ML20215K268

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Offsite Dose Calculation Manual,North Anna Power Station Units 1 & 2
ML20215K268
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 12/19/1985
From: Stafford A
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20215K253 List:
References
PROC-851219-01, NUDOCS 8610280078
Download: ML20215K268 (29)
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Text

l H.P.-0DCM Page 1 of 3 12-19-85 VIRGINIA POWER NORTH ANNA POWER STATION i

0FFSITE DOSE CALCULATION MANUAL UNITS 1 AND 2 RECOMMENDED APPROVAL:

APPROVED BY: ,

CHAIRMAN STATION NUCLEAR SAFETY O2 AND OPERATING COMMITTEE DOC 5 88 R PDR DATE: 12-19-85 SAFITY RILATE)

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I H.P.-0DCM-2 Page I of 6 12-19-85

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NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL- i t

l SECTION 2 .

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LIQUID EFFLUENT RADIATION MONITOR SETPOINTS

+

h Part Subject Page 1 Technical Specifications Requirements 2 2 Applicable Monitors 2 3 Setpoints Calculation 2 4 Example 3

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l H.P.-0DCM-2 Page 2 of 6 12-19-85

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1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.3.3.10. requires that: "The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined .and adjusted in accordance with the OFFSITE DOSE CALCUALTION MANUAL (ODCM)".

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2. APPLICABLE MONITORS Radioactive liquid effluent monitors for which alarm / trip setpoints are determined in accordance with this Manual are:

Radiation Monitor Plant Release Point Instrument Number Liquid Radwaste Effluent Line LW-111 Service Water System Effluent Line .SW-108 Condenser Circulating Water SW-130, SW-230 Monitor locations in the liquid effluent waste stream are shown in Figure '

2.0.

3. SETPOINT CALCULATION 3.1 Maximum setpoint values shall be calculated using the following basic equation:

c=Sf where:

c= the setpoint,, in pCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prict to dilution; C= the effluent concentration limit for this monitor used in implemen-ting 10CFR20 for the site, in pCi/ml; f= the flow setpoint as measured at the radiation monitor location, GPM; F= the dilution water flow calculated as:

F ='f + (218,000 GPM x No. of Cire Pumps in Service).

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H.P.-0DCM-2 Page 3 of 6 12-19-85

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3.2 Each of the condenser circulating water channels (SW-130, .SW-230) monitors the effluent (service water, condenser circulating water, and liquid waste) in the circulating-water discharge tunnel beyond the last point of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, the equation in 3.1 above becomes:

c=C The setpoint becomes the effluent concentration, limit for these monitors

, used in implementing 10CFR20 for the site.

3.3 In addition, for added conse rvatism, setpoints are calculated for the

- liquid radwaste line (LW-111) and the service water system effluent line (SW-108).

For liquid radwaste line (LW-111), the equation in 3.1 becomes:

c= LW f

where:

Kgy = the fraction of the effluent concentration limit used in implementing 10CFR20 for the site attributable to liquid

( radwaste line pathway. .

For the service water system effleunt line (SW-108), the equation in 3.1 becomes:

c= SW f

where:

K SW = The fraction of the effluent concentration limit used in implementing 10CFR20 for the site attributable to the service water system line pathway.

The sum Kgy + Kgy = 1.0.

3.4 The above .me*.hodology does not preclude the determination of more f conservative setpoints.

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H.P.-0DCM-2 Page~4 of 6 12-19-85 i

4. EXAMPLE 4.1 The following information is obtained from an isotopic analysis of the effluent from the liquid radwaste line:

Radionuclide Average Undiluted Concentration Released Released (pCi/ml)

Co-60 3.09E-06 Cs-137 4.08E-06 Cs-134 2.65E-06

~Co-58 3.19E-06 Fe-59 1.78E-06 4.2 The following information is obtained from an isotopic analysis of the effluent from the srvice water system line:

Radionuclide Average Undiluted Concentration Released Released (pCi/ml)

Co-60 8.51E-07 Cs-137 1.01E-06 Co-58 7.95E-07 4.3 Calculate, K and K the fraction of the effluent concentration limit for the liqu N radwash ,and service water pathways.

Liquid Waste:

Radionuclide pCi/mi g Released MPC MPC g Co-60 3E-05 1.03E-01 Cs-137 2E-05 2.04E-01 Cs-134 9E-06 2.94E-01 Co-58 9E-05 3.54E-02 Fe-59 SE-05 3.56E-02 I pCi/ml i MPC g i = 6.72E-01

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H.P.-0DCM-2 Page 5 of 6 12-19-85 i

Service Water:

Radionuclide pCi/ml.

Released MPC MPC g Co-60 3E-05 2.84E-02 Cs-137 2E-05 5.05E-02 Co-58 9E-05 8.83E-03 I pCi/ml i = 8.77E-02 1 MPC f

Calculate the fraction of maximum allowable concentration (L2C) for each pathway using the following equation:

FMAC = F1*hY MPCt

!" i The flow rate for the liquid radwaste pathway is 300 GPM and 2800 GPM for the service water pathway. Three circulating water pumps are available, i

FMAC 'for liquid waste:

300

  • [300 + (218,000 x 3)] x 6.72E-01

, f FMAC = 3.08E-04 FMAC for service water: I 2800 FMAC =

[2800 + (218,000 x 3)] x 8.77E-02 FMAC = 3.74E-04 K

3.08E-04 LW = 3.08E-04 + 3.74E-04 = 0.45 Kgy = 0.55 4.4 The liquid radwaste monitor (LW-111) is calibrated for Cs-137, therefore:

C (pci/ml) = I pCi/mig x MPC i MPC Cs-137 f

C = 6.72E-01 x 2E-05 C = 1.34E-05

H.P.-0DCM-2 Page 6 of 6 12-19-85 (s

4.5 The liquid radwaste monitor (LW-111) setpoint would be calculated as:

1.34E-05 x [300 + (218,000 x 3)] x 0.45 c_ 300 c= 1.32E-02 pCi/ml.

4.6 The service water monitor (SW-108) is calibrated for Cs-137, therefore:

a C (pCi/ml) = I pCi/mi xg MPC Cs-137 i MPC g C = 8.77-02 x 2E-05 = 1.7SE-06 i

4.7 The service water monitor (SW-108) setpoint would be calculated as:

4 1.75E-06 x {2800 + (218,000 x 3)] x 0.55 c= 2800 i

c= 2.26E-04 pCi/ml. .

4.8 The setpoints may be multiplied by the appropriate monitor conversion factor f

to determine the setpoints in CPM (counts per minute). l

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MEMORANDUM 0;C0~5MI5^~

Mr. A. L. Staf ford North Anna EfC

"" Deccmber 4,1985 I F. M. Wiegand IMPACr OF C.W. SYSIliM B.m!FICATIWS (DCP 85-37, DCP 85-38) W LIQUID EFFIHclir DISOfAICE

References:

SWEC Let ter to R. W. Calder dated 11/7/85 (tMS 16,729)

B. W. Foster Mmu to F. M. Wiegand dated 11/13/85 his memo supersedes my mmio to you dated 11/25/85. he C00VI Calculation has been.. revised .to .accmmodate. your desire _ to minimize .. changes - to the.QXM Fonnat.. De pmp flow rate used in the calculation, 218,000 Gaf, is the mininun flow rate per pmp for any ccrnbination of circulating water pmps in operation.

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As we have discussed, the throttling of circulating water pmp discharge ~~~

valves inpacts the GXM (Off Site Dose Calculation Manual) Liquid Effluent Calculations. l Engineering proposes that the attached method of detennining circulating water flow be substituted for the present CDCM method. his proposed method is reemmended for the following reasons:

1. No physical modification is required, i.e. no instrtmentation to install.
2. As a result, no maintenance, periodic testing, or calibration is required.
3. Operations involvanent is minimized, i.e. no flow indication to obtain and record, only changes in the nmber of pmps operating need to be coordinated with IIcalth Physics.
4. his method is consistent with the present method, i.e. calculated flow is used in lieu of actual measurement.

In regard to NRC acceptance of this proposed method, past correspondence on this subject was researched and no unfavorable NRC disposition was found. It is reccxnnended that the NRC be apprised of this change to the Offsite Dose Calculation Manual in the sani-annual health physic report.

Per you request I am forwarding copics of the Flow and Dilution calculations as well as a marked up GXN calculation.

5670 /CWS\lLED/ engr 3

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IUV 36-82-02 Mr. A. L. Stafford Deecmber 4, 1985 Page 2 (Continued)

If you have any. questions , please advise.

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F. M. Wiegand E W:rnvf cc: E. R. Bane w/o Attach.

M. W. Gettler w/o Attach.

T. W. Bernett w/o Attach.

R.-KrBayer w/o Attach.

~ -~C6rfes. Control w/At tach.

File w/ Attach.

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  • n =- I H.P.-0DCM-2 Page 2 of 6 '~

10-11-84

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TECHNICAL-SPECIFICATION REQUIREMENT ~

Technical Specification 3.3.3.10 requires that: "The radioactive liquid effluent. monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm /trin setpoints set to ensure that the limits of Speci*fication 3.11.1.1 are not exceeded. The alarm / trip setpoints of

~

these channels shall be determined -and adjusted in accordance ~ wit' h the" ~

OFFSITE DOSE CALCUALTIG) :tAhTA'. (ODCM)".

I

2. APPLICABLE MONITORS Radioactive liquid effluent monitors for which alarm / trip setpoints are l c.etermined in accordance with this Manual are:

k Release Point Radiation Monitor Plant i Instrument Number  !

Liquid Radwaste Effluent Line __ -

LW-lll Service Water System Effluent Line SW-108 Condenser Circulating Water i SW-130, SW-230 1

Monitor locations in the liquid effluent waste stream are shown in Figure 2.0. '

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3. SETPOINT CALCULATION  !

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3.1 Maximum basic equation: setpoint values shall be calculated using the following '

C:

CF f

] l U

I where: k k

c: the setpoint, in pct /ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution; -

. I C= t the effluent concentration limit for this monitor used in implemen-ting 10CFR20 for the site, in pCi/ml; f=

the flow setpoint .,as . measured at the radiation monitor location, GPM; F=

the dilution water flow calculated as: h F = f + ( 2JS,0C0 GPM x No. of Cire Pumps in Service).

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H.P.-0DCM-2 Page 5 of 6 10-11-84 Service Water:

Radionuclide pCi/ml.

Released MPC MPC g Co-60 3E-05 2.84E-02 Cs-137 '

2E-05'~ '

5.05E-02 Co-58 9E-05 S.83E-03 I . pCi/m1.*~

- 3 '"' ' E~02 ' ~ ~ ~ ~ ~

i @C i Calculate the fraction of maximum allowable concentration. (FMAC) for each

__ pathway using the following equation:

FMAC = FI*hY 1 MPCi

!" i The flow rate for the liquid radwaste path'way is 300 GPM and 2800 GPM for the service water pathway. Three circulating water pumps are available.

FMAC for liquid waste:

x -01

  • [300 + (a.it,eco x 3)] .

FMAC = 3.o s e -o y DiAC for service water: ,

[2800 + ( 18 coo x 3))

FMAC = 3,74 E-OV 3.08 E -0 Li LV 3.08 E-04+ 3.7'l E-09 = 0. M K

3v = 0.E5 l 4.4 The liquid radwaste monitor (LW-111) is calibrated for Cs-137, therefore:

C (pCi/ml) = p 1; x MPCCs-137 i

C = 6.72E-01 x 2E-05 C = 1.34E-05 I

t f

H.P.-0DCM-2 Page 6 of 6 10_11-84 4.5 The liquid radvaste monitor (LV-111) setpoint would be calculated as:

c= -1.34E-05 x i300 t (218,000 x 3)l x 0 75 300 c =, l.32 E-02 pC./ml. l d

4.b The service water monitor (SW-108) is calibrated for Cs-137, therefore:

C (pCi/ml) = I pCi/ml; x MPC i ':PC . - Cs-137 t

[

C = 8.77-02 x 2E-05 = 1.75E-06 j

F 4.7 The service water monitor (SW-108) setpoint would be calculated as:

[

c= 1.75E-06 x [2800 + (218,000 x 3)l x 0 55' t 2800 q c= Q,gg.gr/pCi/ml.

t 4.8 The setpoints may be multiplied by the appropriate monitor conversion factor to determine the setpoints in CPM .(counts per minute).

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~ HEAD LOSS AND FLOW .

~

i

_C.OEFEICTENTS for-the STREAIMSEAL '

BUTfERFLY VALVE with DOMED DISC

(

K and Cf versus disc position

  • He- = = .

29 2gCf- '

/j H I L = head loss across vatve in feet of water . i  ! .

l I

K = head loss coeffic:ent  !

.,. I Cf = flow coefficient '

V = fluid velocity in pipe in feet per second , I g = gravitational constant (32.2) feet per sec.:

7 ,

j

.[f/ * ;,-

M(g Note: Coefficients shown are indicative of the variation cf L __ _ C ~

llow with valve disc angte on tne basis of ; nit head '

loss. ,z' t

- x Actual performance of the valve will be affected by '

the parameters of the complete system. 7 ]- ,

.c

/ 1'.

i

_y

/

  • i ,

i l . t l ! e a

. . , = = I 4 m > s' LOCK-IN RUBBER SEAT DESIGN i OFFERS POSITIVE RETENTION. TOTAL RUBBER CONTROL, AND MAXIMUM USER FLEXIBILITY

1. Valve cise.
2. Corros:On resis: ant retaining nng. '

3 Stainless steel cao screws. '

4 360; full circ:e ruccer seat. 3 Disc 5 Valve cody.

5. Stainfess steel mating surface.

_x1 mpbS$t gg gEADs ~

.4{ il j cAPsCREW

  • Ruocer Seat ful!v foCke0-en cv coveta 1 Configuration a 4, RUBBER SEAT 30es *0: recu *e act'esives '-- eten"cn -[ RETAINER RING

. Ruocer ecge ;s serrate . recuc:ng seat ng tore e ,

, @soovsEAT

  • Cao s: ews c *'c: ceretrate 'uceer - enmina::rg in'.' *i'Oency "O wa!!'e Or 3:3300 ' :ne sea rg j  % /

BODY j

tCQe 's

?<0* *.av 3Cn.5:aO.e :n ;nancag the ;Orcue Cn *ne

] <

220 30*e.vs *2' *"e a-'Oun Of ruCOer OrojeC':c"' 22n 29 'O'*!r le0 'O Cr0v.Ce 2r00 : C-? C'Csure urce' a - A a .-...#p.

ee)

  • Id Crd $ hult) *[I CCse l'e d $,9Q[ =C'

Page 7 ATTACHMENT 4 (7/85 - 12/85)

REVISIONS TO PROCESS CONTROL PROGRAM (PCP) i I

As required by Technical Specification 6.14, revisions to to the PCP for the time period covered by this report are synopsized below. Supporting documentation and affected pages of the PCP are attached.

11-27-85: The PCP was revised in its entirety to ensure accuracy and concurrency with present radwaste processing methodologies.

.. -

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