ML20079K538

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Rev 10 to Procedure 1904.004, Estimating Airborne Release Rates
ML20079K538
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/15/1991
From:
ENTERGY OPERATIONS, INC.
To:
References
1904.004, NUDOCS 9110230121
Download: ML20079K538 (20)
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Text

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1 ENT ER 6Y OPERATIONS I NC O RPO R A TE D 1 i

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N' RGY ARKANSAS NUCLEAR ONE TITLE: ESTIMAr1NG AIRSORNE REI.EASi, RATES PROC / WORK PLAN REV.

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NO. 1904.004 le _

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DT SAFETY RELATED yp YES@ NO C J -

Page 1 of 1 Page Rev Chgl Page Rev Chg l Page Rev Chg lPage Rev Chg 1 10 17 10 2 10 18 10 3 10 4 10 5 10 6 10 7 10 v

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, ,9 10 10 11 10 12 10 13 10 14 10 15 10 16 10 Approval Authority: Approval Date: ,e - g S /

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FO)DA TITLd: LIST OF AFFECTED PAGES FORM NO. 1050.006A g

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

4-P.,0C, WORK PLAN NO, ARKANSAS NUCLEAR ONE i 1904.004 Operat'oris EPirSERIES TITLE:

OrrSI1E PROCEDUREWORK PLAN TITLE: PAGE: 1 of'18 nev: 10.

DOSE PROJEC ESTIMATING AIRBORNE RELEASE RATES CHANGE: )

1.0 PURPOSE l

The purpose of this procedure is to provide radioactive release rate  !

estimafes for rclease points which do not have functioning SPING detector systems or release points which require local readout / sampling from the SPINGS.

2.0 SCOPE This proceduce is applicable to airborne radioactive releases monitored by the SPINGS but for which the SPING data is unable to be acquired by Radiological Dose Assessment Computer System (RDACS). This procedure also applies to containment leakage, Main Steam Line Radiation Monitors and other "unmonitored" releases.

3.0 REFERENCfJ 3.1 References used in procedure preparation:

3.1 1 " Meteorology and Atomic Energy," Slade 3.1.2 " Manual for Protective Actions," Environmental Protection Agency 3.1.3 Memorandum Number CL-2126 (A. Smith to File)

, 3.1.4

- ?' Detecter Calibration Curves (Supplied by Nuclear Chemistry and I&C) 3.1.5 ANO-1 and ANO-2 Integrated Leak Rate Test Reports, Bechtel Power Corp.

3.1.6 AIMS System Manual, Document No. AIMS-M-20, Applied Physi-cal Technology 3.1.7 Memorandum Number N0D-84-105 3.1.8 Calculation Sheet No. 89E-0029-01 and 89E-0029-02 (Steam Line Monitor Calibration Factors).

3.1.9 AND Condition Report 1-90-73 3.2 References used in conjunction with this procedure:

l 3.2.1 1904.002, "Offsite Dose Projections-RDACS Computer Method"

-3.3 Related ANO procedures:

l 3.3.1 1604.051, "Eberline Radiation Monito.ing System" 3.4 i

Regulatory correspondence containing NRC commitments which are implemented in this procedure:

None I

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

-e:

Pt.OC. WOh PL AN NO, 4.

u Entergy ARKANSAS NUCLEAR ONE gg gg SEFaES TITL E: PROCEDUREJWORK PLANTITLE: P E: 1904.004 EPIP OFFFt1E

/ "E PR"!EC cHA90t: jo

""T! MATIN 0 A+Ri; GENE Rett /s5E wi,3

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4.0 RESPONSIBILITY AND AUTil0RITY 4.1 The Shift Operations Supervisor or his designeo is responsible for. initiating this procedure as leng as Dose Assessment functions renain in the Control Room.

4.2 The Dose Assessment Supervisor is responsible for initiating this procedure once the Dose Assessment Team has been established at the Emergency Operations Facility.

5.0 LIMITS AND PRECAUTIONS 5.1 The radiological release rata data source selected should be the best available. Data sources are listed below in order of preference:

5.1.1 RDACS SPING detectors. See Table 1.

5.1.?

Portable instrumentation and grab sample analyses 5.2 It is only necessary to calculate steam release rates if conditions exist as described on Forms 1904.004G and 1904.00411,

-5.3 It is only necessary :.o calculate containment atmospheric leakage

. release rates if condition exists as described on Form 1904.004C.

, 6.0 INSTRUCTIONS.

6.1 Determination of Release Rates using SPINGS NOTE:

This section is to be used when releases are occurring via the SPINGS

-RDACS.

but for someM reason, this data is not being supplied to 6.1.1 SPINGS. Operable A.

Using Form 1904.004I, "SPING Release Rate Worksheet",

proceed to the SPING affected to take appropriate readings.

B.

Record the isotopic activity for the noble gas, iodine-and particulate.SPING channels and calculate a release rate for each in C1/sec.

C.

Document these values on Form 1904.0028 for processing into RDACS.

. . . .. - - - . .= - -- . _ . .- . - . ~ . .. --

PROC, WORK PLAN NO.

g ARKANSAS NUCLEAR ONE Opefat<xis SERIES TATi.E:

EP:P OFFSITg PROCEDURE WORK PLAN TITLE: ' PAGE: of 8 REV: gg DOSE PROJEC

,-u:

ESTIMATING AIRBORNE RELEASE RATES CHANGE:

k_, 6.1.2- SPINGS Aneperable '- Grab Samples Availabla

, A. If'a release is occurring via a known SPING and the SPING is inoperable (i.e. , no indirect or direct readouts available) grab samples may be obtained directly off of the SPING. This should be performed in accordance with normal Nuclear Chemistry procedures and only as radiation levels permit.

B.

Obtain grab samples from the SPING and analyze them in accordance with normal Nuclear Chemistry procedures.

Record values on Form 1904.0041.

C. Onco release rates have been determined, document this data on Form 1904.002B for processing into RDACS.

6.1.3 SPINGS Inoperable - Grab Samples Unnva11able NOTE:

If a known release is occurring via an inoperable SPING and radietion levels prohibit grab sampling, llealth Physics pgrsonnel shall be disostched offsite to assemm_ downwind dom O

~^-)

i A. If radiation levels prohibit sampling of the SPINGS, contact the Doae Assessment Supervisor /Shif t Operations Supervisor and inform of conditions.

B. Complete Form 1904.004F in accordance with Section 6.4 of this procedure. -

6.2 ANO-1/ANO-2-Containment Leakage NOTE:

Complete this section only when leakage is occurring in the Reactor Building and Failed Fuel is beine indicated.

6.2.1 Request Nucinar Che:alstry to analyze the atmosphere of the affected containment building for total iodine concentration (pC1/cc I-131 dose equivalent) ard total noble gas concentration (pCi/cc as Xe-133). Record the results on Form 1904.004C.

NOTE:

}

PASS / AIMS minimum detectable concentrations are approximately I 1E-4 uC1/cc for all radionuclides. ..

6.2.2 Complete form 1904.004C to estimate the lodine' and noble gas release rate from this source. Copy the results on

/] the line marked "U01 1/ Containment Leakage" or "UO2 k_/ 2/ Containment Leakage" (depending on whether it is Unit 1 or Unit 2) on Form 1904.002B.

i L

I 1 ,.

g" ARKANSAS NUCLEAR ONE PROC.WOHK PLAN NO.

$ SERIES TITLE: PROCEDUREWORK PLAN TITLE: PAGE:

EPJPOFFSI}E egayog: 10 DOSE PROJEQ ESTIMATING AIRBORNE REffARP DATrc

-(%

6.2.3 Once the appropriate forms are completed, refer to Procedure 1904.002, Section 9.6, to enter the calculated release rates

. Into RDACS.

6.3 "Unmonitored" Releases Haasured Indoors 6.3.1 Instruct the Health Physics staff to obtain air samples in the af fected area and analyze for I-131 in units of pC1/cc. Record the results on Forv 1904.004E.

6.3.2 Instruct the Nuclear Chemistry staff to obtain an air sample in the affected area and analyze for Xe-133 in units of pC1/ce.

Record the results on Form 1904.004E. (Suggested sampling techniques for obtaining this sample are by use of a water-filled winkler or use of a 5cc gas vial and syringe.)

6.3.3 Determine the area ventilation discharge flow from Heating 6 Ventilation drawings, direct measurement, or other means.

Record the discharge flow on Form 1904.004E.

6.3.4 Complete Form 1904.004E to estimate the iodine and noble gas release from this source.

6.3.5 Copy the results on the line marked "UO3 Unmon. Measured

' Indoors" on Form 1904.002B.

6.3.6 Once the appropriate forms are completed, refer to Procedure 1904.002 Section 9.6, to enter the calculated release rates into RDACS.

6,4 "Unmonitored" Releases Measured Outdoors 6.4.1 Direct Health Physics to determine the approximate plume width in feet and the maximum radiation readings in mR/hr at a convenient downwind distance using a survey meter which is primarily sensitive to ramma radiation. An air fodine sample should also be taken along the plume centerline.

6.4.2 The effect of direct radiation (" shine") from the source can be subtracted by measuring the "hackgrour.d" radiation an. equivalent distance upwind from the source.

6.4.3 Determine the current windspeed from the control room recorders, the RDACS terminals, or other source as described in Sections 9.4 of Procedure 1904.002, "Offsite Dose Projection -RDACS Computer Method."

6.4.4 Using Figure 1 of this procedure, determine the finite plume correction factor and record on Form 1904.004F.

6.4.5 Complete Form

-O(f 1904.004F to estimate the lodine and noble gas release rates from this source.

m W Entergy ARKANSAS NUCLEAR ONE Pf40C. WORK PLAN NO.

OPerat ons SERIES TITLE:

EPIP OFFS nt PROCEDUREWORK PLAN TITLE: PAGE:

nrv 5 of 18 30 DOSE PROJE0 ESTIMATING AIRBORNE RELEASE RATES 6.4.6 Copy the results on the line marked "UO4 Unmon.

Outdoors" on Form 1904.002B, Measured 6I4.7 Once the appropriate forms are completed, refer to Procedure 1904.002, Section 9.6, to enter the calculated release rates into RDACS.

6.5 Contaminated Steam Releases NOTE lt is only necessary to calculate steam release rates if conditions exist as described on Forms 1904.004G and 1904.00411.

6.5.1 Complete Form 1904.004G if the contaminated steam release l involves Unit 1. Otherwise, continue at Section 6.5.2.

6.5.2 Complete Form 1904.00411 if the contaminated steam release involves Unit 2.

6.5.3 Once the appropriate forms are completed, refer to l Procedure 1904.002, Section 9.6, to enter the calculated release rates into RDACS.

7.0 ATTACilMENTS AND FORMS 7.1 Form 1904.004A - Deleted 7.2 Form 1904.004B - Deleted 7.3 Form 1904.004C " Containment Atmosphere Leakage" 7.4 Form 1904.004D - Deleted 7.5 Form 1904.004E "Unmonitored" Releases Measured Indoors" 7.6 Form 1904.004F "Unmonitored" Releases Measured Outdoors" 7.7 Form 1904.004G

" Unit One Contaminated Steam Release Rates" 7.8 Form 1904.004H

" Unit Two Contaminated Steaa Release Rates" 7.9 Form 1904.004I "SPING Release Pate Worksheet" 7.10 Table 1 "SPING Monitors at ANO" 7.11 Figure 1 " Finite Plume Multiplication Factor" O l

m h Entergy ENTERGY OPERATIONS INCORPORATED operat ons ARKANSAS NUCLEAR ONE 6 or is

( DEI.ETED) l I

FORM TITLE:

FORM P40.

j REVS,5, g ,

l ANO-1 NORMAL-RANGE MONITORS 1904.004A #' to l

Entergy ENTERGY OPERATIONS INCORPORATED

- operations ARKANSAS NUCLEAR ONE ,or33

'kv (DEI.ETFD) b O

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l-l O

FOHM TITLE:

M NO. REv-10 ANO-2 NORMAI,-RANGE MONITORS 1904,004B Ag it, .u

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ntergy ENTERGY OPERATIONS INCORPORATED operations ARKANSAS NUCLEAR ONE a or in O [pggg)g E8E 2 Of 2

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b FORM TITLE:

ANO-2 NORMAI,-RANGE MONITORS 1904.004B 80441

-Entergy

~~ ENTERGY OPERATIONS INCORPORATED operations ARKANSAS NUCLEAR ONE 9 of 18 l

( >t- NOTE Complete this form Daly when leakage is occurring in the Reactor Building and railed Fuel in being indicated.

1.0 Circle the af fect ed unit: ANO-1 / ANO-2 2.0 Record contair: ment sample timi date:

3.0 Record the integrated containmr 'eak rater (m*/sec)*

4.0 Record the containment iodine concentration:

(pCJ/cc I-131 D.E.)

5.0 Record the containment noble gas concer.tration:

__ (pCJ/cc as Xe-133) 6.0 Estimate the lodine leakage rate:

Q-iodine a line 3.0 x line 4.0 = (Ci/Sec) 7.0 Estimats the noblo gas leakage rate:

Q-gas = line 3.0 x line 5.0 =

(C1/Sec) 8,0 Enter the calculated release rates (01/sec) into RDACS using section 9,6 of n Procedure 1904.002.

. \.s)

  • NOTE: Integrated containment leak rate for ANO-1 war 2.64E-3 m'/sec as of 11/9/88. Int egrated containment leak rate f.it ANO-2 was S.99E-4 m*/sec as of 4/22/88.

Performed Dy: /

Inf. t ia l Time Reviewed By: __

i l

O FORM TITLE:

CONTAINMENT ATMOSPHERE LEAKAGE FORM NO. 1904.004C RIN.

10

\

h Entergy ENTERGY OPERATIONS INCORPORATED operations ARKANSAS NUCLEAR ONE 20 or is t

1.0 Source location:

2.0 Measurement time & date: /

Timo Date 3,0 Area noble gas concentration _ (uCi/cc as Xc-133) 4.0 Area cirborne radiolodine conen aration (pct /cc as 1-131) 5.0 Area total ventilation discharge flow (CFM) 6.0 Estimate Q gas for this source:

(pCi/cc) x (CFM) x 4.71E-4 8 Line 3.0 Line 5,0 7

=

(01/Sec)

Q gas 7.0 Estimate Q-Iodine for this source:

(pC1/cc) x (CFM) x 4,71E-4 E Line 4.0 Line 5.0 m =

(Ci/Sec)

(v) Q-lodinn 8,0 Entnr the calculated release ratas (Ci/sec) into RDACS using sect ion 9.6 of Procedure 1904.002, Performed Ily: /

Inittal Time Reviewed By: _ _ .

FORM TITLE: FORM NO, REV. lO "UNMONITORED" RELEASES MEASURED INDOORS 1904.004E %j

h Entergy ENTERGY OPERATIONS INCORPORATED operations ARKANSAS NUCLEAR ONE ii of 18 C'\

1.0 Source location:

2.0 Measurernent time & date: /

Time Date I, . 0 Distance from source: (ft) 4.0 Plume width at this distance: (ft)*

NOTE: One mile = 5280 feet.

5.0 Maximum gamma dosn rate at this distance: (mR/hr) 6.0 Maximum lodine concentration at this distance: (pCi/cc as 1-l31) 7.0 Gamma dose rate at the equivalent upwind distance: (mR/hr) 8.0 Current windspeed: mph 9.0 Based on the plumm width on line 4.0, read and record the finite plume cor-rection factor from Figure 1 for a plume of this widt.h:

10.0 Est!. mate Q gas for this source:

a 79 [ (ft)]

x (3.0E-7} x I  !'" *

(m h r._M x Q

~

  • _ .

Line 4.0 Line 5.0 Line 7.0

( (mph)l , [ _ l = ._,_ (C1/Sec)

Line 8.0 Line 9.0 Q-gas 11.0 Estimate Q-Iodine for this ssurce:

[ ( f t ) ) x 8,16E-3 x _. (pCi/cc) x _ (mph) = (Ci/Snc)

.ine 4.0- Line 6.0 L(ne 8.0 Q-Iod'.no 12.0 Enter the calculated releav e rates (C1/sec) into RDACS using section 9.6 of Procedure 1904.002.

Performed By: /

Initial Date Reviewed By:

  • Caution: This unit is squared in the formulas indicated in Steps 10.0 and 11.0

/^

U) 70RM TITLE:

FORM NO. REV.gg "UNMONITORED" RELEASES MEASURED OUTDOORS 1904.004F (,g

= Entergy

~~

ENTERGY OPERATION'L INCORPORATED operat ons ARKANSAS NUCLEAR ONE 22 -,r i8 Page 1 of 2 NOTE Cort:lete the following tables nIlly i f the N-16 Monit ors (RE-2691 and RE-2692) or thn Condenser Offgas Monitor (RE-3632) are indicating a possible Primary to Secondary leak gitd a stenm release is occurring.

l Steam Safety Lift Time Steam Safety Stop Time TABLE 1 _

RADI ATION_. liQRIIDF RI-2681 IJEIFK I.lDMS 1 Monitor Reading (niR/hr): Monit or Readout in Control Room 2 _ Background (mR/hr): Obtain previous reading from Form 1015.03A-9 prior to incident 3 Net Mon. Reading (mR/hr): Item 1 minus item 2 4 No. Safeties Open 2; Unless verified otherwise 5 lb/hr per Safety: 8.0 E5 Constant 6 Steam Flow (lb/br): Item 4 x Item 5 7 Mon. Cal. Factor: L38 E-6 Constant 8 Release Duration (min):

  • See note below l 9 10 min. avg. Q-Gas (C1/Sec): Item 3 x Item 6 x Item 7 (Item 8+10) 10 Q-Gas /Q-lodine Ratio: If Failed Fuel, obtain RCS value from (xe-133) (1-131 D.E.) Nuclear Chemistry; otherwise, 7.2 E-7 for normal operations l 11 10 min. avn. 0- I od in e (C1/Ses): Item 9 x Item 10 TABLE _? _

RADIAllON M011.IQ8.RI-2682 INSIFUCTIONS 1 Monitor Reading (mR/hr): Monitor Rondout from Control Room 2 Background (mR/hr): Obtain previous reading from Form 1015.03A-9 prior to incident 3 het Mon. Reading (mR/hr): Item 1 minus Item 2 4 No. Safeties Open: 2; Unless verified otherwise 5 lb/hr per Safety: 8.0 E5 Constant 6 Steam Flow (lb/br): Item 4 x Item 5 7 Mon. Cal. Factor: 2.38 E-6 Constant 8 Release Duration (min):

  • See not e below 9 10 min, avg. Q-Gas (Ci/Sec): Item 3 x Item 6 x Item 7 x (Item 8+10) 10 Q-Gas /Q-Iodine Ratio: If Failed Fuel, obtain RCS value from (Xe- 133) (1-131 0.E. )

Nuclear Chemistry; otherwise, 7.2 E-7 for normal operations 11 10. min. nygd LodileJC1/ Sec) :

l ltem 9 x Ilem_10

  • Relense duration is the time that the steam release was in progress. If the steam safetien continue to intermittently lift and resent, obtain an estimate of the release time f rom the Shif t Operations Supervisor. Release rate calculations are calculated as 10 minute averages. If the time duration exceeds O 10 minutes, you must process additional segments in RDACS in 10 minute average blocks.

FORM TITLE:

' FORM NO. REV.

UNti ONE CONTAMINATED STEAM RELEASE RATES 1904.004G 10

& ntarav

~~ E ENTERGY OPERATIONS INCORPORATED opera'tlons ARKANSAS NUCLEAR ONE 33 of is Page 2 of 2

_._lAELE 3 -

__IQIAL RELEAFLETES

  • _lRSlR KT1GSS_

l Total 10 Minuto Averaged 1

T<ible 1 (Line 9) +

Q-Gas (C1/Sec): T a b i c 2 ( l.in e 9) l 2 Total 10 Minute Avnraged Tabin 1 (I. inn 11) +

Q-Indioe (C1/Sec)_: ..Inhia 2 (Line__11]

l

  • Refer t o Procedure 1904.002, Snction 9.6 to enter the calculated release rat es into RDACS.

I Performed by: Date/ Time:

Reviewed by: Date/Timn:

O O

FORM TITLE:

FORM NO.

REV.lQ UNIT ONE CONTAMINATED STEAM RELEASE RATES ,

1904.004G Xps g

_ _ _ _ - _ - - - _ _ - - _ - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ ~~

i

~~ - Entergy

~~

ENTERGY OPERATIONS INCORPORATED l -

operations ARKANSAS NUCLEAR ONE in or 18

\

r Page 1 of 2 NOTE Complete the f ollowing tables caly if the Steam Generator Moniters (2RE-5854 and 2RE-5864) or the Condenser Offgas Monitor (2RE-0645) are indicating a possible Primary to Secondary leak and a steam release is

... occ.yuine .

I Steam Safety Lift Time _, Steam Safety Stop Time

. TABLE 1 RADi&IlDXJQNITOR _ZRITS- 1007 INSIREGILONS 1 Monitor Reading (mR/hr): Monitor Readout in Control Room 2 Background (mR/br): Obtain previous reading from Form 1015.03B-10 prior to incident 3 Net Mon Reading (mR/hr): - Item 1 minus Item 2 4 No. Safeties Open: 1; Unless verified otherwise 5 lb/hr por Safety: 1.5 E6 Constant 6 Steam Flow (Ib/hr): Item 4 x ltem 5 7 t!on. Cal Factor : 1.91 E-6 Constant 8 Release Duration (min):

  • Sne not e below l 3 10 Min. Avg Q-Gas (C1/Sec): Item 3 x Item 6 x Item 7 x (it.cm 8+10) 10 Q-Gas /Q-Iodine 14tio: If Failed Fuel, obtain RCS value from (Xe-133) (1-131 U.E.) Nuclear Chemistry; otherwise, 2.5 E-7 O,' for normal operations l _11J .0 Min. Ayg E qsling (C1/Sec): Item 9 JLittn_,19 TABLE 2 EADIATION MONITOR 2RITS-1057 __lLTTRi!CJ10NE 1 Monitor Reading (mR/hr): tion ttor Rei dont in Control Room 2 Background (mk/br): %tain previous reading f rom Form 1015.03B-10 prior to incident 3 Net Hon. Reading (mR/hr): Item 1 minus item 2 4 No. Safeties Open: 1; Unless verified otherwise 5 lb/hr per Safety: 1.5 E6 Constant 6 Steam Flow (Ib/br): Item 4 x Item 5 7 Mon. Cal Factor: 1.91 E-6 Constant b Release Duratibn (min):
  • See not e below l 9 10 Min. Avg. Q-GTs (C1/Sec): Item 3 x Item 6 x Itein 7 x (Item 8+10) 10 Q-Gas /Q-Iodine Ratio: If Failed Fuel, obtain RCS value from (Xe-133) (I-131 C.E.) Nuclear Chemistry; otherwise, 2.5 E-7 for normal operations l 11 10 Min. Avt. 0-Iodine (C1/Sec): Item 9 x_Ilam 10
  • Release duration is the timn that the steam release was in progress. If the steam safeties continue to intermittently lif t and resent, obta in an estimate of the release time from the Shift Operations Supervisor. Release rate caluclations are calculited as 10 minute averages. If the time duration excneds 10 minutes, you must process additional segments in RDACS in 10 minute average blocks.

FORM TITLE:

FORM NO. REV.

UNIT TWO CONTAMINATED STEAM RELEASE RATES 1904.00411 10

-:::.ntergy E ENTERGY OPERATIONS INCORPORATED operct ons ARKANSAS NUCLEAR ONE is a in O l'n ge 2 o f 2

_._IABLE 3 ,

___.JDIALKELTASLKA103

  • INIIKCCIIRNS l 1 Total 10 Minu'o Averaged. _ - Tnble 1 ( 1,i n e 9 ) +

Q Gns (Cl/Sec'; _

__ intile 2 (1,ine 9) l 2 Total 10 Hinuto Averngeil Table 1 (l.ine 11) +

0-lud1DLLGi/lti h_ Tab 1LZ._f L1rie.11 )

l

  • Re f er to l'rorcriure l'104. 002. Sec t .4 cn 9. 6 t o enter the eniculat ed rolonen rates into KDACS.

I Performed by: _ _

tsa t e/ T.ime : __

Reviewed liy: ___

Da t e/ Time _ _

FORM fiiLEa FORM NO.

REV,10 UNIT TWO CONTAMINATEn STEAM KEl. EASE RATES 1904.00411 M'g,g..tt

~Entergy ENTERGY OPERATIONS INCORPORATED

~~

i operat ons ARKANSAS NUCLEAR ONE u, or in O 1. Affected SPING: ,

2. Flow Rate (Circle the appropriate datn source): _ CFM A. Chnnnel 10 B. Flow Recorder C. lief ault flow Kat e from Tabln 1
3. Inntopic Act ivit y (Ultcle the data channel or sourec)

A. Noble Ong (Channel $, 7, 9, Sample':* , pel/cc B. lodine (Channel 3, Sample): . _ .,.. pci/cc C. Particulate (Channel 1, Snmple): pci/cc 4 Relenne Raten **(Cl/sec)

A. Noble Gast _

D. todinn:

C. Particulate:

5. Once the release r ates hnvo been det et mined in St ep 4 above, document this data on form 190!. 0028 for proconsing into RDACS.
  • The Noble Gan Channel shoeld be rend beginning with Chnnnel S. If l Channel ( la in "rnil lit", proceed to Channel 7 If Chnnnn! 7 l

18 in "Ta i l 111", proceed to Channel 9. Recond the appioprinte value,on the noble gan release rate line.

    • Ci/sec = Flow x pel/cc + 2119 (Line 2) (I.ine 3)

O FORM TITLE:

FORM NOJ REV. lO SPING RELEASE FATE WORKSilEET l904.0041 $h.u

..,.._.x

.. - _ . -- - - . - .n - . . _ - - . - _ . -

e PHOC. WORK PLAN NO.

ARKANSAS NUCLEAR ONE i ~ Entetgy

~~~

19 4.onA Operat ons SE RIES Ti1L E:

EPIP OrrStTg PHOCEDUREWORK PLAN TITLE: PAGE: j7 of }g REV' DOSE PROJEC 10 CHANGE:

EST1 HATING AIRBORNE RELEASE RATEh TABLE 1 SPING MONITORS AT AND SPING DESIGNATION DETAULT SPING MONITOR NUMBER FLOW RATES (CTM)

ANO-1 Containment Purge Rx-9820/Honitor 1 30000 ANO-1 Radwaste Area Rx-982S/Honitor 2 33000 ANO-1 Fuel Handling Area Rx-9830/Honitor 3 39000 ANO-1 Penetration Vent Rx-9835/ Monitor 4 1850 ANO-2 Containment Purge 2Rx-9820/Honitor 5 39700 l ANO-2 Radwesto Area 2Rx-9825/Honitor 6 53200 ANO-2 Fuel Handling Area 2Rx-9830/Honitor 7 39700 ANO-2 Penetration Vent 2Rx-9835/Honitor 8 2000 PASS Building 2Rx-9840/Honitor 9 4000 ANO 2 Aux. Bldg. Extension 2Rx-9845/Honitor 10 14000 l Radwaste Storage racility 2RX-9850/Honitor 11 10000 0

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