ML19326D002
| ML19326D002 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/14/1971 |
| From: | Phillips J ARKANSAS POWER & LIGHT CO. |
| To: | Rogers L US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8004300630 | |
| Download: ML19326D002 (11) | |
Text
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!<1 b 8004300 D G ARK ANS AS POWER G LIGHT COMPANY DTH & LOUIS 8AN A DTHEETS LIT TLE ROC'K. AAK?"'5AS 722o3. (5 oil 372-4311 October 14, 1971
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41 Ac.'&
ob Mr. Lester Rogers, Director
-4 Division of Radiological and DCT101971 -
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Environmental Protection U. S. Atomic Energy Coc: mission g.
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8 tu mg Washington, D. C.
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SUBJECT:
ARKNISAS POWER & LIGHT COMPANY ARKNISAS NUCLEAR ONE-UNITS 1 NID 2 DOCKET NUMBERS 50-313 AND 50-368
Dear Mr. Rogers:
In response to your letter of September 7,1971, a summary of maximum design, maximum expected, and actual expected gaseous releases from Arkansas Nuclear One-Units 1 and 2 is attached in Tables A through F.
Shown below is a list of the information requested by that letter with the appropriate tables refer-enced in reply:
1.
Maximum design yearly releases of each gaseous isotope: Tables A and B.
2.
Actual expected yegrly releases of each gaseous isotope: Tables A and B.
s 3.
Maximum design releases of each gaseous isotope per event: Tables C and D.
h.
Actual expected releases of each gaseous isotope per event: Tables C and D.
5.
Annual average concentrations at the Exclusion Dist'ance for maximum design releases: Tables A and B.
6.
Annual average concentrations at the Exclusion Distance for actual expected re-leases :
Tables A and B.
7.
Time-of-release concentrations at the Exclusion Distance for maximum design releases : Tables C and D.
8.
i Time-of-release concentrations at the Exclusion Distance for actual expected releases: Tables C and D.
9.
Ci-Sec/M3 for all the above: Tables A, B, C and D.
- bE0E TAX P AYING. INVE STOA OWNEO MEMBER M890LE SOUTH UTILITIES SYSTEM
c.
10.
Maximum expected releases and maximum expected releases per event for Unit 1: Table E.
11.. Maximum expected releases and maximum expected releases per event for Unit 2: Table F.
12.
Annual average and time of release at Exclusion Distance for maximum expected releases of Unit 1: Table E.
13.
Annual average and time of release at Exclusion Distance for maximum expected releases of Unit 1.
Table F.
Assumptions used for each table are listed below the Table.
In addition to these, the follovipg general bases were used te evaluate the vacte volumes generated:
1.
Maximum Design Releases for Unit 1 - Based on operating cycle listed in Unit 1 FSAR, Section ll, Page 11.1, the 625,36Dgallons of vaste produced prior to processing in the vaste system of Unit 1 is assumed to be at the maximum 1% failed fuel concentration listed in the Unit 1 FSAR, Page 11-27, Table 11-5 2.
Maximum Design Release Cvele for Unit 2 - Same as for Unit 1 with addition of two hot shutdowns and deletion of draining requirement As in Item 1 above the 780,000 gallons of vaste produced prior to processing in the vaste system of Unit 2 is assumed to be at the maximum 1% failed fuel con-centration listed in the Unit 2 PSAR, Table 11.1-2.
3.
Mnximum Expected Releases for Unit 1 - Assumes two cold startups from refueling concentration per year and operation of plant at 2568 MWt for 310 days. The 3,70,000 assumed to be at average 1% failed fuel concentrations. gallons of vaste These average concentrations were obtained by calculating average interval concentrations using Table 11-5 in the Unit 1 FSAR and then, using interval bleed rate data, averaging these concentrations over the vaste volumes generated as a result of reactor coolant system deboration.
h.
Maximum Expected Releases for Unit 2 - Gaseous vaste quantities are based on the degasification of 780,000 D; 780,000 gallons is the gallons of vaste stated in Tables B and expected volume of bleed vastes based on oper-ating data.
This vaste in assumed to be at an average 1% failed fuel con-of the isotope removed from the reactor coolant system ac postulated cycle discussed in 2 above and dividing by the total vaste volume produced in the cycle.
Although the methods used for calculating average coolant concentrations Kr85) from both units, as expected, agree quite vell. differ signif is postulated for evaluating expected releases, the quantities dischargedNo ma from two plants of similar power output and postulated fuel failure should be the same, since the core can only generate so much of an isotope in a T
'1
s 3-given~ operating cycle.
The values for Kr85 in the attached tables differ significantly due to differences in the values as umed for the escape rate coefficients (6.5 x 10-0 for Unit 2 vs. 1.0 x 10-for Unit 1), and in the time and operation that the postulated fuel failure occurs.
Unit 1 estimates that the 1% fuel failure occurs at the beginning of the third core cycle in the remaining first cycle fuel, whereas Unit 2 assumes 1% fuel failure from the start of operation.
5 Actual Expected Releases for Unit 1 - Similar to 3 above, except that.1%
failed fuel is postulated.
Average.1% failed fuel concentrations were obtained by assuming that fuel failure is proportional to the average reactor coolant concentration, i.e.,.1% failed fuel concentration = 1/10 (1% failed fuel concentration.)
6.
Actual Expected Releases for Unit 2 - Similar to h, except that.1% failed fuel is postulated, where.1% concentration = 1/10 (1% failed fuel concen-tration.)
All airborne concentrations were calculaged at ghe Exclusion Distance of 10h6 M using the annual average X/Q = 2.1 x 10- sec/m. This value is valid for calculation of time of release concentrations since sufficient flexibility is available for system operation to ensure that at least annual average meteoro-logical conditions exist prior to discharge.
Concentrations of the restricted area boundary of Th6 M vere not calculated but may be easily determined by multiplying the Exclusion Distance concentrations by 1.190 to account for the difference in X/Q at the shorter distance.
If you have any questions concerning this information, please contact us.
Very truly yours,
@l2N%
--.J. D. Phillips Vice President O
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STATE OF ARKANSAS COUNTY OF JEFFERSON SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this 18th day of October
, 1971.
v Mr Notary Public 3
My Commission Expires:
January 2, 1973 W
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4 TABLE A MAXIMUM DESIGN AND ACTUAL EXPECTED YEARLY AVERAGE EXCLUSION DISTANCE CONCENTRATIONS FOR UNIT 1 (3)
(h)
(6)
(1)
Actual (5)
Actual (2)
Max Design Expected Actual Expected-Max Design
, Max Design Exclusion Reactor Expected Exclusion Reactor Coolant Cone Annual C1 Ci-See Distance Cone Coolant Conc
- Annual Ci Ci-See Distence C ""
In";t+pe (uCi M )
Released MJ (uCi/M )
(uCi/ml )
Released M
(uCi/M-)
3 3
3 k
Kr 85 98 2.30no h.83no-2 1.55no-3
.h91 68h 1.h 36no-3 4.62no-5 Xa 131m 2.0 835 1.75no 3 5.6hno-5
.1ho 33.9 7.12 no-5 2.28no-6
-6 Xe 133m 2 70 765 1.61no 5.15no-8
.232
.039 8.19 no-8 2.62no-9 0
Xa 133 2h3 1.09n0 2.29no-2 7.36n0-4 19.12 509 1.06 no-3 3.h2no-5 (1) Maximum 1% failed fuel. concentration.
(2) Based on complete degasification of 625,360 ganons of bleed vastes and 30 day decay in vaste gas decay tanks.
(3) Yearly average concentration based on X/Q = 2.1no-6 sec/M,
3 (h)
.1% failed fuel average coolant concentration.
- (5) Based on complete degasification of 370,000 gallons of bleed vastes and 30 day decay in vaste gas decay tanks.
(6) Yearly average concentration based on N/Q = 2.1n0-6 sec/M,
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TABLE B
)
MAXIMUM DESIGN AND ACTUAL EXPECTED YEARLY AVERAGE, EXCLUSION DISTANCE CONCENTRATIONS FOR UNIT 2 (4)
(6)
(1)
(3)
Actual (5)
Actual-Max Design
.(2)
Max Design Expected Actual Expected-Reactor
. Max Design Exclusion Reactor Expected Exclusion Coolant Cone Annual C1 Ci-See Distance Cone Coolant Cone Annual Ci ni Raa_
ii.tance Cone Inntope (uCi/nl)
Released M
(uCi/M )
(uCi/ml)
Released M3 3
3 (uCi/M )
Kr 85 h.80 1.hlX10 2 96X10-2 9,39xyo h
.097 260 5.h6X10-1.75X10 Xm 131'n -
3.23 1.68X103 3.53X10-3 1.13X10-0
.12 56 1.18X10-4 3.78X10- '
h Xe 133.
322 1.81X10
- 3. 80X10-2 1.22X10-3 20 1030 2.16X10-3 6.9hX10-3 (1) Maximum 1% failed fuel concentration @ 70 F.
0 (2) Based on complete degasification of 780,000 gallons of bleed wastes and 30 day decay in gas decay tanks.
-(3) Yearly average concentration based on annual X/Q = 2.1X10-6 sec/M3.
(h)
.1% failed fuel average coolant concentration.
(5) Based on degasification of 780,000 gallons of bleed wastes, degasification df = 10, and 30 day decay.
(6) Yearly average concentration based on annual X/Q = 2.1X10- sec/M,
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TABLE C UNIT 1 MAXIMUM DESIGN AND ACTUAL EXPECTED EXCLUSION DISTANCE CONCENTRATIONS AT TIME OF RELEASE OF SINGLE GAS TANK CONTENTS (1)
(5)
(h)
(8)
Max Design (2)
Actual (6)
Actual Max Design Expected Actual Reactor Max Design (3)
Exclusion Reactor Expected (7)
Exclusion Expected Coolant Cone Ci/ Tank Ci-Sec Distance, Cone Coolant Cone Ci/ Tank C 4 -ht Distance Con Icotope (uCi/ml)
Discharged M3-(uC1/M )
(uCi/ml)
Discharge M3 3
3 (uCi/f4 )
Kr 85 9.8 2875 6.0hno-3 2.33no-2
.491 136.8 2.87X10 h 9 97X10-3 Xa 131m 2.0 104 2.18no-h 8.42x10-h
.1ho 6.78 1.h2X10-5 h.93n0-U X2 133m 2 70
.095 1 99n0-I 7.71no-7
.232
.0078 1.6hno-8 5.69X10-7 Xe 133 2h3 1362 5 2.86X10-3 1.10no-2
'19 12 101.8 2.1hX10-h 7.hino-3 (1) Maximum 1% failed fuel concentration.
(2) Based on generation of 19,h00 Ft.3 of gas per cycle, 8 tank releases per year, 30-day decay.
(3) Based on annual average K/Q = 2.1X10-6 3
sec/M, since tank releases may be scheduled to conform with average conditions.
(h) Based on 3-day tank release & X/Q = 2.1X10-6 3
sec/M,
(5)
.1% failed fuel average cycle concentration.
(6) Based on generation of 12,270 Ft.3 of gas per cycle, 5 tank releases per year, 30-day decay.
(T)
Based on annual average X/q = 2.1X10-6 sec/M3 (8) Based on 8.ho ua Smrah
TABLE D UNIT 2 MAXIMUM DESIGN AND NORMAL EXCLUSION DISTANCE CONCENTRATIONS AT TIFE OF RELEASE OF SINGI' GAS TANK CONTENTS (5)
(8).
(1)
(h)
Actual (6)
Actual Max Design (2)'
Max Design Expected Actual Expected Reactor Max Design (3)
Exclusion Reactor Expected (7)
Exclusion Coolant Cone Ci/ Tank Ci-See Distancegone Coolantgonci Ci/ Tank Ci-See Distance c
3 (uCi/M )
(uCi/M )
Discharge M
(uCi/M )
Irotope (uCi/ml)
Discharged M3 3
2.16X10 4 8.3hX10-
.Kr 85 4.80 1030 2.16X10-3 3.3hX10-3
.097 103 X2 131m 3.23 120 2.52X10-b 9.72X10 h
.12 12 2 52no-5 '
9.72X10-5 Xe 133 322 1360 2.86no-3 1.10no-2 20 136 2.85X10-h 1.10no-3 (1) Maximum 1% failed fuel concentration @ 700F.
(2) Based on one complete Rx coolant system degasification 8 90% of core life with 1% failed fuel and 30-day decay.
(3) Based on annual average X/Q = 2.1X10-6 sec/M since tank releases may be scheduled to conform with average 3
meteorological conditions.
(h) Based on 3-day tank release and X/Q = 2.1X10-6 sec/M,
3 (5)
.1% failed fuel average concentration.
(6) Based on one complete Rx coolant system degasification 8 90% of core life with.1% failed fuel and 30-day decay.
(7) Based on annual average X/Q = 2.1X10-6 sec/M,
3 (8) Based on 3-day tank release and X/Q = 2.1n o-6 sec/M,
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4 TABLE E MAXIMUM EXPECTED YEARLY AVERAGE AND TIME OF RELEASE 0F SINGLE TANK CONTENTS CONCENTRATIONS AT EXCLUSION DISTANCE FOR UNIT 1 (5)
(1)
(2)
(3)
(4)
Actual Max Expected Max Max Expected Max Expected Reactor Expected Exclusion Expected Exclusion Coolant Cone Annual C1 Ci-Sec Distancegonc Ci/ Tank Ci-Sec Distance Conc sotons (uCi/ml)
Released M3 (uCi/M )
Discharge M
(uCi/M )
3 3
- r 4.91 7190 1.51no 4.87no 1h38 3.02no-3 1.16no-2
- e 131m 1.4 392 8.23no-k 2.64no-5 78.4 1.6hno-k
- 6. 34no-
'c 133:n 2.32
.476 Ino-6 3.21no-0
.095 2.on0-7 7 71n0-7 e133' 191.2 6025 1.26no-2 4.04X10 1205 2 53no-3 9 76no-3
- 1) 1% failed fuel average cycle concentratio'n.
- 2) Based on complete degasification of 370,000 gallons of bleedwaste and 30-day decay.
- 3) Yearly average concentration based on X = 2.1X10 sec/M,
3 Q
.)
Based on generation of 12,270 cubic' feet of gas per cycle, 5 tank releases per year and 30-day decay.
3
- 3) Based on 3-day tank releases and X = 2.1X10-6 sec/M,
Q
.s 9
W
TABLE F MAXIMUM EXPECTED YEARLY AVERAGE AND TIME OF RELEASE 0F SINGLE TANK CONTENTS CONCENTRATIONS AT EXCLUSION DISTANCE FOR UNIT 2 (5)
(1)
(2)
(3)
(4)
Actual Max Expected Max Max Expected Max Expected Reactor Expected Exclusion Expected Exclusion Coolant Cone Annual Ci Ci-See Distancegone Ci/ Tank-Ci-Sec Distance Cone Isotopa (uCi/ml)-
Released MJ 3
(uCi/M )
Discharged MJ (uCi/M )
-3 Kr 85 97 2880 6.05n0 1.93X10-1030 2.16no-3 8.3hno-3
-3 Xe 131m 1.2 620 1.3no 4.16no-5 120 2.52no-h 9 72n0-4 4
Xe 133 200 1.15n0 2.42no-2 7 73X10-0 1360 2.86no-3 1.10no-2 (1)' 15 Failed fuel average cycle concentration.
(2) Based on complete _ degasification of 780,000 gallons, degasification DF of 10, and 30-day decay.
(31 Yearly average concentration based on X = 2.1x10-6 sec/M,
3 (4)- Based on one complete reactor coolant ystem degasific on at 90% of core life with 1% failed fuel and 30-day decay.
(5) Based on 3-day tank releases and X_ = 2.1X10-6 sec/M,
3 Q
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