ML16277A122

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ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points
ML16277A122
Person / Time
Site: Beaver Valley
Issue date: 04/20/2015
From: Renz L
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
ERS-LMR-14-001, Rev 1
Download: ML16277A122 (10)
v • d • e


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RTI :it. AQ R?1A Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation Subject No.

PAGE 1 OF Liquid Monitor Alert Emergency Action Level (EAL) Set ERS-LMR-14-001 Points 10 Reference HPP EPP : NEI 99-01 rev 6 TIS CR DCP Category Unit 1 Unit 2 D Technical Position

  • Technical Evaluation D Calculation

[81

[81 Purpose NEI 99-01 Revision 6 changed the methodology for calculating Alert set points for Liquid Radiation Monitors. The previous Alert set points were to be 200 x ODCM set points. However, they are now to be calculated for 10 mrem TEDE or 50 mrem thyroid COE.

Note: This Technical Evaluation is not an implementing document Any application of the information contained herein must be reviewed and approved using the established review/approval process for that application.

D ORIGINAL ISSUE

~ REVISION#

I Made correction to page 3: annual drinking water ingestion volume of 730 liters per year, not per day.

by che~ke~r independent review (calculation

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Checklist Attachments

  • Purpose
  • Results 11 Data Sheets
  • Methodology
  • References D Illustrations
  • Input Data D Printouts D Code Listings
  • Transmittal to BVRC D Supt, Rad Ops
  • Author: Dr. Lara Renz
  • John Lebda D MGR, Radiation Protection D Supv, Rad Waste/Effluents
  • Hal Szklinski-BV-SIM
  • Rebecca Novak - BV-A

)

Beaver Valle Power Station Radiation Protection Technical Position/Evaluation/Calculation REVISION:

Subject:

No.:

Page:

Liquid Monitor Alert Emergency Action Level (EAL) Set Points DISCUSSION:

ERS-LMR-14-001 2

This technical evaluation used ODCM source terms for liquid discharges, radiation monitor nuclide detection efficiencies, and nuclide dose conversion factors to calculate radiation monitor readings that correspond to offsite doses of 1 O mrem TEDE and 50 mrem child thyroid. These monitor indicator values may be used for an Alert level in Emergency Plan Emergency Action Levels (EAL), EPP-l-1a and EPP-I-1b, when NEI 99-01 revision 6 is implemented (Reference 1 ). The calculated radiation monitor readings may be used for Emergency Action Level (EAL) determination following an accident with consequent release of radioactivity, and when the results of more rigorous assessments are not available.

METHODOLOGY The bases for the EAL values for the four emergency classifications are:

Unusual Event (UE): ODCM limit multiplied by two (x2) for greater than 60 minutes. ODCM limits are calculated in ERS-ATL-93-021 (Reference 2)~

A)ert:

Effluent pathway radiation monitor indication that corresponds to 10 mrem TEDE or 50 mrem child thyroid dose. The lower of the two values is used. Gaseous doses are calculated at the site boundary; liquid doses are calculated at Midland Water Intake.

There are no liquid effluent pathways associated with a Site Area or General Emergency.

INPUT DATNASSUMPTIONS

1. Ai = Particulate Activity from the release path (Ci/yr)
2. Alig= Ingestion Annual Limit of Intake from 10 CFR 20 Appendix B Table 2
3. F = Dilution Water Flowrate

= 22,800 GPM (= 15,000 GPM BV-1+7,800 GPM BV-2)

4. ODCM site specific mixing effect of the discharge structure = 3
5. ODCM river dilution factor = 200
6. f = Maximum Acceptable Discharge Flowrate (GPM)

= 35 gpm for RM-1LW-104

= 15 gpm for RM-1LW-116

= 80 gpm for 2SGC-RQ100

7. Ei = Monitor Sensitivity (cpm/uCi/cc)
8. DCF = Dose Conversion Factors for child thyroid from RG 1..109 References

[3, 5]

[4]

[3]

[3]

[3]

[3]

[6, 7]

[9]

Release source terms (A) used to determine the monitor EAL values are listed in the spreadsheets in Attachments 1 through 3.

NEI 99-01 revision 6 discusses assumptions and requirements for this set point calculation. Site-specific dose receptor points are expected to be used in the calculation with a one hour exposure duration. The ODCM liquid effluent receptor point is a down river potable drinking water intake structure with in Yi mile of

Beaver Valle Power Station.

Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Liquid Monitor Alert Emergency Action Level (EAL) Set Points REVISION:

No.:

ERS-LMR-14-001 3

the release point. With the assumption that the release concentration is fully mixed by the Ohio River, the nearest drinking water supply is at the Midland Water Intake (at 1.3 miles down river from the release point).

ICRP 23 (Reference 8) gives an annual drinking water ingestion volume of 1950 ml per day (for adults).

USN RC Regulatory Guide 1.109 Table E-5 (Reference 9) gives an annual drinking water ingestion volume I

of 730 liters per year (for adults), which equates to approximately 2000 ml per day. In order to equate this to drinking water per* hour, it is assumed that all 2000 ml are consumed during the one hour release. For child thyroid doses, the ICRP 23 value of 1400 ml is utilized in the same way.

Radiation monitor nuclide detection efficiencies for each monitor and for each nuclide are taken from ERS-SFL-92-039 [Unit 1] and ERS-SFL-86-026 [Unit 2] (Reference 6 and 7). Due to the availability of both 843-30 and 843-30R detectors at Unit 1, set points for both detectors were calculated (Reference 6). Detection Efficiencies are listed in the spreadsheets in Attachments 1 through 3.

The TEDE conversion factors were derived from 1 O CFR 20 stochastic Alig with 1 ALI = 5000 mrem CEDE, and 1 CEDE = 1 TEDE for a liquid ingestion scenario with the assumption that no external exposure occurs during this release.

NEI 99-01 revision 6 acknowledges that the use of EPA PAG guidance provides adult thyroid dose conversion factors, which are not always consistent with state required methodologies. BVPS has previously agreed with the states of PA, OH and WV that child thyroid doses will be calculated. This technical evaluation will remain consistent with past practices. The child thyroid dose conversion factors (DCF) are taken from USN RC Regulatory Guide 1.109 Table E-13 (units of mrem/pCi ingested) (Reference 9). DCFs are listed in the spreadsheets in Attachments 1 through 3.

The following is a description of the math performed by the EXCEL spreadsheets used in this Technical Evaluation.

An EXCEL spreadsheet was made utilizing the ODCM default source term for each unit and radiation monitor combination. Each spreadsheet consists of 15 columns with a row for each radionuclide. At the bottom of each spreadsheet, there is a section to total the count rate (CR) in cpm for 1 O mrem TEDE and the count rate in cpm for 50 mrem child thyroid. Unit 2 is calculated for both cpm and uCi/ml. Details of all spreadsheet math is provided below:

Column 1 - List of the individual isotopes that comprise the ODCM source term. Each isotope occupies a row.

NOTE: Isotopes individually listed in the ODCM but not included in the dose calculation are Br-85 (172s half-life), Rh-106 (29.9s half-life). As short lived daughters of longer lived parents, production &

intake limits are included with the parent values. Because of the short half life, the initial individual quantities are assumed to be insignificant. Ba-137m and Cs-137 isotopes are also individually listed in the ODCM. However, Ba-137m (2.55 min half life) will contribute to the count rate at the monitor, but will be decayed by the time it reache,s Midland Water Intake. All Ba-137m daughter isotopes that an individual is exposed to are included in the Cs-137 dose factors. Therefore, Ba-137m is included in total count rate, but not dose calculations.

Column 2 - [Ai] - Total release quantity (Ci) for each isotope, specific to Unit 1 or Unit 2.

Column 3 - Stochastic Annual Limit of Intake (Alig) for ingestion taken from 10 CFR 20 Appendix B Table

2.

Beaver Valle Power Station Radiation Protection Technical Position/Evaluation/Calculation

- REVISION:

Subject:

No.:

, Page:

Liquid Monitor Alert Emergency Action Level (EAL) Set Points ERS-LMR-14-001 Column 4 - TEDE mrem amount associated with each individual radionuclide, based upon 1 O CfR 20 definition 1 ALI = 5000 mrem TEDE.

Col 4 = [ (Col 2 uCi

  • 1 E6 uCi/Ci) I Col 3 uCi ]
  • 5000 mrem I ALI Column 5 - Intake amount scaled to 10 mrem TEDE:

Col 5 = [(Col 2 uCi

  • 1 E6 uCi/Ci) I I: col 4 mrem]
  • 10 mrem 4

Column 6 - Concentration of individual radionuclide at Midland Water Intake equal to 10 mrem TEDE for a one hour adult intake. (Assumes water ingestion occurs over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.)

Col 6 = [ Col 5 uCi I (2000 ml/hr)]

Column 7 and 10 - Concentration of individual radionuclide at associated BVPS radiation monitor equal to 1 O mrem TEDE for a one hour adult intake. The concentrations at the radiation monitor(s) were calculated using:

Ci= F*3*200_* Ct f

Col 7 = [(22800

  • 3
  • 200) gpm/ f gpm]
  • Col 6 uCi/ ml]

where:

C1 = Liquid effluent concentration prior to dilution Ct= Liquid effluent concentration after dilution F = Dilution water flow rate (gpm)

= 22,800 gpm (15,000 gpm U1 CTBD+ 7,800 gpm U2 CTBD) 3 = ODCM site specific mixing effect of the discharge structure 200 = ODCM river dilution factor f = Maximum acceptable discharge flow rate prior to dilution (gpm)

= 35 gpm for RM-1 LW-104

= 15 gpm for RM-1LW-116

= 80 gpm for 2SGC-RQ 100 Column 8 & 11 - [E1] - List of the monitor specific isotope detection efficiencies. A set of calculations is done for the 843-30 and the 843-30R detectors available for Unit 1 monitors (isotope efficiencies in units of cpm/uCi/ml).

/

Beaver Valle Power Station Radiation Protection Technical Position/Evaluation/Calculation REVISION:

Subject:

No.:

Page:

Liquid Monitor Alert Emergency Action Level EAL) Set Points ERS-LMR-14-001 Column 9 & 12 - The monitor count rate (CR) was calculated using:

CR= L where:

CR = monitor count rate attributed from each radionuclide in ncpm Ci = previously described 5

[Reference 2]

E =detection efficiency for the appropriate monitor (cpm/uCi/cc)[References 6 and 7)

FOR UNIT 2 ONLY:

The Unit 2 monitor display value (DV) was calculated using:

DV= CF11 L C; E; i

CF11 = 5.61 E-9 uCi/ml/cpm; calculated in ERS-ATL-93-021:

Ei = Previously described Ci = Previously described I

[Reference 2]

Application of Monitor

Background:

Because the liquid monitors do not have a background subtract feature, the indicated values are net values. Therefore, monitor background needs to be accounted for when changing the set points on a monitor.

Column 13 - Dose Conversion Factors (DCF) for child thyroid taken from Regulatory Guide 1.109 (Reference 9) in mrem/pCi ingested.

Column 14 - Converted RG 1.109 DCFs into mrem/uCi.

Col 14 = [Col 13 mrem I pCi* 1 E6 pCi/ uCi]

Column 15 - Child Thyroid dose per hour from ingestion concentrations equal to 10 mrem TEDE.

(Assumes water ingestion occurs over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.)

Col 15 =[Col 14 mrem I uCi *Col 6 uCi I ml* 1400 ml I hr]

Beaver Valley Power Station Radiation Protection Technical Position/Evaluation/Calculation I

REVISION: _lfBI 1

,,,~:;;~

Subject:

No.:

Page:

Liquid Monitor Alert Emergency Action Level ERS-LMR-14-001 6

{EAL) Set Points Conversion of Child Thyroid Dose to a GounrRate equal to 50 mtem CdhirilittedDose EquivalenHCDE):

CR for 50 mrem COE (CThy) = CR for 10 mrem TEDE L CDEi I 50 mrem RESULTS An EXCEL spreadsheet was generated to perform the alarm set point calculations. See Attachments 1 through 3.

Alarm Set Point Calculation Summary - Unit 1

[all units in cpm]

10 mrem TEDI:

50 mrem Child Thyroid Minimum Set Point Monitor Range RM-lLW-104 843-30 1.81E+09 5.89E+08 5.89E+08 10to1E6 RM-lLW-104 843-30R 2.09E+09 6.80E+08 6.80E+08 10 to 1E6 RM-lLW-116 843-30 4.22E+09 1.38E+09 1.38E+09 10to1E6 RM-lLW-116 843-30R 4.87E+09 1.59E+09 1.59E+09 10to1E6 Alarm Set Point Calculation Summary-Unit 2

[all units in uCi/ml]

TEDE Child Thyroid Minimum Set Point Display Range 2SCG-RQ100 5.89E+OO 2.42E+OO 2.42E+OO 5.6E-8 to 5.6E-2 I

Readability/Range Discussion:

As displayed in the tables above, all calculated set points are significantly greater (>4000%) than the range of the associated instrument. Generally when an over range EAL value occurs, it has been acceptable to choose a value of approximately 80% of the high range of the monitor. For example, 80% of 1 E6 = 8E5 cpm. However, if this value would be employed as an EAL indication, an ALERT level would be declared significantly sooner than required for 1 O mrem TEDE and/or 50 mrem child thyroid dose. More specifically, even at the 95% range values, ALERT EAL indication would be declared at doses less than 0.1 mrem TEDE and less than 1 mrem child thyroid for all available radiation detectors at both units. These values are far below the required EAL thresholds of 10 mrem TEDE and 50 mrem thyroid, which, if employed, would cycle plant and industry resources unnecessarily.

Beaver Valle Power Station Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Liquid Monitor Alert Emergency Action Level

  • EAL Set Points Conclusions/Recommendations:

REVISION:

No.:

ERS-LMR-14-001 7

NEI 99-01 recognizes that this Initiating Condition may result in a value beyond the display range of the monitor. Therefore, guidance states that if the calculated set point is greater than approximately 110% of the highest accurate monitor reading, then developers may choose not to include this monitor value as an

, EAL indication and are instructed to identify an alternate EAL threshold. The only viable alternate methodology is a liquid isotopic sample analysis. Sampling methodology is covered under its own distinct EAL according to NEI 99-01 revision 6. Therefore, it is recommended that BVPS EALs do not contain a liquid effluent monitor threshold value that equates to 1 % of the PAG for an ALERT classification.

REFERENCES

1.

NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors, Revision 6, 2012.

2.

FE NOC, Process Alarm Set Points for Liquid Effluent Monitors, ERS-A TL-93-021, Revision 4, 2012.

3.

FENOC, Offsite Dose Calculation Manual Procedure 1/2-0DC-2.01. ODCM: Liquid Effluents, Revision 14, 2014.

4.

10 CFR 20 Appendix B Table 2.

5.

SWEC, UR(B)-160, BVPS Liquid Radwaste Releases and Concentrations - Expected and Design Cases: Per Unit and Site, Revision 3; 1983

6.

FENOC, Isotopic Efficiencies For Unit 1 Liquid Process Monitors, ERS-SFL-92-039, Revision 3; 2010.

7.

FENOC, Unit 2 ORMS Isotopic Efficiencies, ERS-SFL-86-026, Revision 6; 1991

8.

ICRP 23, Report of the Task Group on Reference Man, 1974.

9.

Regl,llatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, 1977.

ATTACHMENTS

1. (see page 8) Unit 1 Liquid Monitors Alert EAL Set Points for 843-30 Detectors
2. (see page 9) Unit 1 Liquid Monitors Alert EAL Set Points for 843-30R Detectors
3. (see page 10) Unit 2 Liquid Monitors Alert EAL Set Points

Beaver ~alley Power Station Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Liquid Monitor Alert Emergency Action Level (EAL) Set Points REVISION:

No.:

ERS-LMR-14-001 - Unit 1 Liquid Monitors Alert EAL Set Points for 843-30 Detectors

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DOICTION EFAOENtY

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!J.llE-07 LIDE-01 1.58h01 1"""1

Beaver Valle Power Station Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Liquid Monitor Alert Emergency Action Level (EAL) Set Points REVISION:

No.:

Page:

ERS-LMR-14-001 9 - Unit 1 Liquid Monitors Alert EAL Set Points for 843-30R Detectors iUnit 1 Liquid Monitors Alert EAL Set P~ints ___

. ----~:;:~,~!~~;*-*---

843-30R Detectors Adl!ltwateriritake=

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  • CRincpm:

'.luitopes indMd1.1illylilt~dln lfR Oro.4bulnotincludedinthe d()Secakulationart Br*S5 (172:i ffiff.lfe), f\\t1-l(X)(J9.93 half-tile. As1hoT1 lrnd ld.~uchtt>rs oflotiterll~ed pare Ms, production& intake Umib are iocludtdwithttie parent valuts. Beca"se of the shm half life, tlie initial individual iql.lin!itie~a.fl! 1~um~dm he ins1gnitkallt

sa.mmand Cs-l31 l54lopcsaNil~11 indMdu.ally !istedin tht ODCM However, Ba-l37m(2.5S minh31f life) will wntrilwte to the wuntrate al the

'.monitor, tJutwlll bt dwyrd bylhe limE itreicheS PlidlandWaterlntake. All Ba-Wm d31Jghter Jsotope5 tf!at if1 indNidual is eJpQS~ le are

indudedintl.e CS*137 de~ factcrt. The111Jore, Ba* 137mis inclu&dinWt-11roontrale, but not dosecakul~tiom.
Assumes daily drinki~gwati
r iota~* oo:c_urs in 1hour ~riod.at Mid!andwarer int.ike.

r~rate5fro.:nll2*~*2.01

~Suurce Term for {RM-UW-!043'14 RM-lLW*116) from l/2-00C-201 (Stone and Web~tert.afa1Lation Package URlBf-1001

  • 0c1ecti110 Efficiency !or (AM*llW*lf>l.and IUIHL'lf llE) from l/2*0DC*201 [Cdladation Pcdagt ERS*Sfl*9l-019)

'.Assumption~-

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200

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Beaver Valle Power Station t---------------------*--------------------**-*********************--****-------*

Radiation Protection Technical Position/Evaluation/Calculation

Subject:

Liquid Monitor Alert Emergency Action Level (EAL) Set Points REVISION:

No.:

ERS-LMR-14-001 Page:

10 - Unit 2 Liquid Monitors Alert EAL Set Points Liquid Monitor Alert EALS;t-P~i;t~-

    • ~-----* ""'""'1*01y 001.ID9Do11y[mlJ*

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'801 moi 9.E'l{)l 7.£t0l 9.E<Ol S.E<-01 lh04 7.(t{IJ l.E+ol 4Erlll lE<!ll l.E<01 o.01t00 1._nf-03 forhourinb~e 11Ci/ml LllE-08 2.&1[.(!I l46Hl8 7..lll_..{1,1 llMl LSOE-08 S.JJE-06 l59E-!>9 1261-09

'63E*ll 416-0'J l47f:~

9.ssq1 5.74E*ll 4.00.-10 4~-W

.Bn.11

~49E-IO 4.f.l[.IQ 5.95?-10 lSIE-07 2..3fl*07 l03E*l0 9'.l!*U lOlE-10 nlE*ll 213£.10 Z3'!-<!I 2.81£-0J 9.21£-01 5.9SE-O.l 253£.()3 5.84£-~

106E-09 lllE*OS

!)(£.(18 2..SBE-07 7.JOE*t))

S.li'E*lO lllE--0!

tOl--06 4.38£.{l]

2UE.ai me<:<

lME~

U3E-10 t~E-10 l({i*JI Z.92.E*lO Z.58E-10 291!-ID

  • 1&-02 ociiml l.9lE-lll UOE-OI l.IOE-03 tlSE-03

}Jlf.Q:l 3.07E~

im-01 5.14WI l.l1£-0I llll'-07 7.11£-0I 4.DE~

trn:--OS 115[.QS 6.91E-OS

!.45£-05 i7f£..Q6 7.S!E-Ol 7.68£-05 L02E-04 4,UE-02 4.03'-02 5.18!:.0S l.57£..0S

<JS&<ll

'57E*D5 165[...(l) 4.03E--04 4.!'DE*04 l.57£.03 LOlE--03 412f.Q.l 9.99£-04 L81E-Ot 1921.00 BOE-m 44'1-0Z 12SE.OO 883(.0S 5.76£-01 Inf~!

7.49[--02 4.llE-01 4.03[-0I L7SE-OI 1.61C-0$

763E.{6 tf!if.(.5 4"!.(l; 4.42E-OS 49'Jf-OS U.E.ol l~Et\\11 lllii-OI!

104i4 4.*HE*l~JI l<C£"'8 llli<-08 OCll.00 OCll.00 S.65£-l-07 19'1>!!;

t2/l+ffi 2.43E+-06

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HSEiOS li&<-08

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ll&o(ll 4.:22Ei<e li':ltCS

<CG<-Oa 11500!

l7lft08 418£~

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G.C-02 2.E+Ol

~Et{}3 lfi-02 1.£~

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7.CCE-05 1~£-0S l<XI-Ol Sll!-01 4.ll-06 19M:{l7 433E.a.i S&1E*07 L15E*OS.

S.16E-07 l25E--07 SSIE-07 l44H-02 tllE;(l2 t<a<-01 CRinwm.~

4.97E+Dll S95El<B l!W<B 134Et<ll 7.l(IE-Ol l-1'E<-02 0.0000 Ul5Ellal CRirrpm=

4JZE+al DIJinuCi/mlr.

S.89E+ol Dvtnua/mh 2.42£+03 f '"" ;od;,;d.,llyl**d;, <h*OOCM~""'""dod ;, oe d"e<<kol*a.o*ra ~-BS [17~ ~*lf~;r.1, Rh-l<l[1'.9sh<IJ.nfe. A;;ho1tn".d dnghters,./ lcmge1 INeci parcnb, p1oduaio11 & intake limits ar.- liv.luded with the parent values. ~au>e al thr Yicrthalf life, the initial ind111ld1ial

quanll!lesarern~rnedtobe ln>iznjlic
ant.

El*D1m and Q:-ll7 J~lope; ;ire1lso i'ICNitfo*llv fi~tedin tht-ODCM. !bwfver, lla-137m(lS~rrin lwlflife) wi11 contribute to tli~ c.wnl r*te.il tht

monitor, but will br dmytd by the liT'll! ltrei!d~i Mdlind Witt1 lritJh. All8i-131m 11!ughter IS£tlo~es ch.it a.~ indi't'idud! i1 upc~d lo are

!lnduded In 1heCs-l37dc!.! bctcrs. Thereto~. B.1*ll1mis !nduded In tor.ii oountrate,bul nol dost calailatioris lA~'umesdilll'{ :lrinkiniw11tr inb~it oa:nin l~curperiod at Midland waterlilla~e.

h1ow1*tn frtml/2*00C*2.01

~oum! T e~m fii (.~~°" ~lW.lO:i ind RM-llW-116) 'rem lJ}OQC-~01 {St~~ *nd Wtb1tfr c.arrulation P1d:1£e UR~l))* 1&'.l!

j~te;cticn lffidll"ncy /orl~M-llW.lOh11d llM*ll~-mJ. from l/2-0DClOl(C.ikuli~m Pacla~ EPS-SFl*92*tR'll OOCMsource term Cfl1Cunvcrs1an /aaor from ERS*An-91-021.

Anum)ltkrns-O.Xe c.1lcuht'on is forcne hourtqiowre. Reference Ml~dail7watef !nt.ike i11 Cll! hour.

'1nt.1ke conwntration bcalail1ted usingCTblo. ~owr~~ (dehult 1SOOJ"-7a:0.11pm) t1rlorto the 1M!rwW1 OOCMoulfa!land riverdUution priortoht.1\\:e.

I 2QlE.07 ZOJ!-01

<<<<ba~011SOm1emCttiy 1.15£t0l 112!+<11 5.o:ftOl

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