ML20092M950
| ML20092M950 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/18/1983 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20092M911 | List: |
| References | |
| PROC-830518, NUDOCS 8407020427 | |
| Download: ML20092M950 (13) | |
Text
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- ' 0FFSITE DOSE CALCULATION MANUAL
!: REVISION 10 l: i.
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0FFSITE 00SE CALCULATION MANUAL REVISION 10 This revision incorporates changes to establish a new release pathway (steam generator blowdown bypass) for potentially radioactive liquid effluents. This pathway addition includes adding radiation monitors 2RT-6753, 2RT-6759, 3RT-6753 and 3RT-6759 (page 1-12) and flow indicators 2 FIC-4055, 2 FIC-4056, 3 FIC-4055 and 3 FIC-4056 (page 1-13). Suitable calibration constants (Table 1-1) based on I-131 and Cs-137 are added for the Unit 2 monitors (2RT-6753 and 2RT-6759), with the note that Unit 3 monitor calibration constants would be added before use of the Unit 3 blowdown bypass (page 1-16). A reduction in the administrative value (from 0.8 to 0.7) used to determine the maximum allowable concentration of liquid in the liquid radwaste discharge line (2/3 RT-7813) was made to provide for addition to the new effluent pathway. (See page 1-4 and page 1-6.) The new effluent pathway, " steam generator blowdown bypass," is a continuous style stream, and the calculation and methodology is the same as for steam generator blowdown. Therefore, the changes do not reduce the accuracy or reliability of dose calculations or setpoint determinations. Administrative values were included in this i' calculation so as not to constitute an increase in the total release rate from the site. The value assigned is 0.1 distributed as 0.05 per steam, generator. This revision was presented and accepted by the Onsite Review Committee on May 18,-1983. u 4 a-
Step 2) Thea,djuotsent f actor. A for each batch tank (or [ susp) is determined using: A= I C'v g + C, + Cg + C, +C Fe I~) , l MFC g MFC, KPC g MFC, MPCy ,
= the limiting concentrations of the appropriate HPCyg , MPC ,, MPCg ,
radionuclide from 10CFR20 Appendix B. Table 11 NPCy ,, MPC a Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-4pCi/mi total activity. Step 3) The radioactivity sonitor setpoint may now be I specified based on the values of {C1 3, F. A and R to provide compliance with the limits of 10CFR20, Appendix B Table II, Column
- 2. The monitor setpoint (cpm) is taken from the applicable calibration constants given in Table 1-1 to correspond to the calculated monitor limit C,.
2/3 RT - 7813 0.7 F C*I (1-4) R C s <R g Ag+Ry A ^ 2 + *** + Rn n ( I~' Rev. 10 06/18/83
A3 , A2, etc. = Value of A from equation (1-3) for first [ .- tank, second tank, etc. ,- i R ; The 0.7 is an administrative value used to account for the potential activity for other i I releases. This assures that the total concentra- [ i
, tion from all release points to the plant j discharge will not result in a release of concen-trations exceeding the limits of 10CFR20, f i
' Appendix 5. Table 11, Column 2 from the site. 'I T
i NOTE: If C, < C,g g then no release is possible. To increase C,, increase I dilution flow F (by running more [ ( l circulating water pumps in the [ t
. applicable discharge structure), and/or decrease the effluent flow rates Rg, R2 '
E etc. (by throttling the combined flow as nessured on 2/3 F1-7643), and recalculate C, using the new F, R and , equation (1-4). t k 1-6 Rev. 10 05-18-83
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NOTE: If C, 4 {C g then no release is possible. To increase C,, increase dilution flow T (by running more circulating water pumps), and/or decrease the effluent flow rate R (by throttling the flow as measured on 2F13772 and 3F13772), and recalculate C ,using the new F, R and equation (1-6). If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent ( spurious alarms and yet assure an alarm 3hould an inadvertant release occur. 1.1.2 Continuous Release Setpoint Determination Step 1) The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, and steam generator R ' blowdown bypass, and turbine building sump) l* from the sum of the respective measured concentrations an determined by analysist l ( . 1-8 Rev. 10 I 05-18-83 ll l t
P t i C={ ctg + C, + C + g C, + CFe (I~I) I s t where: IC yg = the total gamma activity ( pCi/cc) associated with each radionuclide, i, in the weekly composite analysis for the release stream. The total measured gross sipha concentration C, = (pC1/cc) determined from the previous monthly composite analysia f or the release stress. i Cp, = The total re-55 concentration as determined in the previous quarterly composite sample for the I I release stres... . Cg = the total measured H-3 concentration (uCi/cc) determined from the previous monthly composite analysis for the release stress. , l C, = the total measured concentration (uCi/cc) of ; Sr-89 and Sr-90 as determined f rom the previous quarterly composite analysis for the release stream, i I ( 1-9 - Rev. 10 ; 06/18/83 r l ^
Step 2) 'Ihe adjustment f actor, B, for each release
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stream (steam generator bloudown or turbine building sump) is determined using: B= IC g + C, + Cg C, + C Fe Il'8) MPC MPC, MFC kPC MFC, Fe a Step 3) The setpoint for each continuous release ' radioactivity monitor any now be specified based on the respective values of { ctg, F, B and R to provide compliance with the limits of 10CTR50, Appendix B Table II, Colure. 2. The monitor setpoint (cpm) is taken from the applicable calibration constants given in [ Table 1-1 to correspond to the calculated monitor limit, C m' 2RT - 7817, 3RT - 7817 (0.5)(0.1)Tjcy3 (g_9,) C 1- RB ' i Where: ICg,B = values of IC g and B (as defined in Steps i i 1 and 2 above) for the steam generator blowdown. ( l-10 Rev.10 0 5-18-83 l
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Table 2-1 I( ' C=ecous Ef fluent Radiatten Monit or Calibration Constarts Monitor Rr-85* Xe-133* m 3.86 E-8 3 07 E-8, s - R
. / 2RT- 7804-1C
, 3kTk 7804-1C e2 05 E-8 1.67 E-8 3.72 E-8 2/3RT-7808C 2. 76 ~ E-8 2/3RT-7814 A ' , 3.37 E-8 4.30 E-8 lR 4.24 E-5 3.61 E 2 / 3RT- 781'4B 2RT- 7818A 3.06 E-8 5.30 E-8 2RT- 78185 6.92 E-5 5.11 E-5 h 3RT- 7818A 3,14 E-6 4.56 E-8 3RT- 78188 3.00 E-5 2.83 E-5 2RT-7865-1 (low) 1.41 E-6 3.02 E-8 C 2RT-7865-1 (mid) 5.33 E-5 21 -7865-1 (high) 6.81 E-2 I
3RT-7865-1 (low) 1.41 E-8 3.02 E-8 3RT-7865-1 (mid) 8.02 E-5 ' 3RT-7865-1 (high) 2.39 E-2 2RT-78 70-1 (low) 1.41 E-8 3.02 E-8
. - 2RT- 78 70-1 (mid) 1.07 E-4
- 2RT- 78 70-1 (high) 2.87 E-2 3RT-78 70-1 (low) 1.41 E-8 3.02 E-8 3RT-78 70-1 (mid) 1.08 E-4 3RT-78 70-1 (high) 2.17 E-2
*uct/cc/ cpm >
a s...
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(. s (, , s. 2-10 g,y, to 05-18-83 r
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" R = 400 spa
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where R is the effluent flow rate at the radiation monitor as definc3 in Step 2. The 0.1 is an adr.inistrative value to account for the This potential activity in other release pathways.
- assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10CTR20, Appendix 5. Table 11, Column 2 f rom the site.
0.5 is an administrative value used to account for simultaneous releases from both SONGS 2 and SONGS 3. I NOTE: C,<{C,1 then no release is possible. To increase C a increase the dilution flow F (by running more circulating water pumps), and/or decrease the ef fluent flow rate R (by throttling the flow as measured on 2F1-3772 or
- 3r1-3772, as appropriate) and recalculate C, using the new values of F. R and equation (1-9a).
\ 1-11 Rev. 10 05-18-83
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I s 4 2RT - 6753, 2RT - 6759, 3RT - 6753, 3RT - 6759 ( ' a ., ; - c g < ~(0.5) (0.05) rg ,1 , RB - Where: .
,,..k
}cyg, a n values of -{c,1 and n (as defined in Steps 1 and U sbove) for the 'ste'am generator blowdown bypass. ,
R - 200 gpm b' i 4 where R is .the. vaaxitsum per steam generator blowdown
.- -%s ,
s
;- bypase effluent,flowrate.
~ The 0.05 is an ' administrative value' to account for the r,otential activity in other releaseipathways'. This ,
ashoresthatthettalconcentrationfromallrelease
- points to the plant 25 sit.svge will not result in a t'elease exceeding the limits of IUCFR20, Appendix B, !
v. Table'II, Column 2 from the ofte. The 0.5 is an j
,y , ..
administrative value used tp account for simultaneous releases from both 50NCS 2 and SONGS 3.
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# Rev. 10 05-18-83 W
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o , i Note: Ifq,<,}C g then no release is possible. { To increase C,, increase the dilution flow F (by running more circulating water pueps), and/or decrease the ef fluent flow rate R (by N throttling the flow as measured on 2 TIC-4055, 2 TIC-4056, 3FIC-4055 or 3FIC-4056, as appropriate), and recalculate q,in equation 1-9b) using the new values of F R.- 2RT - 7821, 3RT - 7821 (0.5)(0.1)F{CYg (1-10) Ce < RB Wheret ( ICyg, B = values of IC Tg and B (as defined in i i ateps 1) and 2) above) for the turbine building sump t (
- R = 50 sp / pump (x no. sump pumps to be run) l l
k l ei.1 Rev. 10 05-18-83 l l'.. m..
The 0.1 is an administrative value to account for the This potential activity in other release pathways. assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10CFR20, Appendix B, Table II, Column 2 from the site. 0.5 is an administrative value used to account for simultaneous releases from both SONGS 2 and SONGS 3. ,. NOTE: If C, C }Cyg then no release is possible. To increase C,, increase the dilution flow T (by running more circulating water pumps) and 8 recalculate C ,using the new value of F and equation (1-10).
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O e f I . .* i eV. 10 0$/18/83 ? e
O O Tnble 1-1 (i Liquid Effluent Radiation Menitor Calibration Constants i F Co-60* Ba-133* Cs-137* Monitor 2RT-6753 1.86 E-8 1.96 E-8 - 1.79 E-8 1.91 E-8 2RT-6759 N 3RT-6753 Note 1 Note 1 Note 1 Note 1
':. 3RT-6759 2.08 E-9 3.14 E-9 4.59 E-9 2/3RT-7813 2.11 E-9 3.20 E-9 4.71 E-9 2RT-7817 2RT-7821 2.08 E-9 3.17 E-9 4.61 E-9 3RT-7817 2.24 E-9 2.99 E-9 4.63 E-9 i
3RT-7821 2.15 E-9 3.30 E-9 4.72 E-9
*)Ci/cc/ cpm Note 1 -- These calibration constants will be provided prior to utilizing Unit 3 Steam Generator blowdown bypass lines.
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'N 1-15 Rev. 10 05-18-83
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