ML20207T627
| ML20207T627 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/23/1986 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20207T611 | List: |
| References | |
| PROC-861223, NUDOCS 8703240191 | |
| Download: ML20207T627 (99) | |
Text
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I SEQUOYAH NUOLEAR PLANT OFFSITE DOSE CALCULATION MANUAL .
DATES OF REVISIO!:S Original ODCM 02/29/80*
04/15/80**
Revision 1 10/07/B0**
Revision 2 11/03/80, 02/10/81 Revision 3 04/08/81, 06/04/81**
11/22/82 (10/22/81, Revision 4 11/28/81, 04/29/82**)
10/21/82**
Revision 5 01/20/83**
Revision 6 03/23/83**
Revision 7 12/16/83**
Revision 8
- 03/07/84**
Revision 9 04/24/84**
Revision IO 08/21/84**
Revision 11 02/19/85**
Revision 12 ~
Revision 13 12/02/85 Revision 14 04/14/86 Revision 15 11/05/86***
- w!A a 1 23 14 RARC Charrman /Datf boMexema%k6 Manager, RO 'Date 4
\;
s
\
8703240191 970224 PDR ADOCK 05000327 R PDR
- Low Power license for Sequoyah unit 1
- RARC Meeting date
- Date approved by RARC Chairman s Revision 15 ,
s s
...-.-t_. . - - - - - - ,
y- s- _
TABLE OF CONTENTS (continued)
Liquid Effluents 17 2.
2.1 Concentration 17 2.1.1 RETS Requirement 17 2.1.2 Prerelease Analysis 17 2.1.3 MPC - Sum of the Ratios 18 2.2 Instrument Setpoints 19 2.2.1 Setpoint Determination 19 2.2.2 Post-Release Analysis 20 2.3 Dose 20 2.3.1 RETS Requirement 20 2.3.2 Monthly Analysis 21 2.3.2.1 Water Ingestion 21 2.3.2.2 Fish Ingestion 23 2.3.2.3 Recreation 23 2.3.2.4 Monthly Summary 25 2.3.2.5 Dose Projections 25 2.3.3 Quarterly and Annual Analysis 25 2.3.3.1 Individual Doses 25 2.3.3.2 Population Doses 28 2.4 Operability of Liquid Radwaste Equipment ,
28
- 3. Radiological Environmental Monitoring 30 3.1 Monitoring Program 30 3.2 Detection capabilities - 30 3.3 Interlaboratory Comparison Program 30 34 Land Use Census 30
- 4. Arnual Maximum Individual Doses - Total 31 TOC-2 Revision 15
& .t SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE T.ISTING REVISION 15 ,
~
Revision Page TOC 1 through TOC 2 Revision 15 1
Revision 6 2
Revision 14 3
Revision 12 Original 4
5 Revision 14 6
Revision 4 7
Revision 8 8 through 9 Revision 5 10 Revision 14 ,
los Revision 15 11 Revision 13 12 Revision 12 13 - Revision 14 -
14 through 15 Revision'15 15a Revision 12 16 Revision 13 .
16a Revision 8 Table 1.1 (Page 1) Revision 12 Tatle 1.1 (Page 2) Revision 15 Table 1.2 (2 pages) Original Tabis 1.3 (8 pages) Revision 4 Table 1.4 Revision 12 Table 1.4A (removed from document) Revision 9 Table 1.5 Revision 12 Tables 1.6 and 1.7 Revision 5 Table 1.8 (2 pages) Original Figures 1.1 and 1.2 Original Figure 1.3 Revision 3 17 Original 18 Revision 15 19 Revision 15 20 Revisicn 6 21 through 23 Revision 15 24 through 25 Revision 10 26 through 29 Revision 8 i Table 2.1 (3 pages) Revision 7 Table 2.2 Revision 5 Table 2.3 (3 pages). Revision 10 Table 2.4 a-c Revision 5 30 . Revision 13 30s Revision 15 Table 3.1-1 (5 pages) Revision 13 Table 3.1-2 Revision 15 Table 3.1-3 Revision 13 Table 3.2-1 (3 pages) Revision 13 Figure 3.1-1 through 3.1-5 Revision 13 Figure 3.1-6 Revision 15 Figure 3.1-7 Revision 14
! 5R i fcr occh nuclid2 is also ecleulated b'y en altsenctiva meth:dology using the reporting requirements of 10 CFR 50.73 (2 times the 10 CFR 20 Appendix B.
Table II air concentrations). Release rate limits Ri for each nuclide are .
calculated using this methodology as given below:
'S Ri = (2)(MPCi )/(5.12 x 10-6)(10-6)
= 3.91 x 1011 where MPCi = the 10 CFR 20, Appendix B. Table II, air concentration, yCL/cc.
5.12 x 10-6 = worst land site boundary X/Q, s/m3 (Table 1.4).
10-6 = conversion factor, m3/ce, The release rate limit, Ri , for each nuclide will be the most restrictive one calculated using both methodologies.
For a known mixture of n nuclides the release rates must be such that:
n Qi .
<1 "
Ri i=1 Appropriate release rate limits in yCi/s for each nuclide and release point will be provided to plant personnel for use in establishing monitor setpoints. The setpoint in counts per minute for each gaseous effluent monitor will be established using plant instructions. The general equation used by plant personnel in establishing setpoints in epm from release rate limits in vCi/s is the same as that used in Step 2a.
1.2 Monthly Dose Calculations Dose calculations will be performed monthly to determine compliance with specifications 3.11.2.2 and 3.11.2.3. These specifications require that the dose rate in unrestricted areas due to gaseous effluents from each reactor at the site shall be limited to the following:
For noble gases,
- 1. During any calendar quarter, 5 mrad to air for gamma radiation and 10 mrad to air for beta radiation. .
- 2. During any calendar year, 10 mrad to air for ganma radiation and i
20 mrad to air for beta radiation.
For iodines and particulates,
- 1. During any calendar quarter, 7.5 mram to any organ.
l
- 2. During any calendar year,15 mram to any organ.
-10a- Revision 15
. . . ,=. . _ _ _ . - . . ._ . -. _ _ _ . . - . - .
l Fcr dstsrmining the beta dssa to cir:
1 ( ,
l (1.17)
DSn=tm Ini DFBi i
where:
Dg n = beta dose to air for sector n, mrad.
3 Ii n
= air concentration of radionuclide i in sector n, pCi/m DFBi = beta to air dose factor for radionuclide i, mead /yr per pCi/m3 t, = time period considered, ye The sector having the highest total dose is then used to check compliance with specification 3.11.2.2.
- 1.2.2 Todines and Particulates 1
- sten 1 .
Doses will be calculated using the methodology described in thEs step. If 50 percent of the applicable limits are exceeded, step 2 will be performed. .
Equations and assumptions for calculating doses fram releases of iodines and particulates are as follows:
Assumptions
- 1. Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone and teen g.i. tract from vegetable ingestion.
u
- 2. Real cow locations are considered for the milk pathway and nearest resident-locations with home-use gardens are considered for the vegetable
, pathway.
- 3. The highest annual-average D/Q based on 1972-1975 meterological data for ground level releases will be used for ingestion pathway doses.
- 4. No credit is taken for radioactive decay.
- 5. Releases of I-131 and I-133 are considered for the milk pathway. Sr-89, if Sr-90, Cs-134, and Cs-137 releases are considered for the' vegetable pathway to the child bone. Co-58 and Co-60 releases are considered for the vegetable pathway to the teen g.i. tract.
- 6. The calculations extrapolate doses assuming that only 90 percent of the total dose was contributed. -
4
- 7. The cow is assumed to graze on pasture grass for the whole year.
l Revision 15 i
I i
f
4 Eaustions .
For determining the thyroid dose from milk ingestion of I-131 and I-133:
DTH = x IOS (1.18)
(0.9) x 3.15 x 107 where:
DTH = thyroid dose from I-131 and I-133, mrom.
Qi = monthly release of nuclide i, Ci.
DF = nuclide i milk ingestion dose factor to infant. (Table 1.7)
D/Q = relative deposition rate, 2.96 x 10-'m-2 0.9 = fraction of dose expected to be contributed by I-131 and I-133 3.15 x 107 = s/yr.
10' = pCi/Ci Equation 1.18 then reduces to:
DTH = 1.04x10-so .
I Qi DFi i
For determining the bone dose from vegetable ingestion:
106 (1,19)
QiDFi D/Q DBC1 =
3.15 x 107(0.9) where:
15 DBC1 = bone dose to child from nuclide i, mrem.
Qi = monthly release of nuclide i, Ci.
DFi = Vegetable ingestion dose factor to child, 2.25 x 1011, 1.36 x 1013, 1.59 x 1011, and 2.58 x 1011 mram/yr per pCi/m2 -s for Sr-89 Sr-90, Cs-134, and Cs-137, respectively. (As per Regulatory Guide 1.109 and NUREC/CR-1004 methodologies).
D/Q = relative deposition rate, 7.10x10-'m-2 3.15x107 = s/yr.. .
10' = pCi/C1.
0.9 = fraction of total bone dose expected to be contributed by Sr-90.
Equation 1.19 then reduces to DBC = 2.50 x 10-10 y qg pyg ,g i
Revision 15
, . ~. -
) * .
TABLE'I.1 EXPECTED ANNUAL ROUTINE Gr.SEOUS RELEASES FROM ONE UNIT AT SEOUOYAH NUCLEAR PLANT
- CURIES / YEAR '
AUKILIARY TURBINE SERVICE NUCLIDE BUILDING CONTAINMENT BUILDING BUILDING i
Sr-89 7.6(-7) 1.2(-7) 1.6(-7) 1.0(-8)
Sr-90 2.2(-8) 4.3(-9) 8.4(-9) 3.5(-10)
Sr-91 1.5(-6) 1.2(-8) 8.9(-8) 1.6(-8)
Y-90 3.8(-8) 4.7(-9) 8.2(-9) 5.1(-10)
, Y-91m 9.1(-7) 7.4(-9) 4.1(-8) 9.6(-9)
Y-91 4.4(-6) 7.0(-7) 1.9(-6) 7.0(-8)
- Y-93 3.0(-7) 2.4(-9) 3.6(-8) 3.4(-9) ,
J Zr-95 1.3(-7) 2.1(-8) 8.4(-8) 2.4(-9)
- Nb-95 1.1(-7) 2.2(-8) 8.4(-8) 2.2(-9) i Mo-99 9.9(-4) 3.0(-5) 1.4(-4) 1.2(-5)
Tc-99m 8.9(-4). .2.8(-5) 1.0(-4) 1.0(-5) .
Ru-106 2.2(-8) 4.1(-9) 8.4(-9) 3".5 (-10)
Te-132 6.0(-5) 2.0(-6) 2.1(-5) 8.3(-7)
- Ba-140 4.8(-7) 4.4(-8) 2.1(-7) 7.3(-9) .
La-140 3.4(-7) 4.6(-8) 1.4(-7) 5.3(-9) co-144 7.2(-8) 1.4(-8) 4.2(-8) 1.3(-9)
Pr-143 1.1(-7) 1.1(-8) 4.2(-8) 1.6(-9)
Pr-144 7.7(-8) 1.4(-8) 2.8(-8) 1.2(-9) l /i" Np-239 2.7(-6) 7.0(-8) 1.2(-6) 4.0(-8) 4 i
4 t
i 1
j
- l I
i 4
-Sheet 2- Revision 15
}
j
a a 2.1.3 MPC-Sum of th' Raties .
The sum of the ratios (RJ) for each release point will be calculated by the following relationship.
+ +*** + E + *** *
(2.2)
RJ= gp Cg MPQ where:
C1
= undiluted effluent concentration of radionuclide i, as determined in Section 2.1.2,yCi/ml.
MPC1 = the MPC of radionuclide i, as specified in Section 2.1.1, yCL/m1.
= the sum of the ratios for release point j.
RJ Therearefourpossibleliquidreleasepojntsintocoolingtowerblowdown.
- 1. Steam Generator} N Cooling Tower Blowdown = F Steam Generator' ?
2.
- 3. Condensate Waste - '
DomineralizerTanks '
- 4. Radwaste Tanks ;
v The sum of the ratios at the diffuser pipes must be 1 1 due to the releases from any or all of the above sources. The following relationship will assure this criterion is met:
_f 1El + f9E2 + f'E3 + fAEA < 1
- (2.3)
F+f1+f2+f3 + f4 where:
f,f i 2 f.f4 3 = the effluent flow rate (gallons / minute) at the respective release point determined by plant personnel.
R,R,R,R4 = the sum of the ratios of the respective 1 2 3 release point as determined by Equation 2.2. , ,
F = mininum dilution flow rate for prerelease analysis (cooling tower blowdown,
- gallons / minute) = 15,000 gal / min.
For releases into the cooling tower blowdown line, additional mixing is assumed to occur in the diffuser pond when SQN is operating in Helper or Open cooling mode.
Revision 15
I ?
The results, from field tests conducted in September 1979, are exprocccd in terms of relative concentration r:
r - 9.9x10-5 (F + fi+f2+f3+f) 4 Equations 2.3 then becomes 9.9x10-5 (F + ft+f2+f 3 + f4 ) f (R 1 1-1)
+ f 2(R2-1) + f3 (R3-1) + f4(R4-1) g,F (2.3a) 2.2 Inst rument Setpoints 2.2.1 Setpoint Detemination The setpoint for each liquid effluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal samma emitter, ,
geometry, and detector efficiency are combined to give an equivalent satpoint in counts per minute (cpm). The physical and technical description location and identification. number for each liquid affluent radiation detector is contained in plant documentation. _
The respective alarm / trip setpoints at each release point will be set such that the sum of the ratios (RJ) for all points, as calculated by Equation 2.3, will not exceed 1. The R3 is directly related to the total concentration calculated by Equetion 2.1. An increase in the concentration would indicate an increase in the respective Rj. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm / trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint(s) be set above the affluent concentration (C3 ). That is, Sj = b3 * (Cj + B) (2.4) where Sj = desired alarm / trip setpoint at release point 3 bj = scaling f actor to prevent alarms / trips due to variations in the effluent concentrations at release point j. ,
monitor response based on the total concentration in the liquid C3= effluent at release point j specified by Equation 2.1, pCi/ml.
B= monitor background prior t'o release.
Revision 15
- b. During any calendar year to 1 3 mrem to the total body and to i 10 mrem to any organ.
To ensure compliance, cumulative dose calculations will be performed at least once per month according to the following methodology.
2.3.2 Monthly Analysis Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose. If tha projected dose exceeds the above limits, the methodology in Section 2.3.3 will be implemented.
The 21 nuclides (listed below) contribute more than 95 percent of the dose to the total body and the most critical organs for each pathway. The critical',
organs considered for water and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid and liver.
H-3 Na-24 Cr-51 Mn-54 Fe255 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Zr/Nb-95 Mo/Tc-99m Ag-110m Sb-124 I-131 I-133 Cs-134 Cs-136 Cs-137 A conservative calculation of the monthly dose will be done according to the i following procedure. First, the monthly release data will be obtained and the activities released of each of the above 20 radionuclides, if identified, will be noted. This information will then be used in the following calculations.
2.3.2.1 Water Inmestion The dose to an individual from ingestion of water is described by the following equation.
20 3 (2.11)
Dj = 0.95 I (DCF)ij Iij , rem i=1 l
Revision 15
.* s .
where:
Dj = dose for the jth organ from 20 radionuclides, rem j = the organ of interest (bone, CI tract, liver, thyroid and total body).
a 0.95 = conservative correction factor, considering only 20 radionuclides.
DCFi j = critical ingestion dose commitment f actor for the jth organ of adult or child from the ith radionuclide rem /pCL, see attached as Table 2.1.
Ij i
= monthly activity ingested of the ith radionuclide by the critical age group for the jth organ, pCi. '.
I ij is described by I i j= At V43 (30) ~ '#
- Fd (7.34 x 1010) where: -
Ai = activity released of the ith radionuclide during the month, l pCi.
Vij = maximum individual's water consumption rate corresponding to the age group selected for the critical DCFij above (Adult: 2000 mL/d, Child: 1400 mL/d; Regulatory Guide 1.109) i 30 = days per month.
I F = average river flow at Chickamauga Dam for the month (cubic feet per second),
d = fraction of river flow available for dilution (1/5).
7.34x1010 = conversion from cubic feet per second to milliliters per month.
Considering the conversion factor from rem to mesa ( x 10s), the dose equation then becomes:
20 2.15 x 10-* (2.13) 3 Dj = F I (V x DCF)ij *Ai , mesa i=1 l
T h,
is. <
"/C
('
Revision 15 I
i
a' * .
2.3.2.2 Fish Intestion
! The dose to an individual from the consumption of fish is described by .
Equation 2.11. In this case the activity ingested of the ith radionuclide (Iij) is described by yci (2.14)
Iij = Fd ( 3 x 010) ,
where A1 = activity released of ith radionuclide during the month, yCL B1
= effective fish concentration factor for the ith radionuclide uCilt, see attached as Table 2.2.
pCi/mL ,
l Mj i
= amount of fish eaten monthly by maximum individual l
4 corresponding to age group selected for the critical DCrij, ~
above (Adult: , 1750s, Child: 575g; Regulatory Guide 1.109).
F = average-river flow at Chickamauga Dam for month (cubic feet per second) d = fraction of river flow available for dilution (1/5) 7.34x1020= conversion from cubic feet per second to milliliters per month.
The dose equation then becomes Dj =
f08 I At B1 (M
- DCF)ij i=1
, mram (2.15)
Considering the conversion f actor fram ram to area.
j Recreation The total body dose to an individual via the shoreline recreation pathway is described by the following equation. For this calculation, the total dose is estimated based on a calculation for co-58. Co-60, Cs-134, and Cs-137. These four nuclides are expected to contribute over 95 percent of the recreation dose. .
D = ' "#** (2.16) 0 95 '
8 60 -
i i=1 l
i i
Revision 15
) e .
SQN TABLE 3.1-2 ATMOSPHERIC AND TERRESTRIAL MONITORINC STATION LOCATIONS SEQUOYAH NUCLEAR PLANT Location Reference Approximate Distance and Number Sample Station Direction from Plant 2 LM-2 SQ 0.8 mile N 3 LM-3 SQ 1.3 uiles SSW 4 LM-4 SQ 1.5 miles NE',
5 LM-5 SQ 1.7 miles NNE ,
7 PM-2 SQ (Chester Frost Park) 3.8 miles SW 8 PM-3 SQ (Daisy) 5.6 miles W .
9 PM-8 SQ (Harrison) 8.7 miles SSW 10 PM-9 SQ (Lakeside) 2.7 miles WSW 11 RM-1 SQ (Chattanooga, Riverside) 16.7 miles SW 12 RM-2 SQ 17.5 miles NNE 13 RM-3 (Cleveland) 11.3 miles ESE
- 14 RM-4 (DunlaP) 19.5 miles WNW 18 Farm J 1.3 miles NW 19 Farm HW 1.3 miles W 20 Farm EM 2.5 miles N
, 21 Farm BR 2.3 mile.: SSW 22 Farm LE 3.5 milen S 23 Farm CO 1.7 miler E 25 Farin B (control) 43.0 miles NE 26 Farm C (control) 16.0 miles NE 27 Farm 5 (control) 12.0 miles NNE 48 Farm H 4.3 miles NE r.
's 4 Revision 15
- t. o .
Figure 3 1-6 MILK AND VEGETATION SAMPLING LOCATIONS y ,
y s
e.
~
19 v t ,-
4 3,
)
l 1 er l 3e s 09 O y
O Hilk and vegetation collected s
e .
O Vegetation only collected 1 2 Note: Vegetation is also collected at each air monitoring station.
See Figure 3 1-1
.?;iO C:'#
5 ' l s
e ,c.js, i,n ; ,
i o ich '
I Description of Change _J See page 10a of Sequoyah Nuclear Plant (SQN) ODCM. The equation for Ri should be:
Rg = (2) N C1 )/(5.12 x 10-6)(10-6)
= 3.91 x 1011 Justification of change In the attachment to the October 30, 1985 memo from E. A. Belvin to H. L. Abercrombie, a footnote presents the correct equation for Rt .
When this equation was transferred to the ODCM the divide symbol was ,
inadvertently omitted. However, release rate limits transmitted in the referenced memo were calculated using the correct equation.
Effect on Setpoint and Dose' Calculations _,
None .
APPROVED DC
. 4 m
&M ali L-V RAhO Enr.in./;,,0.0 t t lTlPG '
Description of Change [
Monthly I/ Particulate dose methodology was revised to include the contribution from Sr-89 Cs-134, and Cs-137. Changes effected are on pages 14 and 15.
Justification of Change The monthly vs. quarterly methodology evaluation presented to the spring RARC meeting indicated that some underconservatism could result using the monthly method if one did not include Sr-89, Cs-134, and Cs-137 contributions.
- Effect on Setpoints and Dose Calculations No effect on setpoints. Calcula'ted doses will be more conservative.
.i r
i r
0341c . __ _- ..__ _. . - . _ _. .
lADPisOVEQ-
/ y gjg/
RARC Onr..r.J.;4w II lTl%
Description of Chanze Table 1.1. Pr-144 release in curies /yr from the containment should be 1.4 (-9) instead of 1.4 (-8).
Justification Typographical error Effect on Setpoints of Dose Calculations None 9
o=
d 0341c ~. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ __ _ _ _ _ _ _ -
APPROVED BY-
!- 8 h
RAP.C Cnmn./ Dam Description of Channe N 0 .
i .
Table 3.1-2 of the Sequoyah Nuclear .--... s x , v. . # N Calculation Manual is to be revised by deleting Farin M. 3.5 miles NNE. This farm is to be deleted because milk samples are no long available at this location. This change is also reflected in Figure 3.1-6.
Evaluation and Justification for Chante The change is necessary to accurately reflect the milk sampling program conducted at SQN.
Effect on the Accuraev and Reliability of Dose Calculations and Setypint Determinations This chan5e has no effect on the accuracy or reliability of dose calculations or setpoint determinations.
J c
i f
i I
4 e
t i
, - - . ------,-w ,w -- -7,,, ,_.,,-,,-- -.- -- .-
v,,,__,,.,m,y -,-,---,-,,_,,,,-,p-------.e -
--~nn._ --- -- .,
fpn&-TERc CL.,
- t. ~
ltlcf84 SON ODCM changes 10/15/86 RARC mtg pesertorion of chance The label f or the third possible liquid release point into the cooling tower blowdown is being changed from " Condensate Tanks" to " Condensate Waste Dominerali=er Tanks." This change appears on page 18.
Analysi s or Evaluation Justifyino the Chance This change clarifies the wording used on the diagram to more closely match the terminology used by the plant personnel.
Determination of the Effect of the Chance on the Accuraev er -
Rel i abi l i tv of the Dose Cal cul ati ons or Setooint Det ermi nat i ons This change will have no effect on the accuracy or reliability of the dose calculations or setpoint determinations.
b 4
S
AFPROVED BY' ill$f"/9&
RARC Cnmn/ste SON ODCM changes '
10/15/86 RARC mtg Descri pt i on of chance Equation 2.3, on page 18, is changed to another algebraic form.
Analysis or Eval uati on Justifyino the Chance This change was made to enable the equations used in the ODCM to more closely t esemble those actually used by the plant personnel.
Det ermi nat i on of the Effect of the Chance on the Accuraev or Rel i abi l i ty of the Dese* Cal cul ati ons or Setooint Det ermi nat i ons This change has no effect on the accuracy or reliability of.the dose calculations or setpoint determinations O
m G
APPROVED CY-dM II/(d6 RAn; Cnmn.,Date 4
SON ODCM changes 10/15/86 RARC mtg Description o4 chance Page 19, Section 2.2.1, the reference to equation 2.2 is changed to equation 2.3.
Analysi s or Eval u ati on Justf 4 vino the Chance This changes the ref erence to the equation which is actually used by plant personnel to determine the sum of the ratios.
Determination of the Effect of the Chance on the Accuraev er Reliability of the Dose Calculations or Setooint Det ermi n a t i on s .
This change will have no effect on the accuracy or reliability of the dose calculations or setpoints.
5 i
f
-m
APPROVED DY-t s -
& n/c/n RARO Cnmnmate SON ODCM changes 10/15/86 RARC mtg Descriotion of chance A term was added to equation 2.4 to include the monitor background reading in the calculation.
Anal ysi s or Eval uat i on Justifvino the Chance This change is not a change in the methodology used, but is a reflection of the actual equations used by the plant personnel in their calculations.
Det ermi nat i on of the Effect of the Chance on the Accuracy or Reliability of the Dose Calculations or Setootnt Det ermi nati ons.
- This change will have no effect on the accuracy or reliability of the dose calculations or setpoint determinations.
t 5
9 I
o"
APM LVED BP 1 A b II/Cf96 f(Ai<G Cnmn./03te SON ODCM changes 10/15/86 RARC mtg Descri oti on of chance j The liver will be added to the organs considered for the calculation of the water ingestion dose. This change is reflected on pages 21 and 22.
Anal ysi s or Eval uation Justif vino the Chance s,
p This change will make the organs considered for water ingestion the same as those considered for fish ingestion. This change makes the monthly methodology more consistent with the quarterly methodology.
Determi nati on of the Effect of the Chance on the Accuraev er Rel i abi l i t y of the Dese Calculations or Setooint Determinations
, This change will cause the dose calculations to be more accurate,
, since the total maximum organ dose will be based on contributions, l , to each organ from both water and fish ingestion. This change will have no effect on the accuracy or reliability of setpoint determinations.
s
. . , 9 PROVED BY-b)^^# 11/ClSh SON ODCM changes ~
10/15/86 RARC mtg Descri pti on of chance P-32 is to be deleted from the isotopes considered in the monthly dose calculation methodology. This change is reflected on pages 21, 22, and 23.
Analysis or Eval uat i on Justifyino the Chance A recent change to the Technical Gpecifications deleted the requirement that the' plant report the amount of P 32 released in the liquid ef fluents.
Determi nati on of the Effect of the Chance on the Accuracy or Rel i abi l i t y of the Dose Calculations or Setooint Det ermi n at i ons This change. w'ill -have no eff ect on the accuracy or reliability oV ~
l the dose calculations or setpoint determinations.
i O
e 6
APPROVED BY-
~
IIlClgf r(ARC Chmn/Jatt
. SON ODCM changes 10/15/86 RARC mtg
~
Descri pti on of chance Page 21, Section 2.3.2, third paragraph, second sentence changed to read: "First, the monthly release data will be obtained and the activities released of each of the above 20 radionuclides, if identified, will be used for the dose calculation.
Anal ysi s or Evaluation Justifyino the Chance j This is a clarification of the wording to indicate that these }
isotopes are not required to be reported, but that they are available f or use in the dose calculations if an activity is reported. -
Det ermi nati on of tne Effect of the Chance on the Accuracy or Reliability of the Dose Calculations or Setooint Det ermi nati ons This change will have no effect on the accuracy or reliability of the dose calculations or setpoint determinations.
e i
e D
,,PPROVED (3Y-
- If/y"/f6 RARC CnmnJ3 ate SON ODCM changes ~
10/15/86 RARC mtg Descri pti on of chance Section 4.0 needs to be added describing the method of assuring that 40 CFR 190 do's limits are met. This section shall read as follows:
4.0 Annual Maximum Individual Doses - Total To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, ,
summing the quarterly total body air submersion dose, the -
quarterly critical organ dose from gaseous effluents, the quarterly total body dose f rom li quid ef fluents, the quarterly critical organ dose f rom li quid ef fluents, and the direct radiation contribution for the quarter as measur'ed by the environmental monitoring program, and then taking the sum for each quarter and summing over the four quarters.
Analvsis or Eval uati on Justi* vino the Chance The addition of this section will document in the ODCM how the total doses are obtained for this 40 CFR 190 evaluation. It will make the sections of the ODCM more consistent with the RETS requirements.
Determination of the E4fect of the Chance on the Accuraev or Rel i abi l i ty of the Dose Calculations or Setooint Det ermi n ati ons This change will have no effect on the accuracy or reliability of the dose calculations or the setpoint determinations.
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IDENTIFIER SONAPS-7-oo 9 einsNo. ~B45 '8612 3 0 552 ISSUE aATE , u ,,/ u TITLE SnUV BVnhoADD 0 AdflWe$Ye bn En+mlIbW
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REVISICN LEVEL O cre?cTED SvsTEPr93 PLANT FEATURE:
SYSTEM,'COMPCNENT DESC?.IPTICN: .
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~E NON-SAFETY SYSTEM SYSTEM NO.
APPENDIX R -
O CIuIt STauCTuaES INSTRUMENTATION C1.S7,PAM,ETC)
O LICENSINs -
O oTxEn F' A'ct Etc99?rTecT'ckt C ESSENTIAL
[ FILE CMLY
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CALCULATION CLASSIFICATION ,
.IDENT!FIER: S&NA#f 7W PRELIMI'ARYN CLASSIFICATION: *
[] ESSENTIAL C FILE CtlLY E DESIRABLE C
SUPERCEDED ,
CALCULATIOll CLASSIFICATION JUSTIFICATION:
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REVIEUER: AGREE WITH
].aCLASSIFICATION ] _ DISAGREE -COnnE.';TS RECUIREO D .
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e es u op,e APPROUER: l AGREE WITH CLASSIF: CATION ] . DISAGREE -CC'*F.Z::TS RECU; RED i
- e
TVA 10697 (DNE-OA-6-86) DNE CALClJLATIONS
.',lTitlj.l Safety Evaluation of Radwaste Demineralizers l Plant / Unit l SON /l&2\
lPreparingOrganization l KEY NOUNS (Consult RIMS Descriptors List)
\ ,
l DNE/ NEB l Safety Evaluation, Liquid Waste Systems \
l Branch /Projectidentifiers lEach time these calculations are issued, preparers must ensure that the s i l- l original (RO) RIMS accession nur:ber is filled in. \
l l SQNAPS-7-009 lRev (for RIMS' use) RIMS ACCESSION \ MUMBER I
l lRol l B45 '8612 % 5 5 2 l lApplicableDesignDocument(s) l l l \
l l lR l l \ !
l E I l l l lR l \ l I
lSARSection(s) l UNID System (s) l
\ l.
l l 11.2 l - 77 lR l l
[
\ l' l Revision 0 l RI R2
\ l-l l R3 lSafetv-related? Yes ( )
- No (x) \ l lECN No. (or Indicate Not Applicable)l l l l Statement of Problem .
l 5911
[ Prepared -
l l
I l
l l
l l The use of a nubile demineralizcr system \
\ll l /E f e W b ritu/4 I I l l in place of the deficient radwaste l_
lChec .
l l l l evaporators is,a major cha'nge to System 77. l l 4 dd.e // 12/29/% '
l l l l This change is evaluated as required by l l Reviewed l l l Tech Spec 6.15.1 to verify that no l .d.f.. ish q/W I J l
l l unreviewed safety question exists. -
l l
!^a7hEMd e i ! l l l 1 -30 (:2 M l l l l lUSE FORM l List all pages added l l l
l l lTVA10534lbythisrevision i I I l
l l llfMORE l List all pages deleted l l l l lbythisrevision l l SPACE i l I l l l REQUIRED lListallpageschanged l l l l l lby this revision l l l l
l l
l ABSTRACT [These calculations contain an unverified assumption (s) that must be verified later. Ye s ( )
l No (x)) l l
l A safety evaluation was performed to evaluate the safety of utiliring nobile demineralizers for routine processing l l cf liquid radwaste from the floor drain collector tank (FDCT), tritiated drain collector tank (TDCT), and CVCS lholouptank. l l l l
l The evaluation concludes that the mobile demineralizers can be safely operated indefinitely on radwaste liquids l l cf the quantity and activity generated at SQN. Releases of radioactive materials, offsite doses, and l
l occupational exposure were found to not be significantly affected by the change. There is no increase in the l
l probability of an accident or possibility of a new accident from those evaluated in the Safety Evaluation Report l l c*ntingent on the piping scoped in ECN-L5911 being installed to replace the hoses now in use.
l l l 1 l 1 l -
l l I I l l l l I l_ l l ( ) Microfilm and store calculations in RIMS Service Center 1 Microfilm and destroy. () l l N Microfilm and return calculations to: D e l- . M E d M k Address: W IO C,llt 3 (,,- K
~
cc: RIMS, SL 26 C-X l DNEl - 29380 NE8 12/18/86
_ . - ._ _ - - _ - - - .. _ _ _ . - _ ._ - ~ ,
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~ Prepared by A(.dd, ms#4
. Reviewed by //NI;/ #2/t?[86 -
SAFETY EVALUATION OF RADVASTE DEMINERALIZERS SQNAPS-7-009 Introduction Technical specification 6.15.1 lists seven information requirements that must be fulfilled to support a major change to a radioactive waste processing system. Use of mobile demineralizers in lieu of the original radweste evaporators for processing liquid radwaste constitutes a change requiring this evaluation. Each of the seven information requirements and responses are .. , ,
presented in subsections of the document. .
s I _ _ . . . . . . . . . .
l j
i
- 1 DNE1 - 29'39Q NEB 12/18/86 i
5 Preparedby11,//e%/f. n.iz e/gt Reviewedby((MN[(4/ 29/G4-SAFETY EVALUATION OF RADWASTE DEMINERALIZERS SQNAPS-7-009 .
Technical Specification 6.15.1 Question 1
- 1. Provide a summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59.
Response to Question 1 No evaluation was performed in support of the original installation of the mobile demineralizeer in 1981. Subsequently, in 1983 a formal Unreviewed Safety Question Determination (USQD) was performed and revised in 1985 in support of Design Change Request 1513. This change was to provide permanent piping to replace the hoses needed to operate the deminera-lizers. The piping design was completed under ECN-L5911. Based on the USQD's findings that there was no unreviewed safety question (see Appendlic B),'it was determined that the piping change could be made in accordance with 10CFR50.59. However, the piping under ECN-L5911 has not been implemented in the field. Continued use of the hoses in the long term may result in failures that spread contamination. Therefore, the piping under ECN L5911 should be installed to replace the hoses.
Technical Specification 6.15.1 Question 2
- 2. Provide sufficient detailed information to totally support the reason f.or the change without benefit of additional or supplemental information.
, Response to Question 2 The .nstalled liquid radwaste processing system at Sequoyah Nuclear Plant (SQNp) consisted of a 15-gal / min rated auxiliary waste evaporator and a 2-gal / min rated waste evaporator. These evaporators have been tested and were found to have serious functional deficiencies. Testing has shown that the evaporators cannot produce acceptable quality distillate when operated at greater than 70 percent of their design flow rates. The reduced operating capacity is inadequate to process the high rate of liquid waste (up to 25.8 gal / min average over a month) that is beir.g generated from 2 units at SQN. Since the evaporators are not capable of processlog the liquid waste being generated, they have been replaced by temporary portable demineralizers.
An engineering study (reference 3) was performed to determine the scope of system modification that would be required to, upgrade the evaporators to an acceptable level of performance and reliability. The results obtained from the study are as follows:
- 1. Replace Crane Chempump concentrate pumps with centrifugal pumps which have or can accept the Allis-Chalmers dynamics seal (e.g., Allis-2 DNEl - 2939Q NEB 12/18/86
5
.' , Prepared by la dw/e n/2ekt Reviewedby/CCLWb///12h&6
/ /
SAFETY EVALUATION OF RADWASTE DEMINERALIZERS SQNAPS-7-009
-Chalmers pumps). The dynamic seal appears to be the best seal currently on the market for concentrated boric acid applications.
- 2. Replace both level sensing systems with a glycerin-charged capillary pressure sensing unit utilizing a bellows seal to prevent the freezing of level control tubing (i.e.. Taylor model Nos. 381T or 382TQ, or equivalent). Also, provide flushing capability for the level sensing connections.
3 Install a spool piece and leak detection device and alarm on the evaporator condenser rupture disc flange (i.e., Fluid Components, Incorporated, flow monitor). The alarm should signal on the local . '
control panel and reflash to the control room whenever a leak or rupture of the disc occurs. The device would close the evaporator steam supply valve and the isolation valve in the vent condenser vent
, pipe to plant vent.(see modification item 20). The spool piece will*
provide means for quick replacement of the rupture disc.
- 4. Relocate all pumps (i.e., two concentrate pumps and two distillate
- pumps) off the evaporator skid to a location in the evaporator room -
where maintenance is allowed.
- 5. Install a sight glass across the vent condenser and a high-level alarm to allow.the operator to tell when the vent condenser is
_ flooded. Also, relocate.the vent condenser to a higher elevation in the evaporator room to reduce the flooding problem. The alarm will be at the local panel with reflash to the control room.
- 6. Install a~ check valve on the eductor line between the eductor and ' '
steam trap and a differential pressure-operated solenoid shutoff valve to prevent backflow into the vent condenser.
- 7. Install a moisture trap on the vent line to the plant ventilation system. (This trap must not significantly increase pressure drop of the vent line.)
- 8. Install density meter instrumentation (e.g., Dynatrol) to indicate near end-point concentrations of evaporator bottoms.
1
- 9. Convert the present sampling system to a continuous flow sample system for feed, concentrates, and distillate with minimum piping
) lengths and flushing connections.
i 10. Relocate existing pressure gauges, feed and distillate flow meters from inside the evaporator cubicle to the local control panel outside the cubicle.
- 11. Add a bypass around reflux line orifice with a remote-controlled flow control valve and flow measurement capability with flow readout at the control panel for the reflux line.
- 12. Install fleximesh or other liquid de-entrainment device in the evaporator vapor outlet.
- 13. Install a sight glass across upper and lower flush'line connections to permit a check of level instruments.
- 14. Modify controls to control level at 50-55 percent instead of 60 percent.
3 DNEl - 2939Q NEB 12/18/86 i
. Frepared by M twh 11129lC Reviewed by [68/c b f[ I?/Lf/86
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SAFETY EVALUATION OF .
RADWASTE DEMINERALIZERS SQNAPS-7-009
- 15. Install a 1" drain line to the waste disposal system with a drain valve and check valve on the vent condenser eductor line to allow the draining of the vent condenser if flooding has occurred. Note: This drain is to be considered as a possible permanent drain during evaporator operation.
- 16. Replace seat of vent condenser steam trap with a new seat manu-factured of stainless steel.
- 17. Install a check valve on the distillate recycle line just prior to I
its tie-in to the feed line.
- 18. Remove and relocate / replace vent condenser drain eductor from the -
concer.trates recirculation line to the evaporator feed line.
- 19. Reroute the evaporator condenser rupture dise discharge piping to the floor drain collector tank vent. This will let the large amount of moisture associated.with these ruptures return to the floor drain
' collector tank.
- 20. Install a differential pressure instrument in the evaporator vent piping to the waste gas system. This instrument is to close the vent -
isolation valve automatically when the evaporator venting pressure is below the waste gas header pressure and when a rupture disc is blown. The modification together with item 21 will prevent inadver-tent contamination of the evaporator room due to a loss of pressure in the evaporator.
- 21. Install a vapor pump in the vent condenser vent piping to the plant vent. Thh pump is to interlock with the evaporator steam valve, .
rupture dise flow detector, and vent solenoid isolation valve (see modification items 3 and 20). This pump will operate when started from the control panel and will stop for a ruptured disc or closed vent solenoid isolation valve. This pump is to aid the venting of the evaporator while permitting lower steaming rates and thus reduce carryover problems. (size for 30 lb/h air and noncondensibles, mostly air.)
The estimated cost to implement these modifications was $600,000 in 1981 value dollars.
Based on the extensive scope and cost of the 21 modifications'to correct equipment design, and the need for more process capacity above the evaporators design capacity, TVA decided to use moblie demineralizers.
Technical Specification 6.15.1 Ouestion 3
- 3. Provide a detailed description of the equipmerit, components, and processes involved; and the interfaces with other plant systems. '
4 DNE1 - 29'39Q NEB 12/18/86
' ~
prepared by JE. N'2.edt 12 / 2A%.'
. Reviewed by [(#bf/ /2/19/36 SAFETY EVAI.UATION OF RADWASTE DEMINERALIZERS SQNApS-7-009
' Response to Question 3
- a. Equipment and Components The contracted system for 1986/1987 is the fluidized transfer demineralization system (FTDS) as provided by Chem-Nuclear Systems, Inc. (CNSI). The basic system equipment and components are described below. Contracts are renewed every two years for processing services. Even though the contractor and equipment could change, th.e mobile domineralizer systems of the pressurizer type are considered -
similar and would not require a new safety evaluation.
Demineralizer control Unit:
'The domineralizer control unit acts as the interface between the CNSI equipment and Seguoyah's in-plant equipment. The demineralizer control unit includes the influent and effluent distribution piping, isolation and throttling valves, and temperature, flow, and pressure indicators. In addition, in-line instrumentation for the continuous monitoring of pH and conductivity are provided in the control unit.
The control unit flow diagram on Figures 1 and 2 illustrates the instrumentation and valving arrangement.
The design- and fabrication of the demineralizer system piping meets the requirements of NRC Regulatory Guide 1.143 and ANSI B31.1. Butt welds and fully ported valves are employed where possible to reduce the possibility of crud traps. All welding is completed by certified Section IX welders.
All systems are hydrotested to 225 psig for an affective operating pressure of 150 psig. At maximum flow rates, observed pressure drop across control units is tormally less than 40 psig. The overall dimensions are approximately 88" x 42" x 30" (LxHxW) and the unit weighs approximately 1,500 pounds (dry).
Rosin Transfer Unit:
The resin transfer unit includes two manifolds; one for new resin transfers and one for spent resin transfers. The manifolds are designed with 450 angles where possible to reduce the potential of plugging the lines when resins are being, transferred. In addition, pipe bends are employed where possible to reduce the potential for crud traps at weld seams. Spent resin transfers ca'n be accomplished with gas (nitrogen or air), service water, or filtered waste water.
The design and fabrication of the resin transfer unit meets the requirements of Nuclear Regulatory Guide 1.143 and ANSI 31.1. All 5 DNE1 - 29'39Q NED 12/18/86 l
?
- ~
Prepared by _8/ MJ aju/g-Reviewedby! /1/sp/g4
/
SAFETY EVALUATION OF RADWASTE DEMINERALIZERS SQNAPS-7-009 piping is hydrotested to,225 psis. Overall dimensions are approxi-mately 88" x 42" x 30" and the manifolds wel5h approximately 750 pounds (dry).
Pumpst Warren Rupp Sandpiper 1-1/2" Pumps with 1-1/2" FNPT connections,1/2" FNPT air inlet.
l Sample Sinks:
I
! A sample sink is provided with each system. The capability to sample the influent and effluent of each vessel is provided. The sample sink is fitted with pressure gauges to measure differential pressure'
- across major components of the system.
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. Reviewedby[ hM, /2/27/J4 SAFETY EVALUATION OF RADWASTE DEMINERALIZERS SQNAPS-7-009 Pre-Filter Vessel:
The filter vessel contains six (6) 30-inch long (or equivalent) filter cartridges with a replaceable cage assembly. The filter cartridges are available in various micron ratings which provide flexibility when filtering requirements vary.
The filter vessels are stainless steel and designed and fabricated to ASME Section VIII Standards for operating pressures up to 300 psig and are hydrostatically tested to 450 psig. .
A schematic of the filter vessel is shown on Figure 3.
Domineralizer vessels:
24-Inch Diamotor Pressure Vessels Each pressure vessel can be used as a mechanical cartridge filter, activated carbon charcoal filter, cation demineralizer, anion demineralizer, mixed bed domineralizer, or polishing filter /
domineralizer. The vessels are designed to ASHE Section VIII Standards for operating pressures up to 150 psig and are hydrotested to 225 psis. Normally, four vessels are used in series.
Fiborglass High Integrity Container Pressure Vessel Each fiberglass reinforced plastic (FRP) vessel can be used as activated carbon charcoal filter, cation domineralizer, mixed bed domineralizer, or polishing filter. The vessels are designed to the intent of ASME Section VIII Standards for operating pressures up to 100 psig and are hydrotested to 150 psig. Normally, four vessels are used in series.
Dominera112er System Design and Construction Spee!'ications:
- Compliance with NRC Regulatory Guide 1.143 - Revision 1 dated 1979
- Compliance with ANSI 15.2 1 - Compliance with ANSI B31.1
- Compliance with ASME Joller and Pressure Vessel Code Section VIII and IX
- Compliance with NEC and NEMA standards
- Operating pressures: 0-150 psig 9 DNE1 - 2939Q NED 12/18/86
l? ,*
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i Prepared by $ 8. wew[a, r
,. Reviewed by dit h /M2.3 4
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, SAFETY EVALUATION OF
!' RADWASTE DEMINERALIZERS SQNAPS-7-009 1
! - - Operating temperatures: 50-1350F (limited by media l selection)
Waste handling components hydrotested to 225 psig l -
Waste hoses are reinforced noncollapsible butyl rubber. ,
Special line hoses are available for chemical compatibility with decontamination solution wastes. -
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DNE1 - 2639Q NE8 12/18/86
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- Pr:p: red by 8 6 der 4 ta./2 Wp/
Reviewed by [ M b )f 12 47 g(,, .
SAFETY EVALUATION OF RADWASTE DEMINERALI2ERS SQNAPS-7-009 1
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11 DNE1 - 2939Q NEB 12/18/86
4
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Prepared by .91,Ya.d idag/g4 ;
Reviewedby[/ dsM />d9 34 i <
! SAFETY EVALUATION OF , ,
RADWASTE DEMINERALIZERS SQNAPS-7-009 i b... Interface Plant Eautoment Reautrements:
Process Area L l,
- Minimum Area of 300 sq. ft. Located in SQN truck bay. '
Waste Inlet Pining:
- Pressure: 150 psis maximum !
- Flow Rate Nominally 30 spm from Floor Drain Collector Tank '
i
- Temperature: 70-1400F '
l
- Codes: ANSI 831.1 !
( Treated Discharte: - -
- Pressure: 100 psig
- Flow Rate Nominally 30 sps to Cask Decon Tank
- Service Air .
- Pressure: 80 +20 psig l
- Flow Rate: 40 SCFM Minimum ,
- Quality: Domineralized. 10 umhos
- Pressure 80 120 psig :
- Flow Rate 10-30 spa l Electrical Powert
-110 Volt. 20 amps
-440 Volt. 30 amps Waste Processint Flow is routed from the trittated and nontrittated tanks to the mobile i domineralizer system by use of the floor drain collector tank and tritiated drain collector tank pumps. Processed water from the mobile dominera11 er system can be routed to either the monitor tant or the cask decontamination tank. The mobile domineralizer system removes the water's .
impurities via lon exchange and filtration. When the resin and filter media are expended, the media are dowatered within the domineralizer l
12
- DNE1 - 2'939Q NE8 12/18/86 l i i
prepared by AC Mub r2/n/r.f Reviewed by [( M b /2 6 /
SAFETY EVALUATION OF /
RADWASTE DEMINERALIZERS SQNAPS-7-009
" vessel using a portable pump. Dewatering is required for the plant to meet the disposal site criteria for spent resins. Operating procedures for interfacing plant equipment are provided in instructions SOI-77.lD-B, SOI-77.lB4, and SOI-77.1A8 (attached).
riant Modifications Two temporary alterations have been used to provide the physical flow paths required to operate the domineralizer system. Temporary alteration control form (TACF) No. 82-328-77 provides for installation of a 2-inch '
hose from the tritiated drain collector tank discharge pumps to an isolated primary water header on elevation 669' and from the primary water header to the domineralizers. TACF No. 81-328-77 provides for removal of the internals of check valve 77-572 to allow pumping from the cask decontamination tank to the CVCS monitor tank which provides the final release point of water processed by the mobile domineralizer system.
ECN-L5911 covered the design of permanent plant piping to support mobile demineralizer operations; however, none of the work has been implemented in the field.
Technical Seneffication 6.15.1 Question a
- 4. Provide an evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto.
Response to Question a Based on statements in calculation No. SQNSSG4-001 R1, it was determined that 11guld from the floor drain collector tank (FDCT), the tritiated dealn collector tank (TDCT), and the CVCS holdup tanks (CVCSHT) would be processed through either the condensate domineralizer waste evaporators (CDWE) or the mobile domineralizers (HD) currently located in the railroad access bay. This was to be in lieu of processing these wastes through the deficient waste evaporator and auxiliary waste evaporator packages.
Expected annual releases were calculated in calculation No. SQNAPS3-034 RO for the MD. A comparison of these releases to the 11guld releases in the current revision of Table 11.2.6-2 of the SQN FSAR can be found in Table 1 herein. It should be noted here that the values in the FSAR reflect the processing of the FDCT and TDCT only. Removing the contribution of the CVCSHT from the calculated releases for the HD result in the values found in Table 2 herein. The remaining differences in Table 2 can be explained in difference's in the bases of the appropriate calculations. For example, the amount of 11guld radwaste processed in the calculation of the FSAR numbers were based on design assumptions on the operation of the liquid 13 DNE1 - 2939Q NEB 12/18/86
Pr:p:r:d by Bf[WM es./2f/f4
,, Revfowedby[ h/2/29 /54
/ !
SAFETY EVALUATION OF RADWASTE DEMINERALIZERS SQNAPS-7-009
..radwaste system while the newer releases are based on actual amounts of liquid radwaste processed at Sequoyah Nuclear Plant.
There are no gaseous releases givet. in the FSAR for the processing of 11guld radwaste, and the sources of gaseous radwaste given in chapter 11.3 of the FSAR do not consider the 11(tid radwaste system to be a source of activity for processing by the waste rat system (WGS). Calculation No.
SQNAPS3-034 R0 gives the amount of gas released of 148 C1/yr for the MD.
Table 11.3.6-4 of the SQN FSAR gives the total release from the WGS of 9.750 C1/yr. Therefore, the amount of gas released from processing the .
liquid radweste will not significantly increase the total amount of radioactive noble gases released.
Table 1 '
Predicted Releases from Processing Liquid Radwaste Annual Release (C1/ve)
FSAR RD Liquid 0.26 29.0 la s -- 0.0 148 Table 2 Predicted Releases from Processing Liguld Radwaste From the FDCT and TDCT Annust Release (ci/vr) '
FSAR ED Liquid 0.26 6.52 Gas 0.0 7.84 Technlent Specification 6,15.1 Question 5 '
- 5. Provide an evaluation of the change which shows the expected maximum ,
exposures to individuals in the unrestricted area and to the general population that differ from thoso previously predicted in the license appilcation and amendments thereto.
14 DNZ1 - 2'939Q NE8 12/18/86
Prepared by he h A d n rsitq/td Reviewed by /44hhk/// / 2/L3/34 -
t i SAFETY EVALUATION OF .
RADWASTE DEMINERALIZERS SQNAPS-7-009
' Response to Qu'estion S An isotopic breakdown of the releases calculated in calculation Nos.
SQNAPS3-033 R0 and SQNAPS3-034 RO were transmitted to the Radiclogical Control Branch where exposures to the general population were determined.
A comparison of these exposures to those from Table 11.2.9-2 of the SQN FSAR can be found in Table 3. As can be seen, the new exposures are considerably higher than those reported previously. However, the FSAR exposures do not include the processing of the CVCSHT while the new exposures do. ,
While no exposures were calculated by the Radiological Control Branch for releases from just the FDCT and TDCT, it might be possible to estimate the exposures based on a comparison of the releases from the FDCT and TDCT to-l the total releases. From Table 1. the total MD liquid release to the
! environment is 29 C1/yr and from Table 2 the corresponding value is 6.52 l C1/yr. Assuming a linear relationship between total activity released to '
! the environment and dose, the doses for the MD can be reduced by a factor by 4.45. The estimated doses can be found in Table 4.
Table 3 Predicted Population Doses from Processing Liquid Radweste Annual Dose (mrem /yr)
FSAR HD Bone 0.35 4.10 GI 0.17 1.07 Thyroid 0.34 7.80 Liver 0.38 7.30
Skin ---- 5.80 Body 0.33 5.80
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15 DnEl - 2939Q NEB 12/18/86
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Prepared by 3AYAs[s* A/u/g/
, Reviewedby[ bM[rZ/19[$
I i /
SAFETY EVALUATION OF RADVASTE DEMINERALIZERS SQNAPS-7-009 Table 4 Predicted Releases from Processing Only the FDCT and TDCT Annual Dose (mrem /yr)
FSAR MD Bone 0.35 0.92 GI 0.17 0.24 Thyroid 0.34 1.75 Liver 0.38 1.64 .
Skin ----
1.30 Body 0.33 1.30 Technical Speelfication 6.15.1 Question 6
- 6. Provide a comparison of the predicted releases of radioactive materials.
In 11guld and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made.
Response to Ottestion 6 Offsite shipments of solid radwaste from Sequoyah Nuclear Plant for the period 10/3/84 through 10/1/85 were provided by Lenon J. Riles III of the Risk Protection Branch in a database file. In the time period examined, there was a total of 4.583 Ci of solid radwaste shipped offsite. Of these, 4,290 Cl were resins and 127 Cl were evaporator bottoms. The remaining 166 C1 consisted of trash, solidified oil, etc.
Calculation No. SQNAPS3-033 RO calculates the amount of solid radwaste generated as 2,950 C1 in evaporator bottoms, and calculation No.
SQNAPS3-034 R0 calculates the amount of solid radwaste sonorated as 2.890 Cl in resins. In the period examined, the HD would have boon used to process any liquid radwaste. Therefore, using the CDWE to process liquid radweste would increase the amount of evaporator bottoms to 3.077 C1 whilo reducing the amount of resins to 1.400 Cl. The total amount of nolid radwaste produced would increase to 4.643 C1.
The predicted 11guld and gaseous offluents we're discussed previously.
Based on semi-annual reports, the amount of 11guld and gaseous effluents roloased annually while using the old wasto evaporator systems were 10.6 C1 and 11,000 Cl respectively. The reported gaseous offluents are mainly l from the WGO. The 314 Cl/yr from the CDWE or 148 Cl/yr from the HD will not significantly increase the gaseous offluents. The liquid offluents l
will increase from 10.6 Cl/yr to 22.4 C1/yr for the CDWE or 29.0 C1/yr for
! 16 ^
' DNE1 - 2939Q NED 12/18/86 1
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Pr: par:d by AR[.e M4 #Llu/u Reviewed by 8/'Athh /2/L9 &
SAFETY EVALUATION OF RADWASTE DEMINERALIZERS SQNAPS-7-009
-the MD. There are several potential reasons for this, the most probable one being that only one unit was in operation at the time the waste evaporators were in use.
Technical Speelfication 6.15.1 Ouestion 7
- 7. Provide an estimate of the exposure to plant operating personnel as a result of the change.
Response to Question 7 '
The MD system was installed when it was discovered that the waste evaporator and aux 111ery wasto evaporator were deficient. The system is '
contracted for on.an as-needed basis and is remotely oporated. The MD -
resin beds are shicided and access to the entire MD system is administratively controlled as a contaminated zone and a radiation area (roped off at 2.5 mrem /h). The sole operation requiring operators to -
enter the MD package is the preparation of Lho domineralizer vessels for shipment offsite. Piping from the waste tanks to the HD was evaluated.
It was determined that the piping would not alter where access to the area around the transfer pipe waad have to be controlled while processing waste. - Therefore, there should be no significant increase in exposure to plant personnel as a result of operation of the MD. Ilowever, there is some exposure associated with the MD when preparing the domineralizer vessels for offsite shipment. This exposure is on the order of 2.5 man-rom and is eliminated with use of the CDWE to process liquid radweste.
4 s
4 4
17 onti 29390 NEB 12/18/86
Prepared by Sr. EJds /1/M/ft' Reviewedby[ r //!JJ[pg, i I SAFETY EVALUATION OF RADWASTE DENINERALIZERS SQNAPS-7-009 l
References l 1. Design Change Request 1513 (L35 820830 902).
- 2. ECN-L5911 (PWP 831109 511). '
l 3. Design Study 1106 (SQP 830208 013). '
- 4. USQD (825 851101 510). ,
- 5. TACF 81-328-77. ,
l 6. TACF 82-328-77. .
- 7. Letter from TVA to NRC dated 7/15/86 (L44 860715 805),
l 8. Calculation SQNSSG4-001 R1,
- 9. Calculation SQNAPS3-034 RO.
- 10. Calculation SQNAPS3-033 RO.
- 11. Memo from H. L. Abercromble to D. W. Wilson dated 7/11/86 (553 860630 800),
f a
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18 DNt1 2930Q l NE8 12/18/86 l l
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Prepared by A.F //w-Me st#.9/f4
.- Reviewedby! l M M!g6
/ /
SAFETY EVALUATION OF .
RADWASTE DEMINERALIZERS SQNAPS-7-009
- i
' APPENDIX A ,
, NRC Consultment Dated October 1,1986 ,,
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Pecpir:d by J.e' I M . M 4pt.p.9/tf Rovi tdby[/
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SAFETY EVAltl.iTION OF
/ /
RADWASTE DEttih.TRALI2r.9s SQNAPC-7-009 Commitment By October 1,1986, the Design Control t'rocess proceduros will bs issued /
revised to ensure that.the requirements of TS 6.15 are met for .1y future
" major changes" to the radwaste systems.'
Compilance , o On August 25, 1986, a revision was isstied to Sequoy h Engineering Proceduct SQEP-13 which Added the following notes 4 "For design changes to gaseous. 11guld, or solid radwaste systems- . mn evaluation nust be perforn.et in accordance with Technical Specificat.lon '
6.15."
O N
6 4
20 DNet - 2939Q NED 12/18/86 n n . .-
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M /2/2.fdC(
Pr:p;r:d by 3 #
..- C' Reviewed by l.
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/
SAFETi! CVAll'ATION OF RADWASTE DFJtINERALIZERS SQNAPS-7-009
.q , ,
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APPENDIX B .
USQD ..
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T 21 '
) DNE1 - 2939Q NEB 12/18/86
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UNREVIEWED SAFETY QUESTION DETERMINATION TVA 10S$1 (EN DES 241) A TO: eAnunork h!,,-fenP pf a f%fm TN 851106 B 0137 (37"ll LM a d1 FROM: F16 SNP uEoS ACCESSION NO T
k PREPARED R EVIEWED APPROVED J ,0 g g c-
.t &A%. L sd2:. 9&r %c, #
> B25 ,85 1101 510 1 A ff'ff$% h. 89 ft hy g h 2 2 R
3 3
4 R 4
5 R
- R0amlNITI Al. lSSUE -
rRcuECT 604 arrECTEo unit (S) o USQ? YES NO V -
ECN M ECN DATE *llit] h M YES /NO SWEET NO.
MR NO. ID DATE- 138,IE SPECIAL REQUIREMENT (S) NO -
OTHER DATE POTENTI AL TECH SPEC CHANGE NO
REFERENCES:
o 'a n* LMO 4 '
ad N D'
DESCRIPTION OF CHANGE ^ 8 D t*5 ^^ bei ne
_ia EN S A2htfL Ph S d A tuka
- f AA c'A* % t3 d Ad 3 ~A A ek.4, M. A . u n m L ' c1.. d .__. m k 0 A d w h b 9,..La L,.- - 6 . mbuo .,1,o.A O b- um l d .
- a pw.mu d e.m,a t , ha .
q_A i4 Q an,p g tf*M h , g,, _
a hy l 5 # A _ . E_ L L m .t -eh .. .m M h eJft. CAR. !
kb OSOD ei am
- WA h 64 - #
S*
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n +,mi t - A ~~s w h M M W me&L L.~e.- .
k.1 4 m . & u s ctd o m _ ~ 2 w a .. 6 L . u a _ d i L J .~ 1 c h b '
m._L. ea.~-~& -62. n &M a A JC one n .
- LA, ks \;IL all d.s. .% nd . oM u. 0, k.J.Q s aL,&,ALL &&. L Ms2
- n A.:.ob JR;, L mb k ht&L , rah A C 4 %tAA _
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1 4 / 6 CC (ATTACHWENT91s peO . YE3 CHIEF NUCLEA R ENQiNgtm,wlDC124 C4 CHitF. ARCMtT,ECTUR AL DESIGN em AMCH.weCIM C.M Chit P. N CCMANICAL EN OCS 3N ANCM. IC2SPT.M ~
CMtEP.CivlL E eOINEtatNa SR ANCM.wtOtto C.M CMIEP. QU ALITY A$ tun ANCE an ANCM.witC224 C-M CMtEP. Crvtb EM DES en AMCM. w3C126 C-M M ANAQCR OF CONstauCTION. 2782a C4 CMIEF. ELSCTRICAL EMelMERRime S A AMcH.wSCIM C M CM't#. COST P'.? NNING AND CONT A CL ST A PP. W12C Fa C M CMIEP. ELECT A DCAL EN OCS BR ANCM wfCt24 C M Pt ANT Sypg gtNygNQgNy CMtEP.WSCMAM c LE iMsg AINe saANCM.wl00228 C M OIR ECTO R. MUCLE A a powt m CIvtSION. 716 t o-C WEOS. 84027 C4
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. . sn.., .,
UNREVIEWED SAFETY QUESTION OETERMINAI40N s
t.SiII a. /1 Project ON notNrireEn Umrrveewoo Safety QuettIOn!
- 1. Is the procapility of occurrence or the consequences of an accecent or
- malfunction of equipment smoortant to safety previously evaluateo en tne Sa f.tv Anaiym Report increas.o r . . . . . . . . . . . . . . . . . . . . . . . . . . . vei No %
.rustifiution:
. h se.4 id.tt d 1.u.h. m .J t.1 am M.a.L ndaled ALL NL.l,.. k-
,.. A l a 1. n,,.:.h w w % .tM.L M e,.
A.,
L.,_0;,l1 ei hd - ,,h',b'd.1 w C L _D_
.9 L L a x. L L. a-a -.h e e u..% Li ,sw.: u o o J f,
.00A 1 _
Ae a _,-L e. co m tm iesa. A h C D. i m !.l*,S % \
3 aNU 7 ,d h .%, .
Ne s no A u S ,d, J . A deh c %.SA9 Jd M be eoidD 6, el1 6 . "
su a 4 f
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I
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- 2. Is the possibility for an accident or malfunction of a different type than any evaluated provsously in the Safety Analysis Report createor . . . . . . . . . . . . . . . Yes No N
.sustifiation, A .a .b s tidAba_eu M h. b (L.L u e = La n. A as J. .h h ' L M w AL2 Jo i' m....eh k 0 8 n aAL m n
. ',11LA e k dJ
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! b I
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I g 3. is the marva of safety as defined in the masis for any tecnnical se cification
- reouceor............................. ........ . . . . . . . . . . Yes No ,,) ,,,
MO . 40 A.h r_ A c0hAstA%
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.'. . a TVA 10551 A (EN CES740) gn,,, .,
e UNREviEWED SAFETY QUESTtON OETE AutN AT LON LS9II n- /$
ICENDFIER Unreviewoo safety Ovestion:
- 1. 45 the prod &Delity of occurrence of the consequences of an accident or malfunction of equipment important to safety previously evaluated in in. sa f.tv Anaiyies R e port inuea sea r . . . . . . . . . . . . . . . . . . . . . . vei No %
austmation:
s,. h.a
.% sea 4 0 d b d. m al t.h ar,a M.al,ndad'2 e f..- U m .:. A Let % $.)x 8.' W m L J i k b a L L A .3 . d a d i ..ra - oh e m L~0:,_iA oA6.L_
u., % k i e-&:. ., u ,shl'ai M A r..A m. M A L .001'-
s a .uLe. en tm Ieonem M U b *. h 2v w il' .D %
_.6 a. . n.o,&b u X ,mi.d. aauAd sesO k- 7a.E 'Ac. % -
._ Vus Av-. d d O 6 eDi\VM bu0 01 $k e_. 4 1
- 2. Is the possibility for an accident or malfunction of a different type than any evaluated prevsousJy in the Safety Analysis Report createc t . . . . . Yes No _
.,ust mo tio n, we .a .b e siaAb_erudrh k 6 LLot e a w L ., L % A n. a k a d ~ % sita b d & n s
doJ M A L s Zm mbd h 4,J. nam 1h J w ed ~cAeRmb g o v a
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t
- 3. Is the margin of safety as defined en the Dasis for any tecnnical specification
- ,eoucear... ..... . . ... . . . .Y es N o ,, ,,_,
I bLo moo. a cL A r. N 1 0 d w b eb. %
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~ Pespersd by J.6 smsd /2/14/9/
.. Revleued by ffi d e N (2.l17 6&-
SAFETY EVALUATION OF
~
RADWASTE DEMINERALIZERS SQNAPS-7-009 ,
APPENDIX C
~ Work Instructions
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SQNP
{ SOI-77.iD-B Page 1 of 3 - Unit 0 Rev. 40 Date / / .
IV. INSTRUCTIONS
['C. Normal Operation of Rad Waste D. I. in Service to (a) Monitor Tank (b) Cask Decon Collector Tank or (c) Distillate.
1.
In the instruction section of this SOI-77.1D, A Part has been .
completed and is in Rad Waste Status File.
, 2.
. Complete the following valve alignment for operation of Rad '
Waste D. I. Use flow print 47W830-3 R-12 for reference',
f I
Drumming Waste to Aux Contractor Closed Valve 0-FCV-77-402 Rad Waste Discharge Header Valve Open 0-FCV-77-400 Rad Waste Discharge Recire Valve Open 0-FCV-77-401 Rad Waste D. I. Discharge Valve Open1 0-77-921 Rad Waste D. I. Discharge to Closed 0-77-968-CDWE Conc. Return Closedi 0-77-967 Chemical Dr. Tk. Pump Dis. Closed 0-77-711 Waste & Aux. Waste Evap. Closed 0-77-713 Dis. to Drumming Header Rad Waste Recire Header Valve Closed 0-FCV-77-302 Rad Waste Recirc Header Valve Closed 0-FCV-77-227
- Rad Waste Recire Header Valve Closed 0-FCV-77-301 Rad Waste Discharge Valve to Closed S.R.S.T. 0-77-951 j ~~'-
Rad D.I. Discharge to CDCT or Closed Monitor Tank 0-77-712 Waste Drumming' Header Valve to Closed Drum Station 0-FCV-77-213 Waste Drumming Header Valve to Closed Drum Station 0-FCV-77-214 Waste Drumming Header Valve to Closed L Drum Station 0-FCV-77-215 Waste Drumming Header Valve to Closed Drum Station 0-FCV-77-216 Waste Drumming Header Valve to
~
Closed 0-FCV-77-217 Drum Station Waste Drumming Header Valve to Closed Drum Station 0-FCV-77-218
- 3. Open valve 0-81-518
(
for operation. Rad Waste.D. I. Valve when D. I. is ready -
, 1 v.
Valves shall drumming not be operated if the CDUE is recire. concentrates through waste header. - l l
[ -185-
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SOI-77.1D-B - Unit 0 Page 2 of 3 Rev. 40 L IV. INSTRUCTIONS C. (Cont.)
'[. Jf" 7 4. -
[ To pump from Rad Waste D. I. to (a) Monitor Tank (b) Cask 1 Decon. Collector Tank.
(a) or (b) and only one. Complete one of the following y ,
6.a g To pump from D. I. to Monitor complete th$'following valve alignment.
Monitor Tank.Check to be sure F.D.C.T. is not pumping to f8 W.C.T. Filter Iso. Valve Closed Waste Drumming Return to Aux. 0-77-648
~ Open 0-77-635
' Waste Evap.
Aux. Waste Evap. Supply Line Open 0-77-922 (Bypass Check Valve) -
Aux. Waste Evap. Feed Valve Open Aux. Waste Evap. Bypass Valve 0-77-633 Open 0-77-630 Supply to W.E. Cond. Filter to Open 0-77-647 Monitor Tank
.. Waste Evap. Cond. Filter Inlet Open 0-77-561 J .. Waste Evap. Cond. Filter Outlet Open 0-77-595
"- Resin Trap Dis. Valve from Waste Closed 0-77-564 Evap. Cond. Demin.
l
- Local Sample of Supply to W.E.
l Closed 0-77-560 Cond. Filter Inlet Rad Waste D. I. Discharge to Closed 0-77-967 C.D.W.E.
Rad D.I. Discharge to CDCT or Open 2 Aux. Vaste Evap. Feed Isol 0-77-712 Closed 0-77-629 I,.
- Locat'ed in Waste Drumming Room 1
Is not to header. be opened if CDWE recire. of concentrates through waste drumming
(
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. SQNP d$ SOI-77.1D-B - Unit 0
,f- Page 3 of 3 Rev. 40
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IV. INSTRUCTIONS (Continued)
{
C. 6. b. Valve alignment from D. I. to C.D.C.T.
f Waste Drumming Return to Aux.
Vaste Evap. Open 0-77-635
[I Aux. Waste Evap. Supply Line (Bypass Check Valve)
Open 0-77'922 A'ix. Waste Evap. Feed Valve Open Aux. Waste Evap. Bypass Valve 0-77-633 0 pen 0-77-630
(- Supply to W.E. Cond. Filter C1'osed 0-77-647 to Monitor Tank
, V.C.T. Filter Iso. Valve Open 0-77-648 W.C.T. Filter Iso. Valve Open 0-77-683 I Supply Valve to W.C.T. "A" Closed Supply Valve to W.C.T. "B" 0-77-651A Supply Valve to W.C.T. "C" Closed. 0-77-651B f
C.D.C.T. Supply Valve
-- Closed 0-77-651C
- Open 0-77-666 s
Rad Waste D. I. Disch. to Monitor Open 0-77-712 Tk. or C.D.C.T.
Rad Waste D. I. Disch. to Closed 0-77-967 C.D.W.E.
Aux. Waste Evap. Feed Isol. Closed ' 0-77-629
- 5. -
Record correct flow path thru D. I. to correct tank being supplied water from D. I. on Rad Waste Print Status Board.
6.
Refer to SOI-77.1A8 these pumps being used or 1B4 to supply from T.D.C.T.
waste to D. or I.F.D.C.T. to start .
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SQNP .
[ SOI-77.lB4 - Unit 0
-1 af Page 1 of 5 '
Rev. 30 .
FLOOR DRAIN COLLECTOR TANK (Demineralizer and Non D.I. Processing) l Date / /
I. PURPOSE To provide following conditions for operation, precautions, and instructions for the operations.
A. Normal Operation B.
To transfer contents on FDCT to Cask Decon Collector Tank C.
To transfer contents of FDCT to Waste Condensate Tanks A, B, or C .
D.
I To transfer contents of the FDCT to the Rad Waste D. I.
II. CONDITIONS FOR' OPERATION '
A.
Normal valve alignment for the Floor Drain Collector Tank Check .
list S0.I-77.1B4-1 Completed and in Rad Waste status file.
B.
( Power Availability Checklist 77.1B4-1 for FDCT pump (s) Comoleted and in Rad Maste status file.
r C.
Rad Waste prints marked according to Valve Checklist SOI-77.1B4-1 or deviated. -
~
, III. PRECAUTIONS I
- A.
All water in the FDCT should be considered radioactive.
B.
The FDCT and TDCT must not be crosstied together. If they are'crosstied together the FDCT must be processed thru Rad Waste D. I. or CDWE IV. INSTRUCTIONS Floor Drain Collector Tank
~
A. Normal Operation 1.
Check the level in floor drain Collector Tank maintain between 10% to 70%
2.
Conditions above for operation and signed off. Part's A, B, and C have been completed
~~
OS
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SQNP
- ' SOI-77.lB4 - Unit 0 afb Page 2 of 5 .
4 Rev. 30 B.
To transfer contents of FDCT to Cask Decon Collector Tank Operator Date / /
1.
Approval from SE or Radwaste Coordinator to pump FDCT to CDCT i~
2.
Valve Checklist on SOI-77.1B4-1 for Normal Alignment on FDCT is completed and in Rad Waste status file.
~ . _ .
- 3. Power Availability Checklist 77.1B4-1 for FDCT pump (s)-
comoleted and in Rad Waste status file. '
t
- 4. Open the following valve for proper valve lineup to the CDCT.
l
.a. Open 0-77-630, Aux. Waste Evap. Feed-bypass va'lve. '
- b. Open 0-77-648 Waste Condensate Tank filter inlet. .
, c. 'Open 0-77-683 Waste Condensate Tank filter outlet.
d ., Open 0-77-666 Cask Decon. Collector Tank inlet.
.5.
Check Valve 0-77-647 to Monitor Tank closed.
- 6. .-
Check Valves to the Waste Condensate Tanks A, B, and C Closed.
f l' a. A - WCT Valve 0-77-651A . ,
- b. B - WCT Valve 0-77-651B
- c. -C - WCT Valve 0-77-651C
- 7. Record correct flow path on Rad Waste Print Status Board from FDCT to CDCT.
- 8. Start FDCT Pump (s) and monitor CDCT level as it increases.
CAUTION: These is no high level alarm on CDCT, just low level alarm.
- 9. Stop FDCT Pump (s) when CDCT is at its desired level. FDCT Pump (s) will stop automatically at 10% level in FDCT.
- 10. Close Valve 0-77-666 to CDCT, Inlet and record on Rad Waste Print Status Board.
- M I. -114-g h*
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-$b' SOI-77.1B4 - Unit 0 Page 3 of 5
- Rev. 30 -
C.
To transfer contents of the FDCT to Waste Condensate Tanks A, B or C. '
Operator f 1.
Approval Date / /
from SE or Radwaste Coordinator to pump FDCT to WCT A,
.e B, or C.
- 2. ' Valve Checklist on SOI-77.1B4-1 for normal alignment on the FDCT is Comoleted and is in the Rad Waste sta,tus file.
f' 3.
Power Availability Checklist 77.1B4-1 in Floor Drain Co,llector Tank Pump (s) is Comoleted and in Rad Waste status file.
[I 4. Close the following Valves for proper Valve alignment to the Waste Condensate Tank (s).
- a. 0-77-647 Monitor Tk. inlet from Rad Waste System.
b.
0-77-666 CDCT inlet from Rad Waste System. ~
- 5. Check Open the following Valves for proper Valve alignment to the Waste Condensate Tanks.
- a. Open 0-77-630, Aux. Waste Evap. Feed Bypass.
- b. Open 0-77-648 Waste Condensate Tank Filter Inlet.
, c. Open 0-77-683 Waste Condensate Tank Filter Outlet.
- 6. Open Waste Condensate Tank Inlet Valves as needed. -
- a. 0-77-651A "A" WCT Inlet.
- b. 0-77-651B'"B" WCT Inlet.
4 c. 0-77-651C "C" WCT Inlet.
a
8.
Start FDCT Pump (s) and monitor WCT's as the level increases.
High level alarm at E 90%. .
FDCT Pumps trip off at 10% low level.
10.
Close the inlet Valves that were open to the Waste Condensate Tanks A, B or C and record on Rad Wste Print Status Board. .c
' a. 0-77-651A "A" WCT Inlet.
- b. 0-77-651B "B" WCT Inlet.
- c. 0-77-651C "C" WCT Inlet.
M
'9 W
l -115-
(-
- SQNP SOI-77.1B4 - Unit 0 Page 4 of 5 Revision 45 D.
To transfer contents of the FDCT to the Rad Waste D. I. .
Operator Date / /
- 1. -
" Valve Checklist on SOI-77.1B4-1 for Normal Alignment on the FDCT is completed and is in the Rad Vaste Status File.
2.
Power Availability Checklist SOI-77.1B4-1 for FDCT Pump (s) is Comnieted and is in Rad Waste Status File.' -
3.
Terminate the use of the Waste Evap. Feed Pumps (TDCT),'
y if in use.
- CAUTION: If shutdown of Rad D. I. will be necessary, call Rad Waste D. I. Operator to inform him.
4.
.+ Open Valve 0-77-621 Aux. Waste Evap. cross connection to Waste Evap.
L
- 5. Close Valve 0-77-629, Aux. Waste Evap. Feed Isolation to CDCT W or-WCT's.
p 6. Open Valve 0-77-534 Waste Evap. Feed crosstie valve.
p 7. --
Close Valve 0-77-540 TDCT Recirculation Valve.
~
"8. Insure' Rad Vaste D. I. is manned and ready for operation with operable flev path out of Rad Waste D. I. to (a) Monitor' Tk (b) CDCT. This is in SOI-77.1D Part C or D of instructions.
- 9. Record correct flow path on Rad Waste Print Status Soard.
10.
Start A and/or B Aux. Waste Evap. Feed Pump (s) (FDCT Pumps).
3- 11.
CallI. Rad D. and Waste check D.theI. tank at PAX 6346 level to verified being flow filled by thetoD. R5dI. Waste 12.
Shutdown Rad D. I. as needed by stopping Aux. Waste Evap.
Feed Pump (s) (FDCT Pumps).
e w
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-116-b_ .
=. . .... _ _ _ . . __
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- SQNP SOI-77.1B4 - Unit 0
' Page 5 of 5 -
Revision 45 -
13.
f _ Align the FDCT per SOI-77.1B4-1 by closing Valve 0-77-621 and opening Valve 0-77-629.
f 14. -
Record correct flow path on Rad Waste print status board.
V. REFERENCES
-r . 47W830-1 - -
l 47W830-2 47W830-3
- 47W819-1 1
l
+
4
=
I - '
- i. .
1 L
~
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l -117-4 -.,,,,-,-.------n, ,--,..-.n,. , . , , , . . . , , , . , _ - - _ . , . - . --- , . , . , , , . - . - - . _,n_,,,v.a,,- , , , , . . , . . , ,,e,,--
o SQNP Valve Checklist 77.1B4-1
~
SOI-77.1B4 - Unit 0 *
,. Page 1 of 1
- , Rev. 42
- SRO Date / / Operator "
Purpose of Valve Checklist: Normal Valve Alignment for FDCT I Flow Diagram
Reference:
47W830-1 47W830-2 47W830-3 I 47W819-1
.' Verified By Required f , Function Position . Valve No.
Floor Drain Collector Tank Drain to Aux (1) Closed 0-77-616 i
Building Floor and Equipment Drain Sump -
Aux Waste Evap Feed Pump "A" Suction Open O'77-617A Aux Waste Evap Feed Pump "A" Casing Drain Closed 0-77-618B Aux Waste Evap Feed Pump "A" Discharge Open 0-77-620A Aux Waste Evap Feed Pump "B" Suction Open 0-77-617B Aux Waste Evap Feed Pump "B" Casing Drain Closed 0-77-618B Aux. Waste Evap Feed Pump "B" Discharge Open 0-77-620B
' Aux Waste Evap Feed Cross Connect to Closed , '
Waste Evaporator 0-77-621 -
Aux Waste Evap Feed Filter Inlet Open L 0-77-622 Aux Waste Evap Feed Filter Vent Closed (2)0-77-623
( Aux Waste Evap Feed Filter Drain Closed 0-77-624 Aux Waste Evap Feed Filter Outlet Open. 0-77-625 Aux Waste Evap Feed Filter Bypass Closed 0-77-626 Aux Waste Evap Feed Filter Local Sample Closed 0-77-627 Aux Waste Evap Feed Recycle to FDQT Throttle 0-77-628 ,,
Aux Waste Evap Feed Isolation Open 0-77-629 g CCS surge tank relief line drain in U-2 Closed 0-77-1351 653 pipe chase .
(1) Valve located on bottom of tank, on East side,1" line. .
(2)If shield plug is installed on Aux. waste evap. filter housing, the vent valve is closed per maintenance instructions.
l -
118-
- , - - - ,,. ---.,n .. -
. l .: .
.;g *
- SQNP i',
SOI-77.1B4 - Unit 0
,. Y Auxiliary Waste Evaporator Feed
- Pump Power Availability 77-1B-4
'~ Page 1 of 1 Rev. 30 '
I
~
- I. ELECTRICAL BOARD ENERGIZED AND EQUIPMENT - ACB CONNECTED NORMAL CONTROL PRINT FUSES INSTALLED REFERENCE Aux Waste Evap 480V Fuel and Feed Pump A Two 10 Ampere 45N743-2 Waste Handling Fuses Board A . 45N775-1 l .- '
Verified .
l J
Aux. Waste Evap 480V Fuel and .
Feed Pump B Two 10 Ampere 45N743,-21 Waste Handling Fuses
' Boa rd B _.
45N775-1 Verified -
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, SQNP-SOI 77.1A8 - Unit 0 Page 1 of 3 .
Revision 28 ,.
.; TRITIATED DRAIN COI.I.ECTOR TANK (Demineralizer Processing) -
Date I. PURPOSE
{
j To following provide conditicns for operation, precautions, and instructions for the operations:
A.
I, Normal Operation *~
B. ..
1 To transfer contents of the Tritiated Drain Collector Tank tio D. I. '
C.
" Tritiated drain collector tank to floor drain collector tank. -
II. CONDITIONS F0ht OPERATION 3 A. .
Normal valve alignment for Tritiated Drain Collector Tank Valve Checklist 77.1A8-1 completed and in Rad Waste Status File B.
o Power Availability Checklist 77.1A8-1 for TDCT Pump (s) completed and in Rad Waste Status File t_ C.
Rad Weste prints marked.according to valve checklist 77.1A8-1 or deviated.
~
g III. PRECAUTIONS .
A.
All water in the Tritiated Drain Collector Tank should be consider radioactive.
B.
The TDCT and FDCT should not be crosstie together. If they are the
, FDCT evaporator. must be processed thru Radwaste D.I. or condensate demin. waste t
IV. INSTRUCTIONS I
A. Normal Operation i
1.
Check the level in the Tritiated Drain Collector Tank and operate the Rad Waste D.I. as required to maintain level between 10% to 50%. .
- 2.
Conditions above and signed for Operation off. parts A, B and C have been completed NOTE: .
This places the Tritiated Drain Collector Tank in a condition of readiness to receive drains. The water l
will betoremoved Tank the Rad Wsate from the D. I.Tritiated per PartDrain Collector .
instruction, "B" of this g
, . l "*
. W.
,. _ _ _ - - - - _..___--_.m., . . . _ _ , , , , _ , . . . _ . _ , _ _ _ _ . , _ , . _ , _ _ , , _ _ , . _ _ _ . . . . _ _ , , _ _ _ _ _ . _ _ . _ - . _ _ _ _ , _
'. SQNP SOI 77.1A8 - Unit 0 J -
Page 2 of 3 .
Revision 45 TRITIATED DRAIN COLLECTOR TANK (Demineralizer Processing)
IV. Date a INSTRUCTIONS (Continued)
" B.
To transfer Rad W'aste D.the I. contents of the Tritiated Drain Collector Tank to the d
1.
e Completed Valve Checklist, SOI-77.1A8-1 for TDCT normal valve alignment in Rad Waste Status File. ~-
- 2. , Completed Power Availability Checklist, SOI-77.1A8-1 in Rad Waste Status File.
L 1' 3.
Check Recire Valve 0-77-628 on FDCT closed. N/A this step
-if FDCT is not being processed to Rad Waste D. I.
4.
- Terminate the use of Auxiliary Waste Evaporator Feed .
Pumps (FDCT), if in use to Rad Waste D. I. N/A step l
if it does not apply.
l CAUTION:
Shutdown of Rad Waste D. I. may be necessary.
If so, notify Rad Waste D. I. operator.
p 5.
Check Recire Valve 0-77-540 on TDCT. Throttle only if FDCT
~ was being processed thru Rad Waste D. I.
"6 . .
- Record position of Valves 0-77-628 (FDCT Recire).and l 0-77-540 (TDCT Recire) on Rad Waste print status board
- only if FDCT was supply to Rad Waste D. I. N/A if it does not apply.
7.
Insure Rad Waste D. I. is manned and ready for operation with operable flow path out of Rad Waste D. I. to (a)
Monitor SOI-77.1D, Tank or (b)
Parts C Caskor D ofDecon Collector Tank. This is.in instructions.
]h Radwaste print status board is to be completed for applicable instruction.
8.
Start A and/or B Waste Evaporator Feed pump (TDCT).
,4 9.
- Call Rad Waste D. I. , PAX 6346 to verify flow to Rad Waste D. I, and check the tank level being filled by the Rad Waste D. I. ,
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SQNP -
SOI 77.lA8 - Unit 0 Page 3 of 3 IV. Rev. 28 INSTRUCTIONS (Continued)
C.
Tritiated Drain Collector Tank to Floor Drain Collector Tank 1.
Permission from S.E. or Radwaste Coordinator to perform instruction.
2.
Completed valve checklist SOI 77.1A8-1 for TDCT normal valve alignment F
in radwaste status file.
a 3.
Completed power availability checklist, SOI 77.1AS-1 in radwaste status file.
f~
4.
Close 0-77-533 waste evaporator filter bypass on TDCT discharge header (to prevent flow to radwaste D.I.). *
- 5. Open waste evaporator feed X-tie valve 0-77-534 i
6.
- Close A.W. evaporator discharge valve 0-77-529.- Make sure A.W.E.
feed pumps are off and locked out.
- 7. Check open A.W. evaporator feed pump recirculation valve 0-77-628.
- 8. Open 0-77-621 auxiliary waste evaporator X-tic tc waste evaporator discharge header (TDCT-FDCT X-tie).
9.
Start A and/or B waste evaporator feed pumps and fill FDCT to needed
, level..
10.
Stop A and/or B waste evaporator feed pump when FDCT is at desired level. .
- 11. Close the following valve to place valve checklist in normal alignment. 0-77-534 waste evaporator feed X-tie valve to A.W. evaporator discharge header, 0-77-621 auxiliary waste evaporator X-tie to waste evaporator discharge header.
12.
Open the following valves to place valve checklist in normal alignment.
0-77-529 A.W. evaporator feed discharge valve, 0-77-533 waste evapora-tor filter bypass valve.
V. REFERENCES 47W830-1
- 47W830-2 47W830-3 47W819-1 . 2 4
ans O
f.
[..
SQNP .-
l Valve Checklist 77.1A8-1 SOI-77.1A8 - Unit 0 *
', Page 1 of 2 -
Rev. 42 *
- SRO DATE '
OPERATOR 4
Purpose of Valve Checklist: Normal Valve Alignment for TDCT a
Flow Diagram
References:
47W830-1 47W830-3
[ 47W819-1 a- .
Verified By Required *-
{ Function Position Valve Number F Tritiated Drain Collector Tank (2) Closed 0-77-528 i
to AB Floor and Equipment Drain Sump Waste Evap. Feed Pump A Suction Open i 0-77-529A :
Waste Evap. Feed Pump B Suction Open 0-77-529B Waste Evap. Feed Pump A Discharge Open 0-77-532A Waste Evap. Feed Pump B Discharge Open 0-77-532B Waste Evap. Feed Pump A Casing Closed Drain 0-77-530A Waste Evap. Feed Pump B Casing Closed Drain , 0-77-530B -
Waste Evap. Filter Bypass (1)0 pen
.. 0-77-533 Waste Evap. Feed Filter X-Tie Closed L 0-77-534
- , WEF Filter Isolation (1) Closed 0-77-535 WE Feed Isolation (1) Closed ~
0-77-538 Local Sample closed 0-77-539 l
TDCT Recirculation Valve Throttle
- 0-77-540 WE Feed Isolation closed 0-77-541 ..
(1) Position of these valves can be reversed if Rad Waste D. I. prefilter is not in use and the Waste Evaporator feed filter is to be used. Record this correction on Rad Waste print status board. ,
(2) Valve located in TDCT Room, East Side.
l .
l l
. W
o .. ~
SQNP Valve Checklist 77.1AB-1 SOI-77.1A8 - Unit 0 4
J .
Page 2 of 2 Rev. 33 Purpose of Valve Checklist:
To align valves from discharge of TDCT Waste Evap-g.
orator Feed Pump to Rubber Bullhose to Primary Water lleader to Rad Waste D. I.
I
' NOTE: This page of valve checklist instructions to be removed when temporary bullhose is removed and primary water header rett.rned to normal operation.
~
. Verified Bv Function Required' Position Valve No.
3.
VALVES LOCATED ON EL. 669 '
Primary Water Hdr Isol Vlv (by AUO Desk) Tagged Closed 0-81-514 Primary Water Supply to Waste Evap. Tagged Reagent Tank Closed 0-77-547 Primary Water Supply to Aux Waste . Tagged Evap Reagent Tank Closed 0-77-639 Primary Water 2" Supply to the Waste s Evap Package Closed 0-81-516 Primary Water 2" Supply to the Aux Waste Evap Package Closed 0-81-516 . .
Primary Water 2" Supply to Spent Locked Resin Tank Closed 0-77-695 VALVES LOCATED ON EL. 705 BY RAD WASTE D. I. & DRUMMING ROOM Primary Water Supply for flushing of Tagged Drumming Header Closed 0-77-714A
- Primary Water Supply for flushing of Tagged Drumming Header Closed 0-77-714B Primary Water Supply for flushing of Tagged Drumming Header Closed 0-77-715A Primary Water Supply for flushing of Tagged
, Drumming Header Closed 0-77-715B Primary Water Flush Valve to Spent Tagged .
Resin Fill lleader l Closed 0-77-716 l 2" Red llandle V1v off Bullhose Supply .
1 to Primary Water lleader (On El 653, by {
TDCT Room Doorway Closed No Number l - ,.
. j 1
)
. . *e SQNP -
Waste Eva'p orator Feed Pump Power Availability Checklist 77.1A8-1 * '
SOI-77.1A8 .
- Page 1 of I l Rev. 28
- ELECTRICAL BOARD ,
ENERGIZED AND EQUIPMENT NORMAL CONTROL PRINT ACB CONNECTED FUSES INSTALLED REFERENCE Waste Evaporator Feed Pump A 480V Fuel and Waste Two 10 Ampere Handling Fuses 45N743-2
, 45N775-1 2
Verified Board A Compt 2C '
Waste Evaporator 480V Fuel and
! Feed Pump B Two 10 Ampere 4SN743-2 Waste Handling Fuses 45N775-l' t
Verified Board B Compt 2C '
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CALCutATICN CLAssleICAT!"N
- c. e , -. ., e - , n. . v. eros.cy,ny.
PLANT / UNIT SOA// I d 2- IDENT!r!ER _rew Apr oo?
1 RIMS NO. Ti45 '8B 1 2 3 0 551 Issue cATE ,msu -
TITLE Sde51 Svoloo4/su d &DWE REVIsICN LEVEL O cre? cts 0 svsTE~rs) .
PLANT FEATURE:
SYSTEM / COMPONENT DEsCRIPTICry; .
O sarETv sv5 ten sysTEn No.
~ "
~1 *7 / re. de.,u+e Den m lize e tw> eh PLANT ENUIRONnENT Evao,m4or CEC, ETC.) '
h NON-SAFETY SYSTEM sYsTEn NO.
APPEMOIX R -
O CIuIt STRUCTURES O INsTRunENTATIoN C1.s7,PAM,ETC) -
O LICENsINs -
O oTRER ~
F?Not rLeestevroTtON O EssEnTIa' O r!'E Cnty h DESIRAsLE
[ su."ERCECID suanITTED _f.c, Q,a w /re DATE r2-/ z/tf REuIEUED .218 h DATE et - 1't - n l
APPRCUED W -
DATE _ /L/30/.R I
I r 1
- a . .
- Attrch:n nt NJ.1 '
3 P;ga 2 cf 2
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CALCULATION CLASSIFICATION ,
IDENT!FIER: S/0N APS 00 F PRELIMINARY CLASSIFICATICN: '
ESSENTIAL C FIL'E OflLY
@ DESIRASLE C SU."ERCEDED ,
CALCULATION CLASSIFICATION JUSTIFICATION: '
SUSMITTER: $th &bNes a b y U ex:%d8 &
naud n V
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f n 9s& Au4L4' J
- 05.1 ' 27 xYd
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REVIEUER: ASREE WITH
{ CLASSIFICATION
_ ] DISAGREE -CCM.9E.'!S RECU!EEC 6
o ne oe e "
e e e
.sLASSIFICATION g,
RECUIREO O
Gun
', TVA 10691 (DNE-0A-6-86) DNE CALCULATIONS Wb-- _EC l Title l Plant / Unit l l
Safety Evaluation of CDWE l SQN/l&2 l lPreparingOrganization l KEY NOUNS (Consult RIMS Descriptors List) l DNE/ NEB l Safety Evaluation. Liquid Waste Systems l l
l Branch /Projectidentifiers lEachtimethesecalculationsareissued,preparersmustensurethatthe. l l
l original (RO)RIMSaccessionnwberisfilledin. l l SQNAPS-7-008 lRev (for RIMS' use) RIMS ACCESSION NUMBER l l l R0 h70107F013862 ~B45 '8612 3 0 551l l l l
'llApplicableDesignDocument(s) lR I l Bd5 ,87020? 5-51l l NA R
lSARSection(s) l UNID System (s) l l l l l 11.2 l - 77 lR I l l l Revision 0 l RI I R2 i R3 ISafety-related? Yes ( ) No (x) .]
lECNNo.(orIndicateNotApplicable)l l l lStatementofProblem l l 5911 1 5911 l l l l l Prepared .. l j ( ,, l l l The use of the SQN COWE in place of the l l
M, M4s,Mn ::.fu/n' dMI.lat11 l l deficient radwaste evaporators constituto a l g .
l l majorchangetosystem77. This change is l lChecky l K(M Mc b /// id2.9 /&f- Urb ~ l l evaluated as required by Tech Spec 6.15.1 l l to verify that no unreviewed safety questioni l Reviewed l l l l Af. 8. E -- -- n /2*lf4 h
- g"*T~ l l exists. The need for the evaluation was !
l m,/ stlp hf l i #D2-55N lUSE FORM l List all pages added l2/2/ai f l
l l
l l m27/86-2wi and m28/862Ba l Reference r.eno L44 860715 805 0
lTVA10534lbVthisrevision l l l l l llFMORE lListallpagesdeleted l l l l y0 l SPACE lbythisrevision l I l l Q l REQUIRED l List all pages changed l l l l l l' lby this revision l l l l G l ABSTRACT [These calculations contain an unverified assumption (s) that must be verified later. Yes ( ) No (x)) Q l \.! }
lAsafetyevaluationwasperformedtoevaluatethesafetyofutilizingthecondensatedemineralizerwasteevaporator8 l (COWE) for routine processing of liquid radwaste from the floor drain collector tank (FDCT) and tritiated drain D lcollectortank(TDCT).
Q l 0 l The evaluation concludes that the C0WE can be safely operated indefinitely on radwaste liquids of the quantity and' B lactivitygeneratedatSQN. Releases of radioactive materials, offsite doses, and occupational exposure were found 8 l to not be signficantly affected by the change. There is no increase in the probability of an accident or D lpossibilityofanewaccidentfromthoseevaluatedintheSafetyEvaluationReport. However, it is recommended )
l that the CDWE building floor joints be sealed to minimize the consequence of radioactive materials leaking from B lspillsinthebuilding. 4 i '
>0 l S I B I B I 0 i B l DNEl-NEB-2976Q [
l 0
( ) Microfilm and store calculations in RIMS Service Center Microfilm and destroy. () @
(# Microfilm and return calculations to: D. L . /Vlid,' A l//J /( Address: W/DC/M C-r Q cc: Nmd, dL Zb L-A l
1
l 5 REVISION LOG
! i Tsue SAFETY EVALUATION OF CDWE I
r
"'O ",, DESCRIPTION OF REVISION 972,,
1 The crystallizer feed / level controls description were revised to reflect the method of operation used by ikt., 5"Cpi":d;. .
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P:so 1 cf 16 SAFETY EVALUATION OF CDWE Prepared by 32 ,,w/e4 at</st SQNAPS-7-008 Checked by th 82/19/8 4 Introduction
~ ~ ~ ~
Reference 1 listed seven information requirements that must be fulfilled to satisfy the requirements of Technical 3pecification 6.15.1 for major changes to the liquid radweste process system. Changes made to the condensate domineralizer waste evaporator (CDWE) to process radioactive waste from the .
floor drain collector tank (FDCT) and tritiated drain collector tant (TDCT) , . , _ , ,
constitutes a major change. Each of the seven information requirements and responses are presented in subsections of this document.
k
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DNE1 - 2984Q NEB 12/21/86 t
.,. , . Pego 2 cf 16 SAFETI EVALUATION OF CDWE Prepared by h. $ u'& nnlMl%
SQNAPS-7-008 Checked by MP90
- 2[17hs Technical Specification 6.15.1 Question 1
- 1. Provide a summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59. .
Response to Question'l In April 1985, a safety evaluation was performed by DNE-NES (calculation NE8 CALC-SQNSSG4-001, Appendix B) to evaluate the feasibility of utilizing .
the Condensate Domineralizer Waste Evaporator (CDWE) in place of the. '
deficient waste evaporator and auxiliary waste evaporator. DNE-NE8 determined that no unreviewed safety question existed for this change.
See Appendix B for details.
Sub' sequent'to this evaluation, two incidents have occurred where liquid has leaked from the floor of the CDWE building, through the building floor .
joints, and into the soil adjacent to the building. The soil was slightly' ~
contaminated as a result of the leakage. Corrective action was taken to remove the contaminated soil and refurbish the floor joints, however, the joints are not leak proof. While not considered an offsite dose concern. -
the problem should be corrected to minimize occupational exposure and to minimize generation of low-level radwaste.
Technical Specifiestion 6.15.1 Question 2
- 2. Provide sufficiently detailed information to totally support the reason for the change without benefit of additional or supplemental information.
Response
The installed liquid radwaste processing system at Sequoyah Nuclear Plant, (SQNP) consisted of a 15-gal / min rated auxiliary waste evaporator and a 2-gal / min rated waste evaporator. These evaporators have been tested and found to have serious functional deficiencies. Testing has shown that the evaporators cannot produce acceptable quality distillate when operated at greater than 70 percent of their design flow rates. The reduced operating capacity.is inadequate to process the large volumes'of liquid waste (up to 25.8 gal / min average over a month) that is being generated from 2 units at SQN. Since the evaporators are not capable of processing the liquid waste being generated, the CDWE has been modified to process high conductivity borated floor drain water.
DNEl - 2984Q NEB 12/21/86
_, m ;
/ t
- C I, >
, Pago 3 of 1G .
SAFETY EVALUATION OF CDWE
,, Prepared by R . d I b islavic .
SQNAPS-7-008 ,
, Checked by I4+ Ch INb)
An engineering study (reference 3) Was performed to determine the scope of..
system modifications required to upgrade the evaporators to an acceptable level of performance,and reliability. The conclusions reached in' s reference 3 are as fellows: '
' ~
- 1. Replace Crane Chompump concentrate pumps with centrifugal have or can accept the Allis-Chalmers dydomics seal (e.g.,pu'ans ( which Allis-Chalmers pumps). The dynamic seal appears to be the'bsst sea currently on the market for concentrated boric acid applicationr.
- 2. Replace both level sensing systems with a glyce$ n-chkrged capillary '
pressure sensing unit utilizing a bellows seal-to prevent-the freeains of level control tubing (i.e.. Taylor model Nos. 381T or 'A2TQ, i or ..
equivalent). Also, provide flushing ca'pability for the level sencing .
connections. * ,
- 3. Install a spo'o1 piece and leak detection device and alarm on the .
evaporator condensse' rupture dise flange (i.e., Fluid Components, {
Incorporated, floy monitor). The alarm'should signal on the local control panel and twflash to the control room whenever a la'ck or -
rupture of the dise' occurs. The device would close the evaporator '
steam supply valve'and the isolation valve inlthe vent condenser vent pipe to plant vent (see modification item 20). The spool pioce will e
provide for quick replacement of the rupture disc.
- 4. Relocate all pumps (i.e., two concentrate' pumps and two distillate pumps) off the evaporator skid to a location in the evaporatoe roox where maintenance is allowed.
- 5. Install a sight glass across the vent conderiser and a high-level alas to allow the operstor to tell when the vent condenser is ficoded.
Also, relocate the vent. condenser to a higher' elevation in che .,
evaporator room to reduce the flooding problem. The alarm will be at i the local panel with reflash to the control rocm.
6.
Install a check valve on the eductor lihe between the educt'ur and steam trap and a differential pressure-operated solenoid s!)6 toff ve.1ve to prevent backflow into the vent condenser. ~
l
- 7. Install a moisture trap on the vent line to the plant ventilation .
system.
(This trao must not significantly lacrease pressury drop of the vent line.-) ,
- o -
- 8. Install density meter instrumentation (e.g., D;tiatrol) to indicato near end-poir<t concentrations of evaporator boicoms.
l DNE1 - 298/.')
NEB 12/21/86 l
t
a 5 o s . .
,,. SA5ETYEVALUATIONOFCDWE Prepared by E.6' j'. ,,,,/.., af,4]y .
SQh*APS-i-008 Checked by ((24, 84/2fh6
, u
- 9. Convert present sampling system to a continuous flow sample system for feed, concentrates, and distillate with minimum piping lengths and flushing connections.
>A-
- ', _ 10. Reloc t4' existing pressure gauges, feed and distillate flow meters
'- from isilde the evaporator cubicle to the local control panel outside the cubicle.
- 11. Add a bypass around reflux line orifice with a remote-controlled flow control valve and flow measurement capability with flow readout at i control panel for the reflux line.
- 12. Install fleximesh or other liquid de-entrainment device in the .
9vaporator vapor outlet. "
f .
t
- 13. Install a sight glass across upper and lower flush line connections to -
permit a check of level instruments. .
14 Modify controls to control level at 50-55 percent instead of 60 percent.
- 15. Install a 1" drain line to the waste disposal system with a drain
,b valve and check valve on the vent condenser eductor line to allow the draining of the vent condenser if flooding has occurred. Note: This drain is to be considered as a possible permanent drain during evaporator operation.
- 16. Replace seat of vent condenser steam trap with a new seat manufactured of stainless steel'.
- 17. Install a check valve on the distillate recycle line just prior to its
+
tie-in to the foed line.
- 18. RJmove and relocate / replace vent condenser drain eductor from the s: , concentrates recirculation line to the evaporator feed line.
- 19. Reroute the evaporator condenser rupture disc discharge piping to the FOCT vent. This will let the large amount of moisture associated with these ruptures return to the FDCT.
1 i
l
,, DNEl - 2984Q i NEB 12/21/86
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, SAFETY EVALUATION OF CDWE Prepared by Br. S M A is f 24/fs j SQNAPS-7-008 Checked by 12/2 3 l
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- 20. Install a different'ial pressure. instrument in ths evaporator vent !
piping to the waste gas system. This instrument is tp close the vent isolation valve automatically when the evaporator venting. pressure is below the waste gas header pressure and when a rupture' disc is blown.
The modification together with item 21 will prevent inadvertent
' contcmination of the evaporator room due to a loss of pressure in the evaporator.
~
s
- 21. Install vent.
a vapor pump in the vent condenser vent piping to the plant .
This pump is to interlock with the evaporator steam valve,'
rupture disc flou, detector, and vent solenoid isolation valve (see modification items 3 and 20). This pump will operate when stceted from the control panel and will stop for a ruptured disc or closed
' vent solenoid' isolation' valve. This pump is to aid the " venting of the-evaporator while permitting lower stenming rates and thus reduce carryover problems.
(s.lze for 30 lb/h air and noncondensibles, mostly -
air.) i The estimated cost to implement these modifications was $600,000 in 1981 value dollars.
Based on the ettensivC scope and cost bf the twenty one modifications l to correct-equipment design, and the need for more process capacity above the design capacity of the evaporators, TVA decided to upgrade the'CDWE to process high conductivity floor drain water.
Technical Specification 6.15.1 Question 3 3.
Provide a detailed description of the equipment, components, and process involved, and the interfaces with other plant systems.
Response to Question 3 A. Equipment and Components The CDWE is an HPD evaporator / crystallizer rated at 30 gal / min. The unit is a forced circulation type evaporator consisting of a vapor body, recirculation loop, and two-pass vertical heater. It was designed to process contaminated liquid waste produced in the regeneration of condensate demineralizer resins and FDCT waste water.
At its rated capacity of 30 gal / min, the CDWE has been routinely used to process liquid radwaste produced from the FDCT and TDCT.
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i2h4/E -
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.The CDWE consists of a crystallizer vessel, mesh pad entrainment separator, an external heater, a recirculation pump with interconnecting piping, and auxiliary equipment including an instrumentation rack and a control panel.
Crystallizer The Inconel 625 crystallizer is 7'0" in diameter and 19'-2" in overall height. It is a cylindrical vessel, with a cone bottom. Operating volume is 503 ft3 Entrainment Separator Vessel -
'The entrainment separator vessel is 4 ft. In diameter a-id contains a 1 ft. thick mesh pad. It is located adjacent to the crystallizer. The mesh pad assembly is designed and supported to facilitate remote removal from the entrainment separator for maintenance and decontamination. Spray water nozzles, above the mesh pad and below, are provided for. regular cleaning.
Heater .
The heater-,- 4'-1/8" in diameter and 18'-6" in overall length, is a l vertical tube design with two passes on the liquor side. The unit l consists of 214 2" OD x 16 BWG (average wall) x 14' long Inconel 625 l tubes. The interior surfaces of the crystallizer, and the liquor '
boxes of the heater, have been given a No. 4 finish. These polished surfaces reduce the tendency for fouling and solids accumulation.
They are also considered advantageous with respect to the extent to which radioactive lovels can be reduced prior to maintenance operations.
Recirculation Pumq The recirculation pump is a Lawrence Axial Flow pump designed to handJe 6000 gpm at 15 ft. TDH, with 22 ft. NPSH required, and pump speed at 898 rpm. The pump, equipped with a Falk 6C1 gear reducer, a 75 HP TEFC motor is mounted on a common baseplate with six spring supports. This spring-mounted base design accommodates the thermal expansion of the recirculation loop system. The stuffing box is sealed with a Durametallic type /R0 double' mechanical seal, with auxiliary grapholl packing to prevent gross leakage'in the event of seal failure.
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Ptss 7 cf 16 SAFETY EVALUATION OF CDWE.
j,f f Prepared by } d E M- w i/4 ist:g M SQNAPS-7-008 Checked by 12/9/8C Condenser and Subcooler A' condenser and subcooler are provided with the radwaste ecncentration system. The condenser is a horizontal unit having two tube passes on the cooling water side. The condenser serves as a heat sink for the-evaporator. It contains 400 3/4" OD x 18 BWG x 8'-0" long tubes of-304L stainless steel construction. The subcooler is a single pass exchanger with 174, 3/4" OD z 18 BWG x 8'-0" long tubes.
Instrument Rack- .
An instrument is provided to mount transmitters and controls which' require field mounting but which, for maintenance and operation, have -
'been kept out'of are'sa which are restricted due to the presence of radioactivity. Purge water for process connections and for the recirculation pump mechanical seal and wash water for the mesh pad
- entrainment separator are controlled at the instrument rack.
Instrument panel An instrument panel with Leeds and Northrup controllers has been provided to serve the concentrator system. The semi-graphic display provides esse of checkout and monitoring of instrumentation, and process.
The CDWE was initially designed to process a sodium sulfate (Na2SO4) waste stream. Plant requirements require the CDWE to process borated waste streams too. The volatility of the borated waste necessitated the modification of the entrainment separator to improve the stripping of the volatile components from the overhead vapors, as well as addition of more piping, valves, and instrumentation.
The CDWE has been modified to permit diversion of the steam condensate flow to the CDWE blowdown tank (BT-9). The diversion is based on conductivity. A high conductivity condition will cause the steam condensate to be diverted to the blowdown tank.
A sample sink / instrument skid (AP-1) is used for sampling of feed, distillate, steam condensate and concentrates in the CDWE recirculation loop. The skid also has instrumentation for monitoring the pH and corrosiveness of the concentratca in the CDWE recirculation loop.
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Pege 8 of 16 SAFETY EVALUATION OF CDWE .
Prepared by f d'. d -M et/24/W SQNAPS-7-008 Checked by /ffl/r [ IM29[6'
~
Entrainment Separator The entrainment separator was modified to include ballast trays for refluxing and stripping. The vessel length was extended by 7'-4".
The vessel is 48" in diameter and 14'-4" long between tangent lines.
The unit includes a York meshpad and three trays supplied by Glitsch.
The modifications of the entrainment separator included the addition of some peripheral equipment. The equipment included the reflux pump, control valves A0V-58 and 59, flow instruments FE-55 (orifice plate),
FIT-55 (dp cell transmitter), FI-55 (panel mounted flow indicator),
and FAH/L-55 (flow alarm). These items provide the reflux stream flows over the trays counter to the vapor flow, in order to remove -
gases from the water' vapor. The vapor passes through vFry ~small holes in each plate. The pressure drop and flow rate are controlled so that only vapor, not the reflux liquid, pass through the holes; thus -
" bubbling" the vapor through the liquid and stripping the volatiles from the vapor.
Sample Sink Skid The sample sink skid is approximately 34" deep by 108" long by 90" high. It . includes a 24"x24"x10" stainless steel sink with a vented plexiglass hood. Provisions are included for sampling feed, distillate, condensate and concentrates in the CDWE recirculation loop. Wash hoses are provided for cleaning spillage. The pH (AE/AI-71) and corrosion (AE/AI-70) instruments for monitoring the concentrates in the CDWE recirculation loop are mounted on this skid.
Steam Condensate Diversion System The CDWE was modified with the necessary piping and instrumentation to divert the steam condensate to the CDWE blowdown Tank (BT-9). The diversion is determined by the condensate conductivity.
The components for monitoring the steam condensate quality are located on the conductivity analyzer skid AP-2. AP-2 measures 66"Hx36"Wx6"D and is mounted on the condensate pump skid. Included on AP-2 are the sample cooler; the condensate analyzer; PCV-65, a pressure control 1
valve to reduce the pressure in the condensate line to the appropriate level for downstream instrumentation; PRV-66, a pressure relief valve to protect the equipment from high pressure; PI-67, -a pressure gauge !
to indicate system temperature; TI-68, a temperature gauge to indicate l
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f.* ,. . Pags 9 of 16 SAFETY EVALUATION OF CDWE Prepared by f P ., ,M-r) nt2 yM .
SQNAPS-7-008- Cheeked by- ,. i &
. system temperature; FI-69, a rotameter flow indicator to indicate and adjust the condensate flow rate through the condensate analyzer; and CE-4, a conductivity element to measure conductivity. CE-4 is not a new component as it was in the system before (furnished under contract.
'7-126) and has been relocated to AP-2. The conductivity meter (CIS-4) '
associated with CE-4 monitors the steam condensate quality and
~
provides input to control valve A0V-30 to determine if the condensate 4
should be diverted to the blowdown tank.
' Control valve A0V-30 has been added to permit diversion of the
- condensate to BT-9. The condensate diversion system also uses A0V-29, CE-4, and LC-29. These are now utilized in the condensate diversion system. Solenoid valve SOV-40 has been added for transferring the condensate level pot level controller (LC-29) signal from A0V-29 to .
10V-30 on high conductivity. -
- B. Processes ,
Steam. Steam Condensate, and Vent Gas The driving force for evaporation is provided by saturated steam which enters the heater at.the steam inlet nozzle. The steam supply is at 65 psia; it is desuperheated and'the pressure is reduced. As the steam enter,s the heater it is diverted along the internal plenum (which distributes the steam throughout the length of the tube bundle) by means of a baffle plate. The baffle plate prevents serious erosion and vibration of the heat exchanger tubes caused by the high steam velocities at the inlet.
The steam condenses on the outside of the tubes and transfers its heat to the liquor flowing through the tubes. The resulting condensate flows from the heater by gravity to the condensate drain tank.
Noncondensible gases, including air, can accumulate in the heater shell. These gases,if allowed to build to high levels, reduce the i
efficiency of the unit. A continuous flow of gases is vented via the I i vent gas nozzle on the shell side from the system through the vapor pipe of the separator to the condenser and subcooler. Non-condensible gases which are vented from the condenser and subcooler are cooled in the vent gas cooler before discharging to the vent system.
l Evaporator Control -
The evaporator has three primary control loops: steam flow, feed flow, and concentrate discharge.
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Steam Flow 1
The capacity of the concentrator is determined by the steam flow to the heat exchanger. Under the design conditions, normal steam flow is '
about 18, 350 lbs/hr at 35 psia pressure. If the feed liquor is significantly hotter or colder than design temperature (80*F), the steam flow will require adjustment to maintain the required evaporation rate. The steam pressure at the heater chest is also-
' monitored to provide an indication of the heat. transfer efficiency of. ~
the unit. .
Feed Flow / Crystallizer Level Control-4 At design' conditions of feed and product liquor and evaporation rate. -
the feed flow should average 30 gpm. The crystallizer level is controlled automatically by adjusting the crystallizer level con'.-ol. gg
-~
The feed flow to the crystallizer is controlled by the flow controller, the set point of which is reset by the crystal 11zer level controller. Therefore, in order to maintain the desired feed rate, it.
will be necessary to adjust the steam rates, and the bottoms i .
withdrawal rates. Increasing the steam rate will tend to increase the product density, therefore, the liquid level setpoint must also be --l Rg increased.
Concentrate Discharge ES' Concentrated waste is withdrawn from the crystal 11zer in preset batch quantities. The normal average discharge rate is 1.5 gpm. The actual (or instantaneous) rate is 30 gpm. The density of the concentrate is measured by a Dynatrol density transmitter which measures the density of the slurry on the recirculation line. The density transmitter ,
provides an electronic signal to the density recorder.
em l
I' DNEl - 2984Q NEB 12/21/86 o
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' SAFETY EVALUATION OF CDWE Prepared by [Mc[48 2[2/,$7 .
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[ b1[/[/O hf) '
Indicators and Recorders Several significant process measurements, such as temperatures and pressures, are indicated or recorded to monitor the evaporator system operation.
a) Steam flow -'
b) Steam pressure / temperature ~
- ~ ~
c) Feed liquor flow d) Feed liquor temperature e) Feed liquor analysis - pH value, etc.
f) Concentrated waste temperature g) Concentrated waste density '
h) Concentrator body level ..
i) Heat exchanger inlet temperature ,
~ -'
-2 " d j)* Heat! 6xchangerloutlet! temperature ..
k) Circulating pump amperage -
_l) ' Crystallizer vessel pressure m) Conductivity of steam condensate n)n' Conductivity of distillate - . - - . . . .. -. -. ---. ..
o) Concentrates withdrawal rate p) Pressure drop across mesh pad -
m-nau -r non e i rt . rnor ui r . u. r.e . ; .- n. , . .. .s C. Interfaces With Other Plant Systems All Interfaces with the CDWE are shown on mechanical flow diagram N 47W830-7. A list of these interfaces are as follows: .
a) Demineralized water supply to blowdown tank b) Distillate pump drain to floor drain c) Layup water header to distillate pumps e) Distillate to cooling tower blowdown f) Offgrade distillate / slurry discharge to floor drain collector tant y (recycle) g) Waste feed from nonreclaimable holdup tank .
h) Waste feed from floor drains . _
i) CDWE building to waste disposal system vent header j) CDWE building atmospheric vent k) CDWE concentrates to. drumming area '
- 1) Electric power to pumps and controls m) Auxiliary plar.t steam to CDWE heater . . 7 n) Plant instrument air to instruments and control valves o) Cooling water to CDWE condenser subcooler p) Makeup water to CDWE blowdown tank g) Waste feed from TDCT via FDCT ,
DNE1 - 2984Q
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' ' Pcgo 12 cf 16 SAFETY EVALUATION OF CDWE Prepared by M servIO nl24/W -
SQNAPS-7-008 Checked by h e ik2h6 Technical Specification 6.15.1 Question 4
- 4. Provide an evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto.
Response to Question 4 Based on statements in calculation No. SQNSSG4-001 R1, it was determined that liquid from the FDCT, the TDCT, and the CVCS holdup tanks (CVCSHT) would be processed through either the CDWE or the mobile demineralizers '
(MD) currently located in the railroad access bay. This was to be in lieu of processing the~se wastes through the deficient waste evaporator and auxiliary waste evaporator packages.
Expected annual releases were calculated in calculation No. SQNAPS3-033 RO for the CDWE. A comparison of these releases to the liquid releases in the current revision.of Table 11.2.6-2 of the SQN FSAR can be found in Table 1 herein. It'should be noted here that the values in the FSAR reflect the processing of the FDCT and TDCT only. Removing the contribution of the CVCSHT from the calculated releases for the CDWE result in the salues found in Table 2 herein. The remaining differences in Table 2 can be explained in differences in the bases of the appropriate calculations. For example, the amount of liquid radwaste processee in the calculation of the FSAR numbers were based on design assumptions on the operation of the liquid radwaste system while the newer releases are based on actual amounts of liquid radwaste processed at Seguoyah Nuclear Plant.
There are no gaseous releases given in the FSAR for the processing of liquid radwaste, and the sources of gaseous radwaste given in chapter 11.3 of the FSAR do not consider the liquid radwaste system to be a source of activity for processing by the waste gas system (WGS).
Calculation No. SQNAPS3-033 R0 gives the amount of gas released of 314 C1/yr for the CDWE. Table 11.3.6-4 of the SQN FSAR-gives the total release from the WGS of 9,750 Ci/yr. Therefore, the amount of gas released from processing the liquid radwaste will not significantly increase the total amount of radioactive noble gases released.
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~-
6 Table 1 Comparison of Predicted Releases from -
Processing Liquid Radwaste Through CDWE Annual Release (Ci/yr)
FSAR CDWE Liquid 0.26 22.4 Gas 0.0 314 Table 2 Comparison of Predicted Releases from Processing '
Liquid Radwaste From the FDCT and TDCT Through CDWE Annual Release (Ci/yr)
FSAR CDWE Liquid 0.26 3.96 Gas 0.0 19.27 Technical Specification 6.15.1 Question 5
- 5. Provide an evaluation of the change which shows the expected maximum exposures to individuals in the unrestricted area and to the general population that differ from those previously predicted in the license application and snendments thereto.
Response to Question 5 An isotopic breakdown of the releases calculated in calculation Nos.
SQNAPS3-033 R0 and SQNAPS3-034 RO were transmitted to the Radiological Control Branch where exposures to the general population were determined.
A comparison of these exposures to those from Table'11.2.9-2'of the SQN FSAR can be found in Table 3 herein. As can be seen, the new exposures are considerably higher than those reported previously. However, the FSAR exposures do not include the processing of the CVCSitT while the new l exposures do.
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Pago 14lef 16 SAFETY EVALUATION.OF CDWE' Prepared by M,2/ mule #2/24#4 -
SQNAPS-7-008 Checked byffY'[$1})! ,l2fMhr.
'While no exposures were calculated by the Radiological Control Branch for
-releases fIrom'just the FDCT and TDCT, it might be possible to estimate the exposures based on a comparison of the releases from the FDCT and TDCT to the total releases. From Table 1, the total CDWE liquid release to the .
environment Ci/yr.
is 22.4 C1/yr and from Table 2 the corresponding value is 3.96 Assuming a linear relationship between total activity released to the environment and dose, the doses for the CDWE can be reduced by a factor-by 5.66.
The estimated doses can be found in Table 4 below. As a check it is known that the thyroid dose is a direct function of the amou'nt of iodine released. The amount of iodine released from all three sources is 19.12 Ci/yr and 3.33 C1/yr respectively for just the FDCT and TDCT.
Multiplying the CDWE thyroid dose from Table 3 by the ratio of the releases results in a value of 0.96 mrem /yr as opposed to the value of -
0.97 meem/yr determined using the factor of 5.66. Therefore~, the estimated values in Table 4 would appear to be acceptable approximations.
Table 3 Comparison of Predicted Population Doses from Processing Liquid Radwaste Through Various Systems Annual Dose (mrem /yr)
,, FSAR CDWE Bone 0.35 1.21 GI 0.17 0.91 Thyroid 0.34 5.50 Liver 0.38 1.81 Skin .-
1.52 Body 0.33 1.94 Table 4 .
Comparison of Predicted Population Doses from Processing Only the FDCT and TDCT Through CDWE -
Annual Dose (mrom/yr)
FSAR CDWE Bone 0.35 0.21 GI 'O.17 0.16 Thyroid 0.34 0.97 i
Liver 0.38 0.32 Skin -
0.27 Body 0.33 0.34 DNEl - 2984Q NED 12/21/86
. Pago 15 cf 16 SAFETY EVALUATION OF CDWE Prepared by )# 2cw/ze ,m.9/&(
3QNAPS-7-008 Checked by A /2 gp Technical Specification 6.15.1 Ouestion 6
- 6. Provide a comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when changes are to be made.
Response to Question 6 Offsite shipments of solid radwaste from Sequoyah Nuclear Plant for the .
period 10/3/84 through 10/1/85 were provided by Leaon J. Riles III of the Risk Protection Branch in a database file. In the time period examined, there was a total of 4,583 Cl of solid radwaste shipped offsite. Of these, 4,290 Ci were resins and 127 Ci were evaporatcr bottoms. The remaining 166 C1. consisted of trash, solidified oil, etc. ..
~
Calculation No. SQNAPS3-033 RO calculates the amount of solid radwaste generated as 2,950 Ci in evaporator bottoms, and calculation No.
SQNAPS3-034 RO calculates the amount of solid radwaste generated as 2,890 Ci in resins. In the period examined, the mobile demineralizers would have been used to process any liquid radwaste. Thorofore, using the CDWE to process liquid radwaste would increase the amount of evaporator bottoms to 3,077 Ci while reducing the amount of resins to 1,400 C1. The total amount of solid radwasto produced would increase to 4,643 C1.
The predicted liquid and gaseous effluents were discussed previously.
Based on semi-annual reports, the amount of liquid and gaseous effluents released annually while using the old waste evaporator systems were 10.6 Ci and 11,000 Ci respectively. The ioported gaseous effluents are mainly from the WGS. The 314 Ci/yr from the CDWE or 148 Ci/yr from the HD will not significantly iherease the gaseous effluents. The 11guld effluants will increase from 10.6 Ci/yr to 22.4 C1/yr for the CDWE or 29.0 Ci/yr for the MD. There arv several potential reasons for this, the most probable one being that only one unit was in operation at the time the waste evaporators were in use.
~
Technical Specification 6.15.1 Ouestion 7
- 7. Provide an estimate of the exposure to plant operating personnel as a result of the change.
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Pago 16 of 16 CAFETY EVALUATION OF CDWE Prepared by JC# dorado /2 r2W94 SQNAPS-7-008 Checked by [/4 2//2df[6 Response to Question 7 The original design at SQN called for liquid radwaste to be processed by an evaporator followed by demineralizer(s). The current design represents a return to this concept with the use of the CDWE followed by demineralizer(c). In both schemes the evaporator systems were or are located in shielded cubicles with controlled access. Piping of the liquid radwaste to the CDWE is located in shielded pipe chases. Therefore, there should be no increase in exposure Lo plant personnel as a result of operation of the CDWE as opposed to the original evaporator packages. '
me
- O M
O DNEl - 2984Q NEB 12/21/86
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- SAFETY EVALUATION OF CDWE Prepared by /-ef,M[#4 M 3 izygfg SQNAPS-7-008 Checked by M IIf?1[jlp APPENDIX A NRC Commitment Dated October 1, 1986 6
e DNE1 - 2984Q NEB 12/21/86
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- SAFETY EVALUATION OF CDWE Prepared by M b. 34 rslu/S:
SQNAPS-7-008 Checked by [ 2ht-Commitment By October 1, 1986, the Design Control Process procedures u?ll be issued /
revised to ensure that.the requirements of TS 6.15 are met for any future
" major changes" to the radwaste systems.
Compliance ,
On August 25, 1986, a revision was issued to Sequoyah Engineering Procedure SQEP-13 which added the following note: '
"For' design changes to gaseous, liquid, or solid radwaste systems, an
~
evaluation must be performed in accordance with Technical Specification 6.15." .
W l
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- .- SAFETY EVALUATION OF CDWE Prepared by f e, I.v.wMd npals SQNAPS-7-008 Checked by [/ IkP[M S
APPENDIX B -
4 SAFETY EVALUATION NEBCALC-SQNSSG4-001 1
M
- s 0
- DNE1 - 2984Q NEB 12/21/86 4
fs* * . man TvA ios97 (IN DES 144)EN DES CALCULATIONS
, J. TITLE -
SAFETY EVALUATION OF MAJOR CHANCES TO LIQUID PLANT / UNIT RADI0 ACTIVE WASTE SYSTEM PER TECH SPEC 6.15.1 PREPARING ORC.ANIZATION SQN Units 1&2 OE/ NEB KEY NOUNS (Conesit MEOS CIS DESCRIPTORS LIST)
Safety Evaluation, Liquid Waste Systems 8 RANCH /PROJE tT IDENTIFIERS Each n time umber is filledinese in. calculations are issueo, preparers must ensure that ene o ccess.on NEBCALC-!QNSSG4-001 Rev (for MEDS* usel MEOS accession number APPLICABLE f ESIGN DOCUMENT (S)
E50630C0068 O B45 '850426 200
. a t8!508236 0024 O B45 mo8po 200 R_
SAR SECTIOfW ($1 UNIO SYSTEM (S)
.A 11.2 R_
Revision o ;
Revisson - 1 Revisson ECN NUMBER (Enter "N/A" of there is no ECN) 1 Revision 5911 rind 1654 .
PREPARED -
CHECKED 9x 8 &d[AWss 9x 6' Y '
^"
L ho J.)1 D L L .uL~4,W 4fu - es 1/Ju/f 6?CL66 - d t [L' k List all pages maded j
> j]. ~ by this revision.
E j g ;k List all pagespeleted by this revision.
$hh List all pages changed -j' by this revision.
I STATEMENT OF PROSLEM l
The use of the Sequoyah Condensate Demineralizer Waste Evaporator of the in place deficient waste and liquid radioactive vaste system. auxiliary waste evaporators constitutes a major change o the- t Section 6.15.1 to verify that no unreviewed safety question existsThis chang evaluation 1934. was identified as the result of an NRC inspection Theconducted need for this O ABSTRACT Be fore unit I startup at SQN, the original Westinghouse-supplied waste and allow them to process the volume of liquid radwaste to provide adequate processing capability, ould not In order prod modifications to utilize the Condensate Demineralizer Waste for Evapora ng processing and CVCS holdup the contents tanks. of the tritiated drain collector tank, radioactive waste processing facilities and procedures no unreviewed safety question exists. e that b
This evaluation determined that capability to safely process In addition, the determined it was quantities that and types of liquidtheradwaste CDWE has the bein h'eneratedatSQN. Continuation sneet(si used. the design changes will not h Microfilm and store calculation en MEDS Service Center.
Microfilm and cestroy. O C Microfilm and return calculation to:
Aoo,ess:
m REVISION LOG
~ * .
SAFh'TY, .*~6VALwohl 0F MMsR CAAAIGES Yo L/qarD Titne : RADioAc7tvE 04src SYSTEM PER TECH CPEC LIS. I Revision Date
- u. DESCRIPTION OF REVISION 4,,,,,e,
,1 B<--a/ Project t;aM;(se,- dded 4. av e,. Aect +a Z:ry-cles;3n%4c, - MESCALC. We,d;[;cd/on n % ber -f. ,- 7#
h cJcJdion.
~- . .
ene
= - = .
I 1
tv A 10934 (EN DES 4 741
C
,..,,,j..-
,,1...*'.-- . .. .
k .c ,s. ,
cause detrimental interactions with safety-related items. The CDE
.. is housed in a Seimeic Category I structure which prevents its failure or malfwiction from causing releases of radioactive material to the e nvironment . This design feature will, therefore, preclude the possibility of eaceeding :he of fsite dose limits as established by 10CF R100. . Based on these findings, it can be concluded that the use
.of the CDE is a safe and reliable means of processing liquid radwaste at SqN. No unreviewed safety question results from its use. .
Introduetion Due to the lack of liquid radwaste processing capability at SqN, it has been necessary to utilize mobile domineralizers and the CDE for processing both tritiated and nontritiated ' liquid radweste streams.
The change in radwaste processing operation was necessary due to serious functional deficiencies associated with the originally ,
supplied Westinghouse evaporators which could not provide adequate processing capability.
The CDE was originally installed to process radioactive liquid waste-
- produced in the regeneration of condensate domineralizer resins and radioactive waste from the floor drain collector tank. The following -
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evaluation assesses 'the use of the CDE for processing triciated and
- nontritiated radwaste streams to verify that no unreviewed safety question exists. This evaluation is necessary to comply with Technical Specifications 6.15.1 which require that major changes to radwaste processing f acilities and procedures be reviewed in this manner..
Backe r_ou nd The ori~g inally installed liquid radwaste disposal system (LRDS) at SQN consisted of two Westinghouse-supplied evaporators: 1 2 gal / min wasta evaporator and a 7.5/15-gal / min auxiliary was te evaporator. These evaporators were tested and found to have serious functional deficiencies which did not allow either evaporator to produce distillate of acceptable quality when operated at greater than 60: to 70% of design flowrate. This operating capability was inadequate to process the SqN liquid radwast'e stream which ranges up to 25 gal / min.
To allow the plant to process the voltsses of liquid waste being .
generated, cesporary portable desineralizers and the CDE were u tilized. # -
The CDE system vas originally implemented by ECN 1654 at SqN to concentrate radioactive spent regenerant solutions from the condensate demineralizar system and radioactive waste from the floor drain collector tank. In 1982, modifications to plant piping were initiated by Eci 5 911 to include permanent piping to int'erface the CDE with '
the following waste collection tanks: -
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- 1. Tritiated drcia tank via the waste evaporator pump (tritiated drain collection tank discharge pumps).
- 2. Chemical and volume control system (CVCS) holdup tanks via the CVCS holdup tank recirculation pump discharge.
The mobile denineralizer processing system is also tied into and
. capable of being fed from these waste storage tanks.
The CDWE is an HPD evaporator / crys tallizer rated at 30 gal / min. The unit is a forced circulation type evaporator consisting of a vapor body, recirculation loop, and two pass vertical heater. It was designed to process contaminated lig2id waste produced in the regeneration of condensate desineralizer resins. At its rated capacity of 30 gal / min, the CDWE has been routinely used to process liquid radwaste produced f rom the floor drain collector tank and tritiated drain collector tank. Since piping changes were required to ,
provide this processing capability f rom the triciated drain collector tank, maj or changes to the radioactive was te treatment system were involved which require a safety analysis.
Analysis '
Use of the SQN CDWE for processing radwaste streams originally intended to be processed through the waste and auxiliary waste evaporators does not constitute an unreviewed saf ety question as detennined by evaluation of the following items:
- 1. There is no increase in the probability of occurence or the consequences of an accident or malfunction of equipment impo rt ant
' to saf ety .greviously evaluated in the saf ety analysis report.
This is based, in part, on a review of the updated FS AR Section 15 which verifies that none of the sys tem faults analyzed could be increased in severity by any failure or malfunction of the CDtI.
Design changes to the CDKE were done per AtGI B31.1 (1967) and other appropriate industry standards as required by the FSAR to ensure that no Engineered Safeguard Systems will be degraded. The ,
design changes were also done in accordance with Regulatory Cuide 1.143 to ensure that the of fsite dose limits established by 10CFR100 will not be exceeded.
In addition, as a nonnuclear saf ety related component (TVA Class H) located in a Seismic Category I structure, the CDWE is seismically supported as necessary to prevent unacce pt abl e interactions with safety-related structures , sys tems, o r com pone nt s . This design feature will also ensure that no missiles potentially generated by the CDWE sys tem will af fect any safety r elat ed sys tems. Potential breaks in the new piping interf ace between the CDLE and the LRDS will not result in flooding or harsh e nvi ronment to any safety related sys tems in excess of that previously analyzed. No flow p2th is created f rom any new source which could result in additional liquid coming into and potential flooding safety related egaignent in the auxiliary building.
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The f 11ovi:g itema provide assurance that the CDE will not
. increase the effects of LRDS faults of moderate frequency discussed in FSJul section 11.2.4:
A.
The CDWE has a desigm processing capacity of 30 gal / min which is greater than the original SQN LRDS processing capacity.
Therefore, no decrease in systen surge capacity will occur.
The CDWE will not decrease the sys tem's ability to accommodate waste until failures of sys tem components can be fixed.
B. The CDE is designed to process waste streams which would result from excessive leakage from both reactor coolant sys t em and Auxiliary system equipment.
C. The CDLE is designed primarily to concentrate condensate
, demineralizer regeneration vastes (CDRW) which are potentially contaminated by steam generator tube leaks. This includes the -
processing of steam generator blowdown streams which are not releasable directly via cooling tower blowdown because of high activity f rom steam generator tube leaks. -High activity ,
steam generator blowdown is recirculated to the condensate -
sys tem wh~e re it is cleansed by the condensate demineralizers. ,
- 2. There is no possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report.
The CDWE is constructed and housed such that it will provide assurance equal to that of the original LIW6 e quipment that no unanalyzed accident or malfunction could occur as the result of its failure. The CDLE design assures that minimus capability of safety components is not degraded and, theref ore ,_no faul t or eve nt initiated in the CDWE could propo gate to cause a more serious unanalyzed fault or event. Its enclosure in a Category I Seismic Structure provides the capability to pr eve nt or mitigate the consequences of accidents which could result in potentially excessive offsite exposures. The CDGE provides a LRDS decontamination factor equal to or better tha previous equipment. This is verified by comparison of the CDRW .
isotopic concentration, which the CDLE was originally designed to process, with the isotopic concentration of the combined radwaste streams from the triciated and floor drain collector tanks. These isotopicCriteria Design concentrations are both tahalated in the SQN FSAR and SqN
( SQN-DC-V-22.0) $ and indicate thatLigaid Radwaste Disposal Sys tem Modifica the CDLE 's ability to process the higher activity CDRW will allow it to more than adequately decontaminate the activity levels of the tritiated and floor drain collector tank was te streams.
Administrative sampling of the triciated and nontriciated liquid waste sources prior to release to the CDWE for processing in acco rdance with Sys tem Operating Instruction (S01-77.1) will 1(EC5 841206 503)
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ensure that no streams having activity levels higher than the CDE is capable of processing are fed to the CDE. In addition, distillate from the CDE is monitored as it is discharged to the cooling tower blowdown and is automatically isolated upon detection of high radiation to preclude potential release of radioneeive of fluent.
3.
There is no reduction in the margin of safety as defined in the basis for any technical specification.
This is based on a review of the SQN Technical Specifications which reveals no violation of any Limiting Condition of Operation or Surveillance Requirements as specified in Section 3/4.11.1 or elsewhere. The CDE can be successfully operated given'a comprehensive surveillance and maintenance to 104 program, and the high decontamination factor of 10 3 -
associated with it will allow it to reliably control the concentration within the limitsofofradioactive Technical material released Specification from the site to 3/4.11.1'. '
_ Conc lu sions -
In stanmary, the use of the CDE for processing triciated and
- nontritiated SQN liquid rafwaste streams does not constitute an unreviewed safety question.
The CDE is designed to adequately decontaminate all types of liquid radwasta produced at SQN, and no '
accidents dose or malfunctions limits established are foreseen which would exceed the by 107R100. offsite The CDE is also designed and enclosed in such a manner that no potential degradation of any safety-related system is possible as the result of pipe breaks, missiles, flooding, CDE harsh environment, or other failure or malfunction in the sys tem.
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