 310-1 DELETED C3 11/80 01 17 320-1 DELETED 02 10/d0 01 IP 33C-1 DELETED 01 10/80 01 19 36C-1 CELETED -

01 10/80 01 iP 350-1 DELETED 02 10/80 01 LP 3eC-1 CELETED 02 10/o0 01 27 370-1 CELETED C1 10/80 01 l

LP *CC-1 DELETED C2 11/80 C1 ZP 4CC-2 DELETED C2 10/8C C1 IP 4CC-3 OELETED 01 11/8C 01 LP *10-1 DELETED C1 11/e0 01 LP *20-1 CELETED 01 11/8C 01 LP 510-1 DELETED C2 10/dC 01 ZP 520-1 CELETED C2 10/8G 01 LP 520-2 CELETED C1 10/8C 01 LP 522-3 OELETED C1 10/80 C1 ZP 3C-1 DELETED C1 10/8C 01 1 M+,

CW - - --

$/15/32- LZP INDEX PAGE 2

>RaC. NO. TITLE REV. REV OATE CISAETT ZP 530-2 DELETED C2 10/80 01 IP 3*C-1 DELETED Cl 10/8C 01 49 7C0-2 CELETED 01 11/8C 01 ZP 710-1 -

DELETED 02 10 / ec Cl 29 31C-1 DELETED 01 10/dC 02 LP e20-1 DELETED C1 10/dC 02 2P S3C-1 OELETED Cl 10/80 C2

.29 350-1 DELETED Cl 10/80 02

.9 4 8eC-1 DELETED Cl 10/8C C2

.4P S30-1 DELETED Cl 11/30 02

.ZP. 1110-1 STATION DIRECTOR (ACTING STATION og Jjh3 02 OIRECTOR) IMPLEMENTING PROCEDURE

.!P *120-1

. GPERATICNS DIRECTOR IMPLEMENTING 04 z/83 02 OIRECTOR

.ZP 1130-1 TECHNICAL DIRECTOR IMPLEMENTING PROC. C3 4/81 02 l .ZP 1140-1 MAINTENANCE DIRECTOR IMPLEMENTING Cl ll/SC 02 PROCEDURE _

i

.29 1130-1 STORES CIRECTCR IMPLEMENTING PROCEDURE 01 11/80 C2 l

l .ZP 11o0-C1 ADMINISTRATIVE DIRECTOR IMPLEMENTING C2 1/82 02 PRCCEDURE LIP 1170-1 SECURITY DIRECTCR' IMPLEMENTING C3 1/82 02 PROCECURE

.4P ,1150-1 RAC/ CHEM OIRECTOR IMPLEMEhTING 03 7/81 02 PROCECURE l

l

.ZP ileo-2 RAD / CHEM OIRECTOR INITIATdo 'C 1 11/80 02 ENVIRCNMENTAL MONITORING ACTIVITIES L43 1200-1 CLASSIFICATIONS CF GSEP CONDITIONS C3 f[&D C1 LL3 1 CC-2 CLASSIFICATION CF A NO3LE GAS RELEASE Of I;Llgs c2 LZo 12CC-3 CLASSIFICATION CF AN 10 CINE RELEASE 01 2/32 C1 LZP .20C-4 CLASSIFICATIGN CF A LI')dID RELEASE C1 Slaa 01 L:e '.210-1 HAZAA0005 MATERIAL INCIDENTS REPORTING gg g 1

5/15/42 LZP INDEX PAJE 3 PROC. NO. TITLE REV. REV OATE DISKETT-IP 1220-1 EMERGENCY TELEPHONE NUMBER Cl 5/81 01 10 122C-4 DELETED 01 7/81 01 P 131C-1 NOTIFICATIONS 03 3/yg C2 IP 132C-1 AUGMENTATION CF PLANT STAFFING g l[g,3 C2 ZP 133C-1 P C OF REACTOR Cl ll/dC C2 Zo 1330-2 PCf5 IDEN SAMP NG OF THi PRIMARY q C1 3/81 C3 C0r. TAlf T P RE FOR R 6DIGIDINES DE1 E All C [a

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!S

, , i ZP 1330-3 POS T-A C 1EF_

T 3& fN 'IMARY

. C2 3/81 03 CO.] TAI Pi lE f MTj

! ZP 1330-4 PC CCIDENT SA.lPLING OF 'HE PLANT Cl 11/8C C3 VE T R RTICULATES i ZP 133C-5 POST-ACCIDENT NOBLE GAS RELEASE RATE CO 11/80 03 l OETERMINATICN ZP 1330-6 DELETED 01 7/81 G3 f

G T E LET l .ZP 1330-8 SAMPLING LICUID PROCESS MONITCRS Cl S/Sa C3 l OURING LICUID MONITOR HIGN RACIATION

( ALARM CCNGITIONS

.ZP 133C-10 DELETED Cl 1/32 c3

.LP 133C-11 DILUTION AND TRANSFER OF GAS SAMPLES 00 ll/dl 03

.IP 1330-20 POST-ACCICENT ANALfSIS OF SARON 03 (BACKUP PROCECURE)

.ZP 1330-21 PCST-ACCICENT ANALYSIS OF CHLCRIDE C3 fo/82 C3

_ZP 133C-22 CALI3PATICN OF THE MOCEL 10 CIONEX C2 4/S2 C3 ICN CHRCMATCGRAPH i

.iP 1330-23 CETERMINATICN OF REACTCR CJGLANT PH, C2 6/d2 C3 CONC:JCTIVITY ANC OISSCLVE0 OXYGEN CCNCENTRATIO'4 AT THE HIGH RAOIATIO.4 SA."PLE SYSTE:4

5/15/82 LZP INJEX PAGE 4 DRCC. NO. TITLE REV. REV QATE DISKETT 2P 1330-24 DETERMINATION OF REACTOR COOLANT 02, '/83 C3 HYOROGEN CONCENTRATION AT THE HIGH RADIATICN SAMPwING SYSTEM i

.!P 133C-25 sat 4PLING OF REACTOR CCOLANT AT THE C2 (o/o 2 03 HIGH RAGIATION SAMPLE SYSTEM

{-

l .EP 1330-26 SAMPLING OF CCNTAINMEh;T AIR AT THE C3 4y 82 C3 l HIGH RACIATION SAMPLING SYSTEM

. A Y T *1 l

.ZP 133C-28 S AMPLING OF RA0lOACTIVE W ASTE L'I'J bICS C2 6/d2 C3 i RADI0 ACTIVITY AT THE HIGH RADIATION l

l

.4P 1330-29 S A.1 W- TT Tf1 A1 TION CC 4/82 C3 SANP W YST (VA p RATION AT TH VALTE wN L PANEL)

.ZP I33C-30 TRANSFER OF WASTES FRCA THE HRSS WASTE 00 11/81 03 l

l TANK AND WASTE PUMP 90 1330-31 b AMPLE MOVEMENT CO 1 ' 81 03

[ N 13'30 -@ ST A k. AMPLING OF THE GENERAL ATOMIC 02, 8) l

.4P 133C-50 b b M NGN bNDER ACCIDENT CO 10/81 03 CONDITIONS LIP 134C-1 IMPLEMENTING PROCEDURE FOR FIRE: C1 9/81 02 FIRE MARSHALL -

LLP 134 -2 IMPLEMENTING PROCEDURE FJR FIRE: CL ,3h 01 FIRE CHIEF (CESIGNATED SHIFT FOREMAN) l L?P 134C-3 IMPLEMENTING PROCEDURE FOR FIRE: Cl 7/dl C2 FIRE OFFICER 31 (COGNIZ ANT F. AINTEN ANCE FCREMAN) c2P 134C-4 IMPLEMENTING PRCCEDURE FOR FIRE: C1 9/dl 02 e FIRE BRIGADE LLP 134G-5 IMPLEMENTING PRCCEDURE FOR FIRE: "Cl d/81 00 FIRE COMPANY NO. 1 (MAINTENANCE PERSONNEL)

LZP 136C-1 PROTECTIVE MEASURES FCR ON-SITE C3 7/61 C2 PERSONNEL LZP L3oO-2 USE OF POTASSIUM IOCICE (KI) AS A OI l/f3 Ga THfRCIO 3LOCAING AGENT l

l LZ? 1350-4 RADIATION PROTdCTION PRACTICES CURING CO 11/61 C3 l ACCIDENT CONDITIONS

LZP-1330-32 Revision 2 May 3, 1983 1 -

POST ACCIDENT SAMPLING OF THE GENERAL ATOMIC WIDE RANGE GAS MONITOR A. PURPOS_E The purpose of this procedure is to delineate tne steps required to obtain iodine and particulate samples from either the Station Vent Stack or the Standby Gas Treatment ef fluent monitoring systems during a post accicent condition.

8. REFERENCES ,

1. Wide Range Gas. Monitor, Equipment Manual; General Atomic Company, June, 1981.

2. LCP 310-11 " Sampling of tne General Atcmic Wide Range Gas Monitor for Noole Gases, Iodines, and Particulates."

3. LZP 1330-35, " Isotopic Analysis of Iodine Samples Using AAIS Software with PARAPS Hardware."

4. LZP 1330-36, " Isotopic Analysis of Particulate Samples Using AAIS Software witn PARAPS Hardware."

5. P&ID M-153, sheet 7, Process Radiation Monitoring.

6. Commonweal th Edison Radiation Protection Standards.

7. Hewlett Packard Program Instructi9ns, "I-131, Equivalent Concentration."

I 8. GSEP Environmental Di rector Emergency Plan Implementing Procedure ED-16, " Quick Estimate of Offsite Oose From Unplanned Release: Liquid and Gaseous."

~

9. Action Item Record (AIR), 1-81-358.

10. Post Accident Radiation,(ggglj, Revision 1, August, 1980, Sargent ano Lundy Project 6094-00.

11. Action Item Record (AIR), 1-81-495.

4 LZP-1330-32 Revision 2 May 3, 1983 ,

2

12. General A r rangeme nt, Print M-7.

C. PREREQUISITES .

\

I 1. Ensure there are clean filter assemolles and cartridges _

l in the gran sample holder. y 3

D.

PRECAUTIONS ,

1. A Regulatory Guide 1 3 or 1.4 release of fission products implies extremely high levels of I radioactivity. Dose rates may be high enougn to prevent entry into many areas of the plant tnat are ~

normally habitable. Rad /Cnsm Supervisicn should ce i

contacteo prior to entry into any area wnen such ' a release of fission products i's suspecteo.

2. Wear radiation' dosimetry as recommended ny; Rad / Chem 1

Supervision. i

3. Wear protective ylothin'(and g ' respiratory protection '-

l as recommended b,y Rad /Chom Supervisioq.

! 4. Appropriate survey instr.uments shouldsbe availaole#

for monitoring during(this procedure.

l ' \ ,

The areaa associated with sthe movement df higtj t

l

5. '

radiation samples,should oe, secured to non-essential personnel dur.irg the t~sasferal of samples. '

6. Movement of je?so'nnel and equipment in the plant under post-accident ' conditions should be acconpanied by radiation dose' rate; surveys to describe a route l

of acceptable dose rates. ,

E. LIMITATIONS AND ACTIONS ,

To obtaini lodine,sparticulate, and noble gas samples l

1.

during ottier thanla post accident condition, proceed l

in accordance with,' Reference 2.

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2. Grab sample 1 (GR AS 1) is us'ed for ootaining the s,,

normal operation lamples in an uns'h'n'elded icainel~ '. '

i and particul ate -f il'ter assemol y. Grab sakple 2 ana

! (GRAB 2) is.used f or'; oot a i ni ng the' 'i ntermed i ate and nigh radi,ation sampics in a shielded s

iodir'e . ano parti cul ate fil,ter assemoly. m

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l LZP-1330-32 Revision 2 May 3, 1983 ,

3 l

l 3. The Station Vent stack sampl e panel t-OPLO4J, and l

the Standby Gas Treatment Vent sample panel, OPLO1J, l

are described in Reference 1 as sample conditioner l

panel s.

l

! 4. The sampling as delineated by this procedure need not De done in tne order listed. However, Steps within a sampling procedure must be followed in order.

F. PROCEDURE

1. To obtain an iodine and particulate sample from the l

l sample panel in an alarm situation, proceed in j accordance with Step F.2. To obtain an iodine ano

's particulate sample from the sample panel in a post-l accident condition, or wnen high radiation level exists in the sampling area, proceed in accordance l

with Step F.3.

!,' s';_ 2. To obtain iodine and particulate samples at the sample panel (sample conditioner), proceed in

-- accordance with the following:

a. Open the electrical enclosure door on either the Station Vent Stack Sample Conditioner,

'" OPLD4J, or the Standoy Gas Treatment Vent Sample Conditioner, OPLO1J. ,

b. Place the REMOTE / LOCAL switch in the LOCAL position. The REMOTE CONTROL DIS ABLED l ight s

should light.

it -

c. Place the FILTER SELECTOR HIGH RANGE switch in the GR A8 2 posi tion. Note the time and log the following information (as appropriate) for entry into the A.A.I.S.:

1) System sampled ano unit.

2) Sample location.

3) Sample tima on.

4) Sample date on.

,~

41 D

< x

LZP-1330-32 Revision 2 May 3, 1983 4 .

5) Stack flow (SGTS or Plant vent).

6) Intitial sample flow.

7) Reactor power, megawatts thermal.

8) Reactor power, megawatts electric.

9) Ini ti al s.

d. Allow the sample to flow for the required sample time as designated oy Rad / Chem Supervision.

a. Place the FILTER SELECTOR HIGH RANGE switch in either the "C" or "D" filter position.

f. Isolate the grab sample, GRAB 2, oy closing the following valves:

1) Grab Sample 2 Inlet Upstream Isolation.

2) Grab Sample 2 Inlet Downstream Isolation.

3) Grab Sample 2 Outlet Upstream Isolation.

4) Grab Sample 2 Outlet Downstream Isolation.

g. Disconnect the sample line from the bracket on the shield assemoly.

h. Release the two quick-disconnect fittings.

l

i. Survey the shield assemoly at approximately l one (1) foot. If tne radiation level is less than 10 ar/hr, proceed to Step F.5. If tne radiation level is greater than 10 mR/hr, proceed in accordance with Step F.1.j.

f j. Unbolt the shield assembly f rom the lower ~

mounting plate.

k. Carefully remove the entire shield assembly and transport i t to tne sample preparation area in accordance witn Step F.4.

3. To obtain an iodine and particulate in a post-accident condition, proceed i n accordance with the following:

- -* * * * - * = - * - = * -='

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" e

L4P-1330-32 Revision 2 May 3, 1983 5 .

a. Open the electrical enclosure door on either the Station Vent Stack Sample Conditioner, OPLD4J, or the Standby Gas Treatment Sample Conditioner, OPLDLJ, and place the REMOTE / LOCAL switch in the REMOTE position, then close the enclosure door.

D. Verify the GRAB 2 sample inlet and outlet valves are open, and there is a clean silver zeolite cartriage and particulate filter in the sample holder.

c. Proceed to the control room to start the sample acquisition.

d. At the gas monitor control panel for the system being sampled, ver i f y the REMOTE CCNTROL l i ght is lit, if it i s not, it will be necessary to bypass the Ilmit switch on the electrical enclosure door on tne sample skids to allow remote control.

e. Press START TIMER for MID-HI. This will allow for up to a 99 second sampling period of the system. This may be repeated at selected intervals during the venting and discharging of gases.

f. Upon completion of the sample acquisition, request the Unit Nuclear Station Operator, NSO, to perform a nitrogen purge of the system sampled to allow removal of the samples,

g. Upon completion of the sample purge, proceed to the sample skia, monitoring dose rates as necessary.

h. Open the electrical enclosure door and place the REMOTE / LOCAL Switch in theLOCAL position.

i. Place the FILTER SELECTOR HIGH RANGE switch in either "C" or "D" fil ter position.

j. Isolate the gran sample, GRAB 2, Oy closing the following valves:

- . _ , - - 9

j . . . _ . .

i LZP-1330-32 Revision 2 May 3, 1983

• b

1) Grab Sample 2 Inlet Upstream Isolation.

2) Grab Sample 2 Inlet Downstream Isol at i on .

3) Grao Sample 2 Outlet Upstream Isolation.

4) Gran Sample 2 Outlet Downstream Isolation.

k. Disconnect the sample l ine f rom the Dracket on the shield assembly.

1. Release the two quick-disconnect fittings.

m. Unbolt the shield assemoly f rom the lower mounting plate.

n. Caref ull y remove the enti re shiel d assembl y and transport it to the sample preparation area in accordance with Step F.4.

4. Move the samples from tne Wide Range Gas Monitor, 786'6" elevation of the Auxiliary Building, to the 710' elevation via the Aux. Bldg. elevator.

5. Move the samples to one of tne following sample p.eparation areas in accordance with tne following:

C_AUTION Movement of personnel and equipment in tne plant unaer post accident conditions should oe accompaniea by radiation dose rate surveys to describe a route of acceptaols dose rates.

a. Chemistry Labs, 710' elevation; most preferred.

However, the dose projections of Referenca 10 show this area to present a hostile raalological l

i envi ronment under post-accident conditions.

' If such is the case, consider an alternate area.

b. Turbine Building Process Sample Panel , 1(2)PL13J; primary alternate. Access is via the Turo.

Bldg. elevator from the 710' elevation to the 687' elevation. The dose projecticns of Reference 10 show this area to De at normal shutdown radiation levels unaer a post-accident condition.

l

LZP-1330-32 Revision 2 May 3, 1983 7 .

c. Feedwater Sample Panel, 1(2)PL40J; seconaary alternate. Access is via tne Turo. Blog.

elevator from the 710' elevation to the 663' elevation. The dose projections of Reference 10 show this area to be at normal shutdown radiation level s i s under a post-accident condition.

6. Prepare the samples for analysis in accorcance with the following:

a. Open the shield assemoly door, and remove tne fil ter assembl y.

o. Remove the filter holder ring clamp, separate and remove the iodine cartriage and particulate i filter.

c. Prepare the lodine cartridge for anlaysis in accordance with the following:

1) Prepare the iodine cartridge for pruging to remove noole gases by placing it in the holder aesigned for that purpose.

2) Attach the tuDing on the cartridge holder to a pressurized air (or nitrogen) source such that the purge flow wi ? 1 oe in the same direction as the initial sa.npl e fl ow (the arrow on the cartridge indicates direction of sample flow and the metal flange i s the inlet side).

3)- Start the air flow tnrough the cartriage at a rate of aoout 16 cfn as inoicatea oy s the flow gage. Allow the cartridge to i purge approximately 5 minutes in a hood with good ventilation flow. Do not exceed 20 minutes for purge time.

, 4) Stop the air flow and remove the cartriage from tne holoer.

5) Seal the cartridge in plastic, taking care i

to ensure that no exccss plastic or tape is on the cottom side (inlet) that must lie flat on the counting snelf (arrow pointing up or metal flange down).

y-. ,.vw-- -- - - - - -

- , ,, , , -,e-

LZP-1330-32 Revision 2 May 3, 1983 -

8

6) Survey the sample with a survey meter at contact and record the mr/hr or dpm on the sample label.

7) Verify the sample is labelea with the following information as appilcaole:

a) System sareples and EPN.

D) Sample time on/off.

c) Sample date on/off.

c) Name of person who prepared the sample.

e) Radiation symool sticker.

f) Survey results.

e. Install new fil ter el ements, and tighten the filter nolder ring clamp.

f. Place the filter assemoly in the shield assemoly anc close and latcn tne shleid door.

i g'. Return the shield assemD1y to the sample conditioner skia and ooit it to the lower mounting plate as necessary.

n. Connect the quick-disconnect fittings and reassemole the tuoing Dracket.

i. Open the four isolation valves closaa in Step F.2.f. or F.3.j.

i I

j. If no further samples are to De taken, return i the REMOTE / LOCAL switch to the REMGTE position.

l k. Close the electrical enclosure door.

7. When reaay for anlysis, transport the samples to an area of low contamination and low oackgrounc for radionuclide analysis in accordance with directions Dy the Rad / Chem Director or Health Physics Supervision.

l l

l l

LZP-1330-32 Revision 2 May 3, 1983 9 -

CAUTION Movement of personnel and equipment in tne plant under post-accident conditions should De accompanied oy radiation dose surveys to oescribe a route of acceptable dose rates.

a. Notify the Shift Engineer if a radioactive sample is to oe transported to the Auxiliary Counting Room for gamma isotopic analysis.

D. Nove any samples to be counted from the 6d7' or 663' elevation to the 710' elevation using the Turo. 81dg. elevator.

c. Transport the sample to the 710' elevation Counting Room if the radiological concitions permit. If the Counting Room cannct ne usec, l trancport the sample to the 768' elevation Aux.

l Counting Room using the Aux. Bldg. elevator.

UQLE The Aux. Counting Room is located in tne southeast corner of the hallway near the Unit 2 Control Room, column R-18 on General Arrangement Print M-7.

d. Notify the Shift Engineer of any raciological l concerns oue to tne presence of radioactive samples in the Aux. Counting Room.

8. Analyze the sample (s) in accordance with Reference 3 or 5, as appropriate.

l 9. Determine the I-131 equi valent concentration using i the Hewlett Packard calculator program in accoroance with Reference 7.

10. If the Hewlett Packard calculator or calculator

program "I-131 Equivalent Concentration" is not

! availaole, calculate the I-131 equivalent concentration of the sample (s) in accordance witn Attachment A.

11. Calculate the iodine release rate, uCi/sec, from i

the vent exhaust in accordance witn the following:

I 1

1

?

l .

l 1 - - - - - - -

l .. . . . . .

t i

LZP-1330-32 Revision 2 May 3, 1983 '

10 Release Rate, uCi/sec = ( I_ t f Fl( 2.81gg4_gc / f t,21 60 sec/ min where: I = Sample I-131 equivalent concentration, l uCi/cc.

F = Ef fluent flow, f t / min.

12. Report the sample results to the Rad /Cnem Director for evaluation. Refer to Reference 8.

13. Route all output data and calculations to Rad / Chem Supervision for review.

G. [H{QKLISTS

(

1. None.

H. TECHNICAL SPECIFICATION REFERENCE 1

1. 3 3.7 11.

t

. . ?- . . - . - - . .. . . . . .

LZP 1330-32 Revision 2 ATTACHMENT A May 3, 1983 11 (Final)

Determination of I-131 equivalent concentration of the containment air grab sample in the event that computer analysis is not available.

1. Determine the I-135 concentration in the containment air grab sample from Step F.3

2. Determine the 1-135 concentration in the containnent air at T , the time at which the release was made to the containment, using the following equation:

= A 1-135 concentration (uCi/cc) at 7 c e-gt Whe re: A = l-135 concentration (uCI/cc) from procedure Step F. 3.

e = 2.718

-I A= 1.724 E-03 min decay const.

t = Sample decay time (min.) - reactor shutdown to analysis AT 3

Determine the concentration of I-131,1-132,1-133 and 1-134 using the following relationships:

l-131 Concentration (uCi/cc) = l-135 concentration x 1.0E-01 l

I i

1-132 Concentration (uC1/cc) = l-135 concentration x 9.23E-01

) = I-135 concentration x 6.85E-01 l-f 33 Concentration (uct/ce) 1-134 Concentration (uCl/cc) = l-135 concentration x 1.846 4 Determine the I-131 equivalent concentration of aII rodine concentration i

in the containment air using the following equation:

Total 1-131 Equivalent = l-131 concentration + (1-132 concentration x 0.036)

Concentration (uCi/cc)

+ (!-133 concentration x 0,27) + (1-134 concentration x 0.017)

~

+ (1-135 concentration x 0.084) l r

I

i. -

l

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