ML19224B253

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Health Physics Procedure 1621.2,Revision 4:releasing Radioactive Liquid Waste from Unit 2
ML19224B253
Person / Time
Site: Crane Constellation icon.png
Issue date: 01/05/1979
From:
Metropolitan Edison Co
To: Mullinix W
NRC/IE
References
1621.2, TM-0087, TM-87, NUDOCS 7906140293
Download: ML19224B253 (20)
v • d • e


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- s TMI DOCLY2NTS

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f METROPOLIT/.N E0ISON COMPANY.

Wilda R. Mullinix, NRC 790614o233

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1621.2 Revision 4 01/05/79

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THREE MILE ISLAND NUCLEAR STATION DO A UFMOW STATION HEALTH PYHSICS PROCEDliRE 1621.2 RELEASING RADIOACTIVE LIQUID WASTE FROM UNIT #2 Table of Effective Pages

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Pace Date R evision Paae Date Revision Pace Date R evi-,n 1.0 10/13/77 0

26.0 51.0 2.0 10/13/77 0

27.0 52.0 3.0 10/13/77 0

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29.0 54.0 5.0 01/28/78 2

30.0 55.0 6.0 10/13/77 0

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32.0 57.0 8.(

08/08/78 3

33.0 58.0 9.0 08/08/78 3

34.0 59.0 10.0 01/05/79 4

35.0 60.0 11.0 01/05/79 4

36.0 61.0 12.0 10/13/77 0

37.0 62.0 13.0 10/13/77 0

38.0 63.0 14.0 08/08/78 3

39.0 64.0 15.0 08/08/78 3

40.0 65.0 16.0 08/08/78 3

41.0 66.0 17.0 10/13/77 0

42.0 67.0 18.0 08/08/78 3

43.0 68.0 19.0 01/05/79 4

44.0 69.0 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recommends Approval Unit 2 Staff Recommends Approval Approval Date Approval Date Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval Date CW Date //S 2 9

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5 Chairman of PARC V, Chairman of PORC

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1621.2 Revision 0 10/13/77 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDUPE 1621.2 RELEASING RADI0 ACTIVE LIQUID WASTE FROM UNIT 2 1.0 PURPOSE This procedure describes the regulations applicable to radioactive liquid discharges to unrestr'cted areas and the monitoring programs designed to ensure compliance with these regulations.

2.0 CISCUSSION 2.1 In releasing radioactive effluents to the Susquehanna River, it is necessary to keep the resulting dose to man and lower biota as low as reasonably achievable.

Therefore, radioactive liquids discharged from the plant are analyzed so that releases will meet Technical Specifications. WDL R-1311 monitors liquid radioactive waste prior to entering the Mechanical Draft Cooling Tower effluent.

RM-L7 monitors liquid radicactive waste after dilution by the effluent from the Mechanical Draf t Cocling Tower (MDCT).

2.2 The instantaneous concentrations of radioactive effluents from Unit to the environment shall not exceed the 10CFR20, Appendix B, unrestricted area MPC's.

2.2.1 The total curies released should not exceed 2.S Ci per calendar quarter per waste producing reactor.

(Exclusive of tritium and noble gases) This limit can be increased to 10 Ci per calendar quarter per waste producing reactor, however, this requires notification of the Nuclear Regulatory Commission h

within 30 days.

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2.2.2 Specific chemical parameters must also be verified on each release of the Waste Evaporator Test Tank or Neutralizing Tank ~

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(pH, Baron, conductivity, alkalinity, solids, and iron).,24 35 i

1.0

1621.2 Revision 0 10/13/77

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2.3 Analyses performed will be in accordance with the Envirornental Technical Specifications.

3.0 REFERENCES

3.1 FSAR, Unit-2 3.2 10CFR20 3.3 10CFR50 3.4 2104-1.11 3.5 2104-4.1 thru 4.6 3.6 Environmental Technical Specifications 3.7 HPP 1720 thru 1722 3.8 HPP 1629, HPP 1625, and HPP 1675 3.9 SCP 1900, SCP 1901, SCP 1913, SCP 1918, SCP 1929, SCP 1930, SCP 1950, SCP 1951, SCP 1958.

3.10 Ir.dustrial Waste Permit No, ^ '70204 3.11 Victoreen Tech. tianual 3.12 HPP 1629.2 4.0 EQUIPMENT 4.1 GeLi detection s:. stem 4.2 Liquid Scintillation detection system 4.3 Sampling container 4.4 Beckman Wide-Beta 5.0 OPERATING INSTRUCTIONS Prior to the release of liquid to the station effluent from the Waste Evaporator Condensate Test Tanks A or B, the Neutralizing i

Tanks or any other tank containing radioactive material; Liquid Release Permit must be obtained.

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1621.2 Revision 0 10/13/77 NOTE:

In these OPERATING INSTRUCTIONS the item number of section 5 will refer to the identically numbered section of the Permit.

5.1 The Shift Supervisor initiates the request for release and is responsible to provide items @ thru@.

5.2 The appropriate box is checked to indicate the specific tank to be sampled, analyzed and released.

5.3 In order that no additional liquid is added to the tanks before the dump is complete, the tank is isolated, and a DO NOT OPERATE tag is conspiciously placed.

The tank level is recorded, and the volume in gallons determined, (conversion charts are kept in the Control Room). The form is then turned over to the Radiation Protection Department for completion of items @ to @.

5.4 The next sequential release number is assigned and recorded in the RECORD OF LIQUID _ RELEASES LOG (see HPP 1675).

5.5 The apprc.7riate box is checked.

5.6 The Radiation / Chemistry Technician /Jr. will sample the dasignated tank in accordance with HPP 1629.2, Health Physics Procedure for Liquid Waste Disposal System Sampling, and/or OP 2104-1.11, Nuclear Plant Sampling.

The sample collector will record the sample location, date and time of sampling on the container.

The sample will be tagged with the appropriate radiation label.

a.

If the tank being sampled is a Waste Evaporator Condensate Test Tank or Neutralizing Tank, the Radiation / Chemistry Technician /Jr.

will take a one liter of sample and save it for preparation of

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the weekly proporticnal composite per HPP 1629.2.

The sample collector will sign his initials in the space available.

195 001

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1621.2 Revision 0 10/13/77 b.

The Radiation / Chemistry Technician /Jr. will also obtain a one gallon sample of each Waste Evaporator Condensate lest Tank or Neutralizing ~ nk to be analyzed for tritium and gamma emitting isotopes (GeLi Scan).

Immediately upon returning this sample to 'he lab the Technician /Jr. will add approximately 75 milliliters of concentrated hydrochloric acid to this gallon sample to preclude the possibility of isotopes plating out on the sample container walls.

After mixing the sample and acid thoroughly, the sample may then be transferred to the counting container.

C.

The Radiation / Chemistry Technician /Jr. will obtain a one liter sample of each Waste Evaporator Condensate Test Tank and/or Neutralizing Tank to be analyzed for pH, conductivity, baron, methyl purple alkalinity, suspended and dissolved solids and total iron.

5.7 The Radiation / Chemistry Technician /Jr. responsible for performing the radiation analyses, and the Radiation Protection Supervisor / Foreman is responsible for approving the data in sections @ thru h.

Both sign in the appropriate locations, after completion of the analysis.

5.8 The date and time of each analysis is recorded.

5.9 The estimated volume to be released is calculated by multiplying the volume in the tank from @ by 3785 cc/ gal.

5.10 Perform gross alpha, gross beta, and gamma analyses in accordance with appropriate chemistry procedures.

Record the number of the f

chemistry procedure used to perform the required analysis in this column. Other chemistry parameters must be analyzed for each release as required in @.

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195 002 f

4.0

1621.2 Revision 2 01/28/78 5.10.1 Gamma Isotopic Analysis - A background must be performed on the counting container to be used for the tank sample analysis.

The background sample will have the same sample volume and co.nttime as the tank sample.

Use Demin. water for the background sample liquid.

Perform a background subtraction from the analysis result in accordance with chemistry procedure 1958.

If the Gamma Analysis is not performed in accordance with chemistry procadure 1958.3, perform steps h thru h.

5.10.2 Gross Aloha Alalysis - The gross c<.is not performed on each batch, howes er, will be evaluated in a prr,portional monthly composite.

5.11 The volume of i. ample counted is recorded.

5.12 The sample c' unting time is recorded.

5.13 The gross number of counts, including background, are recorded.

5.14 The background counting time is recorded.

5.15 The total background counts are recorded.

5.16 The net sample count rate is calculated.

(GROSS COUNTS O)

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(BACKGROUND COUNTS h)

(SAMPLE COUNT TIME h )

(BACKGROUND COUNT TD h) 5.17 The % counting error (2a) is calculated GROSS COUNTS h )

(BACKGROUND COUNTS h)

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SAMPLE COUNT TIME h )2 -(BACKGROUND COUNT TIME O )2 (NET SAMPLE COUNT RATE @ )

5.0

1621.2 Revision 0 10/13/77 5.18 The gamma abundance for the energy listed is tabulated for the nuclides expected to be of importance.

All significant peaks must be identified. If other nuclides are found, or if gammas other than those tabulated are used for the isotopic quantification, the appropriate gamra abundance shall be obtained from TABLE OF Tiid ISOTOPES.

5.19 The Specific Activity (SA' is calculated.

Refer to appropriate SCP for further information, the efficiency of the counter is obtained from charts in the counting room.

(NET SAMPLE COUNT RATE @ )

S.A. =

6 (SAMPLE VOLUME USED)

(GAMMA ABUNDANCE)

(2.22x10 )

(EFFICIENCY OF COUNTER) 5.201% of 10CFR20 MPC's are tabulated.

If other nuclides are identified, enter 1% of the appropriate value from 10CFR20, Appendix B, Table 11, Column 2.

5.21 Enter the ratio of @ to @.

6 5.22 Enter the product of @, @ in cc, and 10 to convert to curies.

5.23 Enter the sum of all items in column @.

5.24 Enter the sum of all items in column @.

This is the total estimated curie content in the tank and will be used to insure compliance with the 2.5 curie per quarter per waste producing reactor specification.

5.25 Analyze tank sample for the following parameters and record results:

2 pH, conductivity, baron, methyl alkalinity, suspended and dissolved solids, and iron.

6.0 195 004 7

1621.2 Revision 4 01/05/79 5.25.1 If chemistry analysis indicates a dissolved solids concentratian

> 700 ppm in the tank, a river water sample (RML7) will ce taken within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reiease to ensure compliance.

If boron concentration is > 125 ppm, oilution flow must be established to ensure < 0.7 ppm at the river water discharge.

Dilution flow shall be set to ensure compliance with the above limits.

5.26 The technician who obtains these samples and performs these analyses, signs in the space indicateJ.

5.27 Record all isotopes (excluding Tritium) identified in the sample by GeLi/MCA analysis.

5.28 Record the specific activity of each isotope listed in h.

(Values are listed in h ).

5.29 Record the monitor (WDI-R-1311) sensitivity for each isotope listed inh.

Values are obtained from Table 1621.2-1.

5.30Entertheproductofhx for each isotope listed in h 5.31 Sum the values listed in h. This is the expected value of the WOL-R-1311 response (above background).

5.32 Determine WDL-R-1311 Setpoints by:

calculating backgrounu limitation for 107. error at 99% confidence level.

If < 0.1 deterr.ine hig alarm and alert setpoints using equations on page 19.0.

If > 0.1, WDL-R-1311 liner shall be decontaminated and setpoints recalculated.

5.33 Determine the dilution factor required based on WDL-R-1311 be dividing the high alarm setpoints by 27 cpm.

7 NOTE:

27 cpm = (9.0 x 10 cpm /pCi/cc)(3.0 x 10-7 Ci/cc) 195 005 7.0

1621.2 Revision 3 08/08/78 5.34 Obtain from the Shift Supervisor the present MDCT flow in gpm from FR-146, the maximum MDCT flow which could be made available if required, any critical time restrictions in the release time, and the MDCT flow which is to be used in the calculations. The MDCT flow shall by >5000 gpm, and credit shall not be taken in excess of 38,000 gpm, as per Tech Spec limits.

The name of the Shift Supervisor supplying this information is to be recorded.

5.35 Minimum MDCT flow (FR-146 Alarm Setpoint) is calculated at 90% of the MDCT Flow recommended in 5.36 Deleted 5.37 Deleted 5.38 The dilution factor determined in is divided by 10 and then compared to the D.F. determined in The maximum of the two is the new dilution factor required.

5.39 The RR Max is computed by dividing the minimum MDCT flow (from 35d by the required D.F. from This RR max is used in NOTE:

If RR max ir <5.55 gpm notify the Shift Supervisor and Radiation Protection Supervisor.

5.40 Record the value of RR Max. (WDL-FR-163o Alarm Sat Point) chosen in 5.41 The actual release is calculated as 90% of RR Max from 5.42 If RR actual is based on MPC/10, liquid waste can be released at a rate greater than or equal to 5 gpm, but less than Use this range of rates in

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5.43 The estimated time period to complete the tank dump is calculated by dividii.g the tank volume from by the actual release rate frem T

195 006 8.0

1621.2 Revision 3 08/08/78 5.44 The estimated reading of WDL-R-1311 is calculated by adding to the background reading of WDL-R-1311.

5.45 The estimated reading of RM-L7 is calculated by dividing by the dilution factor requirtJ from or

, whichever is used plus the background of RM-L7.

5.46 The 2 )propriate data from and are transferred to page one of the permit.

5.47 This section is to assure compliance with the 2.5 curie calendar quarterly limit.

The estimated curies to be dumped this release from is multiplied by 100/2.5 = 40 to obtain the percentage of quarterly limit in this release.

The total curies released to date in this quarter and the last release number tabulated is obtained from the RECORD OF LIQUID RELEASES LOG, as per HPP 1675.

These two percentages are summed.

If the sum is greater than 100%,

dumping of this tank requires notification of the NRC within 30 days, as per the Environmental Technical Specifications.

Radiation Protection responsibilities include filling in all information contained within boxes in parts and WDL-R-1311 Alarm Setpoint from 33A and WDL-FR-1636 Alarm Setpoint from 41 FR-146 Alarm Setpoint from Valve Loading from WDL-FR-1636 Expected Reading from 42 WDL-R-1311 Expected Reading from 45 g

FR-146 Expected Reading from 35d RM-L7 Expected Reading from I95 007

1621.2 Revision 4 01/05/19 5.48 The Radiation Protection Supervisor / Foreman will evaluate the data, check the calculations and recommend the release be approved or disapproved. The Supervisor of Radiation Protection and Chemistry, the Unit Superintendent or designated respresentative will make a similar rt_ view and recommendation.

The final authority and approval for a liquid release rests with the Shif t Supervisor.

Then, and oly then will the tank be released.

NOTE:

Just prior to release of liquid effluent through WDL-V-99, WDL-R-1311 must be proved operable using the installed check source or equivalent.

5.49 Operations is responsible for sections h thru h The alarms and valves are set as indicated.

See Section 6.0 for WDL-R-1311 Setpoint procedure.

NOTE:

MDCT Flow should not be changed durina release unless absolutely necessary.

! 30 Time and date are filled in when release starts and ends.

Tank

. Level and volume at start and completion of release are filled in.

The total gallons of MDCT Flow are calculated r y subtracting the MDCT Flow Totalizer reading at start from reading at end of release.

NOTE:

Immediately prior to starting release, start the sample flow pump for WDL-R-1311.

After terminating the release, stop the sample flow pump for WDL-R-1311.

5.51 Mark the WDL-R-1311, WDL-FR-1636 and FR-146 recorder charts at the beginning and at the end of the release:

Flush WDL-R-131i in accordance with OP.2104-4.2 prior to closing WFL-V-99.

After flush of WDL-R-1311, reset as fcilows:

WDL-R-1311 High Alarm - 4200 cpm WDL-FR-1636 0 gpm Alert -

2100 cpm FR146 50 0 m

10.0

1621.2 Revision 4 01/05/79

5. 2 Should the MDCT Flow have to be reduced, the Actual Release rate will have to be re-calculated as per Results of these changes will be recorded in h.

5.53 Shift Supervisor will supply a new MDCT flow.

The required dilution flow is from h or h whichever is used for this release.

5.54 Shift Supervisor will verify that all data from thru h are complete and accurate.

5.55 The form is then returned to Radiation Protection for completion, transfer of data to HPP 1675 forms, and filing.

Volume is calculated fromdatainh.

5.56 The actual quantity of each nuclide released is a product of Specific Activity from h the Actual release volume from h and 10 6 to convert to curies.

6.0 WDL-R-1311 SETPOINT ADJUST PROCEDURE 6.1 Inform Shi f t Supervisor that the WDL-R-1311 Setpoints will be changed.

6.2 Place the function switch on the WDL-R-1311 ratemeter in the CAL position.

6.3 Push the alert pushbutton on the front of the ratemeter and, while holLing the pushbutton in, set the indicator on the ratemeter to the desired setpoint by turning the adjust knob (labeled " Alert" on front of ratemeter).

Release the button.

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l"5 009 11.0

1621.2 Revision 0 10/13/77 6.4 Repeat 6.5 using the Hi Alarm pushbutton and the Hi Alar 1 adjust

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knob (labeled "Hi" on front of ratemeter).

6.5 Peturn function switch to operate position.

6.6 f40tify the Shift Supervisor that the new setpoints are in effect.

t m ees 195 010 12.0

1621.2 Revision 0 10/13/77 SHIFT SUPERVISOR REQUESTS

'ASE PERMIT TANK IS SAMPLED AND ANALYZED IF WASTE EVAPORATOR CONDENSATE TEST TANK OR NEUTRALIZING TANK, TAKE ONE (1)

LITER SAMPLE AND SAVE IT AS PER H.P.P. 1629.2 RELEASE CALCULATIONS ARE MADE TO ASSURE THAT INSTANTANEOUS OR QUARTERLY LIMITS ARE MET ESTIMATED READINGS ARE CALCULATED FOR EFFLUENT MONITORS APPROVAL TO RELEASE IS GRANTED RELEASE IS MADE.

RELEASE DATA ARE RECORDED CALCULATIONS ARE MADE OF ACTUAL QUANTITY RELEASED l E Of\\

13.0

1621.2 Revision 3 08/08/78 WDL-R-1311 SENSITIVITIES TABLE 1621.2-1 Isotone Sensitivity (CPM /pCi/ml) 8 NA-24 1.9 x 10 7

CR-51 1.3 x 10 8

MN-54 1.0 x 10 8

C0-58 1.02 x 10 8

CO-60 1.92 x 10 7

FE-59 9.62 x 10 7

ZH-65 4.19 x 10 8

KR-85M 1.13 x 10 8

NB-95 i.02 x 10 8

ZR-95 1.01 x 10 7

ZR-97 9.93 x 10 8

I-131 1.27 x 10 7

XE-133 1.15 x 10 7

XE-133M 2.11 x 10 8

XE-135 1.41 x iO 8

CS-134 2.22 x 10 7

CS-137 9.03 x 10 For any isotope not listed, use 9.0 x 10' CPM /pCi/ml

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t93 IF CH A JGES IN FLOTJ CRO:a THE '?.CCT (OR CH ANGES 17:THd 9EL 3,

~i -

394s,/B::cn: ce) DEVELOP '

Dunt.NG THE CELEAE. C.*.LCULATION OF. A i:EVI. R ATE thO SETFO!! TST. UST GE !.: ACE. THE f CY! CALC;. L-A

-. TiONS Vi!LL GE COIN UTED CY ? AGE 2 OF.THIS FO".?.*,, :D THE FOLLOY1: !G TA5LE 7

~

PLETEO' i

STOP I

, START' _

- TIME k

TO TA ta' ' ~

'ACTUAt.

'I T!P.tE :^

F rt.113 APPROVAL O'

' Tit / E ' '

GC-l.E ASE P. ATE i i

SET I'OfNT b III IO!?$7 U#IN SW*

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s 77' RE LCASE O..T.' CO:.DLIl CO V Y

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1 ~fALS.

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SPECIAL OPER ATION CALCULATIONS legl,2 3

q t/ FOR U+: EXPECTED CHANGES !?! THE ',tOCT FLOW OR ACTUAL RELEASE R ATE 1HE FOL.v..!NG CALCL'LAT:0!:3 f.'JST BE RS CO*.*f'UTED BY THE ShlFT SUPERVISOR. THIS NEED CNLY eE CONE IF THE MCCT FLO.V IS REOUCf 1

1. MA/.iMUM R ELEASE RATE = WDL-FR-1636 Point R R - M A L- = NEW MCCT FLOW GPM x (0.9)

GPM

=

REQUIRED O.F.

2. ACTUAL
  • RELEASE RATE = (RR MAX) x (0.9) =

GPM

3. MINIMUM FLOW FROM MCCT (FR 146 SETPOINT) = NEW McCT FLOW x (0.9) =

GPM USE THIS AREA FOR CALCULATIONS.

Cl!EilISTRY PARNIETERS Sample Cbtained By:

Analysis Perforced By:

Da te/ Time:

Date/ Time:

RESULT L DitT (1) ol!

4.5 - 9.G (2)

Conductivity

<10 unho (3)

Baron 125 PP;1 flethyl Al'<alinity 100 ppt as CACO 3

l

[

ke j Suscended Solids i

I <560 PP'1

?

(1) 5 Dissolved Solids

<700 PI'"

(1) l Iron

< 7 PP!;

I, 1.

Limit a t' tank t> irsve not ey.ceedir.c li: l' of G-0 pil at plant discharge..._

2.

!!ust be < ige.co to c.casider u :er wi th & NI loss t:ica G or nee =ter taan 9.

If conducti.~ity is > IOunnos, release cust be aproved b; Chcci:tr" Su::-rvisnr orhisdesiencet.1chaseri;te,.cycluci.snctuachedtorelecsclg.{L4 Guideline to assu c.7 p,.T.i afcer dilution.

3.

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ivci.c Revision 3 08/08/78 f!NIE OF

.C..U T cT. C,,f f r> T_.O../ t q q y

.r

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35 CC:; TACT SHIFT S'.!F2?'.'.,!19 FO? 00 LLC.'1I::G DATA CO ;TACTED a ).a. : q.. n r -

r

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b)l..y

.......,...,..s:--

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.: n m uw _

r. _ _

n_

_uu s

d) [1DCT Fio. to use for CALCULATIC:;5.

m (must be > 5000; <33000) 36 illitI?'U
I'OCT = FR-i "5 ALAR
SETFOI:;7 = (0.9)(:'.DCT Flcw Frca 35d )=

@ REVISE 0 CALE ATIL:!3 FO?. ?.PC/10:

{D.F. FRO.-l 23

}

10 H

D.F. FRC:1 @ {

[/.AXII U:4 =

@ 14AX. RR = (l:I.'ll'OCT

_1 66; f

Gr4 _- R.R..s.3

--- J -

.r

{ REQ. iR:.0 C..r. t nV:i L',: :-

}

GO,6 0 4,i

@ RR I4AX. =

12P:4 (E.55 to 50 GPI:) = WDL-FR-1635 Alarm Setpoint

@ RR Actual = (0.9) (RR l'AX) = l__.

_ ____-} GF;4 (5 to 45 GP:4)

@ IF RP. Actual is based on tiFC/10, Licuid Uaste can be released at a rate j

grea ter th':1 or cquai to 5 GF:1, but less tr.:n @.

Use this rar.gc cf i

ra tes in (6' -

@ Estimated time of dump = (Est. Vol. to ce du-ced from (37 call _-

u

(

GP;'-R.4-Ac tu a l l @

@ Estinated Reading of WDL-R-1311 2CF:1 (Frem 0,2.i

) +;

iCP 4 /Backgrour.d) =

\\

I CPIi s

s

@ Estimated Reading of Rii-L7 1

{

l CPti (Es t. Reading of WDL-R-1311 ) +

CF:4 ('Ui-L7) =

CFi4

{ Required D.F. Frca 39

}

195 016 18.0 6

1621.2 Revision 4 01/05/79 Q8)

Q QQ Ql)

Isotopes Identified Specific activity Sensitivity of Monitor Response by Analysis (From 19 )

WDL-R-1311 to Each (CPM)

(txclude 11-3) pCi/ml Isotope (From Table 1621.2-1) b Z=

Estimated Reading of WDL-R-1311 above background h

WDL-R-1311 Setpoint A.

BACKGROUND LIMITATION FOR 10% ERROR 1.

e = 3/ (Monitor Response

) + {(2)(Bkg

)}

=

2.

(e

}/(Monitor Response

)=

NOTE:

If this is > 0.1, WDL-R-1311 liner shall be decontaminated and set points recalculated.

B.

_4IGH ALARM (2) {(Monitor Response

) + (e + Bkg ,= C. ALCRT (Monitor Response ) + (Bkg ) + (e )= h Required Dilution Factor based on WDL-R-1311 WDL-R-1311 Hiah Alarm 27 cpm 195 017 19.0

}}
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