ML18003A872
| ML18003A872 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/11/1983 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| LAP-83-18, NUDOCS 8302150255 | |
| Download: ML18003A872 (13) | |
Text
REGULATOR'INFORMATION DISTRIBUTION 'SOI'EM (RIBS)
"AGCE'SSION NBR:8302150255 DOC ~ DATE: 83/02/11 NOTARIZFD:
NO FACIL'..50-000 "Shear on Harris Nuclear Power Planti
'Unit ii '-Carolina
'";50-001 'Shearon Harris Nuclear Power Planti Unit 2i Carolina
'AUTH INANE AUTHOR 'AFFILIATION
.ZIMMERMANi'S,R.
IGar ol ina IPower 8 Light.Co,
~RECIP ~ NAME
- RECIPIENT AFFILIATION DENTONiHG>>RE Of,fice, of Nuclear Reactor Regulationi Director
SUBJECT:
Forwands source
~term evaluation for vol <<reduction ssysi requested by NRC for use in DES'RC based >>decontamination factors on extremely conservative assumptionsiinconsistent w/Topical Rept AECC 1 ~
DOCKET '0 05000400 05000401 DISTRIBUTION 'CODE: >8001S iCOP IES '>>RECEIVED: LITR.
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Carolina Power & Light Company FEB 11 1983 SERIAL:
LAP-83-18 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS ~
1 AND 2 DOCKET NOS 50-400 AND 50-401 SAFETY REVIEW QUESTION RESPONSE SUPPLEMENT
Dear Mr. Denton:
Carolina Power
& Light Company (CP&L) hereby transmits one original and forty copies of the Source Term Evaluation for the Volume Reduction System (VRS).
This evaluation has been requested by your Mr. Prasad Kadambi for use in preparation of the Draft Environmental Statement (DES).
As we have indicated previously, the decontamination factors of the volume reduction system are being based on extremely conservative assumptions made by the staff which are not consistent with data presented in Topical Report No. AECC-1 which was previously approved by the NRC.
Please contact my staff if you have any questions.
Yours very truly, S.
. Zimmerman Manager Licensing
& Permits JDK/mag (6094C9T5) cct Mr. N. Prasad Kadambi (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Mr. J.
P. O'Reilly (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Ms. Patricia T. Newman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB)
'" 8302i50255 8302ii PDR ADQCK 05000400
'.D:-', 'DR 411 Fayettevilte Street o P. O. Box 1551 0 Raleigh, N. C. 27602
4 4':
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I IE II II 44 I
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D II 4
SOURCE TERM EVALUATION FOR THE VOLUME REDUCTION SYSTEM (VRS)
Figure 1 presents a simplified block flow and mass balance of the URS.
The system will receive radioactive wastes from the following sources:
1.
Backwash from flushable filters on liquid waste process streams 2.
Waste evaporator bottoms "3.
RO concentrate evaporator bottoms 4.
Secondary waste evaporator bottoms 5.
Boron recovery system evaporator bottoms Tables 1 and 2, respectively, present the normal and design basis activities of the particulate and dissolved radioactivity associated with filter backwash.
The radionuclide content and volumes of the remaining sources are provided in FSAR Tables 11.4.1-1 through 11.4.1-3.
These sources of liquid waste are batched and processed through the VRS.
Table 3 presents the annual average and design basis radionuclide input to the VRS.
Though some particulate radioactivity will be trapped on the prefilter, it is assumed that all radioactivity enters the VRS.
The feed material is preconcentrated through a venturi scrubber and a preconcentrator before being sent to the fluid bed dryer (i.e., calciner).
Water vapor exiting the preconcentrator is sent to the condenser and returned to the system.
- However, excess water is directed to the Floor Drain System.
Non-condensed gases from the condenser are also recycled to the VRS; however, a small portion may be exhausted as gaseous waste after processing.
The following sections present an evaluation of the radionuclides which may be eventually discharged to the environment from these sources.
Source Term Anal sis In order to perform the source term analysis from the URS, it was necessary to make a distinction between particulate and dissolved radioactivity entering the system.
The radioactivity present in evaporator bottoms is dissolved and is assumed to pass directly through the feed tank prefilter and enter the VRS.
The filter backwash from the etch disk filters present a more complex situation.
A total of 17 types of )etch disk filters (see Table 1) provide input to the Feed Tank prefilter,
These filters are located in process streams throughout the plant and collect particulate material from these streams.
When the pressure drop across these filters exceeds a preset value, the filters are backwashed by N2 purge to the filter backwash storage tank.
The dissolved radioactivity in the backwash storage tank.
The dissolved radioactivity in the backwash is the activity in the etch disk filter at the time of purge.
For example, the dissolved radionuclide content of the backflush water of the spent resin sluice filter is assumed to be that of the primary coolant.
The average dissolved radionuclide content of the water in the filter backwash storage tank is a weighted average of the dissolved radionuclide concentration in each of the etch disk filters.
The filter backwash storage tank which contains particulate and dissolved radioactivity is passed through a single 44* gallon etch disk filter which collects particulate material above 10'.
The carrying water along with its dissolved solids, is passed to the waste holdup tank.
After processing by the Equipment Drain System, a portion of this water may be discharged.
When the pressure across the single etch disk filter exceeds a preset
- value, it is backwashed to the 1000 gallon particulate concentrate tank via N2 purge.
The activity entering the filter particulate concentrate tank includes the dissolved radionuclides.
The sections which follow describe the mathematical models and assumptions used to calculate these potential sources of liquid and gaseous radioactive effluent.
1.
Liquid Effluent It has been empirically determined by Aero)et that for feed material with a dissolved solids content above 10% by weight, the dissolved solids content (including radionuclides) in the condenser overflow will be 200 ppm.
Since the weighted average dissolved solids content of the feed material is expected to be 110,000 ppm**, the dissolved radionuclide concentration in the condenser overflow will be 1.8 x 10 of that in the feed material.
- Calculation of number of backwashes is based on 50 gal to account for 6 gal contained in interconnecting piping.
- The PCP will ensure that the feed material is always above 10%.
N I
A l
'll II
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With this radionuclide concentration, the condenser overflow of 4.24 x 10 Kg/yr will be routed to the Floor Drain System.
This system 5
provides for treatment via a reverse osmosis unti followed by a cation demineralizer.
The following decontamination factors were assumed:
Cs RO 10 Demin.
10 Total 100 10 10 Others 10 10 100 It was further assumed that 90% of the processed waste is recycled and 10% is discharged to the circulating waste discharge.
Figure 1 indicates that 7.80 x 10 K'g/yr of water is processed through the etch disk filter and sent to the waste hold tank for treatment through the equipment drain treatment system.
This system provides for treatment via an evaporator.
The following decontamination factors for the evaporator were assumed:
Evap.
Cs 104 I
10 Others 10 After processing, it is assumed that 10% is discharged.
2.
Gaseous Effluent As indicated in Figure 1, about 2.4(4) @/yr of water vapor will come off the condenser and be recycled to the dryer.
This represents 4% of the feed material.
A,small portion of the recycled gas will be routed to the VRS air cleaning unit prior to processing through the HEPA and charcoal filter before discharge.
l, II d
II t
Radionuclides
- releases, can be obtained by applying the following decontamination factors:
Iodines A DF of 100 was applied between the feed material to the VRS and the input to the VRS air cleaning unit.
A DF of 10 was applied between the input to the VRS air 4
cleaning unit and discharge to the environment at the plant stack.
Others A DF of 10 was applied between the feed material to the 4
VRS and the input to the VRS air cleaning unit.
A DF of 10 was applied between the input to the VRS 4
air cleaning unit and discharge to the environment at the plant stack.
These relationships are based on empirical data.**
- Topical Report Fluid Bed Dryer Aero)et Solidification System Report No.
AECC-1 February 1975.
I I
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FIGURE I
BLOCK FLOW DIACIRAM OF VRS (2 UNIT OPERATION)
FILTERS TO WASTE HOLDVP
'~
FOR PRO CE.SSINEI TO SOLIDS PAO(AGING FILTER Q+
BACKWASH
- $ TORAOE
- TAHH, 2000 CsAL ETCH DI5 FILTE.R'AI F
HALTE IL PAATICVLAJ.E CONCENTRATE
.TX IOOO CIAI WACITE EVAPORATOR.
BOTTOMS R/O COII(EHTRATE E,VAPORAT0'R SOTTO 7.'I7. 4 KM'I.
41 (3)
/VI(
1.2.'I (4 K /Tg, FEED TANK PRE-FILTER ISO +--
RS FEED TANK 5000 GAL Q TANKS)
S32 (5) Va/YR VENTVRI S CROM'.
CIAStSOLID SEPARATOR SCRIIBBE'R PRE(OH(EHIRATE FLUID BEb DRVER COND E,NSE.
I.IE(~)e, QAS HEATER OVERFLOW TO FI.OOR DRAIN
- TREATMENT, S'(STEQ
, TO PLAN
', STACKlHEPAj CHARCCAL HEPAt CHARCOAL I
FILTERS SE.C WASTE EVAPORATOR BOTTOMS
.SRS EVAPORATOR SOTTOM5 31 K
Si I 1 TO SOLIDS-PA e.S PW) Vg/HR..
(X) DENOTES Ib QP TANKHAS SANPLING CAPABILILITY SEV DATE IT R
2 7236+
IDNKY DATE IY
& 2.7.
5 Aftlt01%D
'yR5 ESASCO SERVICES INCORPORATED ow~C>>" ~~
AttROTCO 12 30 BL G 8 rl/1 ia CAROLwh PowER g LICIHT SHE/IRON HAI(RIS MPP BLOCK FLOW DIAGRAM OF yRS F>guRE I
il r