ML20039H233
| ML20039H233 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 12/13/1976 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201190749 | |
| Download: ML20039H233 (5) | |
Text
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- n L i DEC 131976 Docket No.: STN 50-561 MEMORANDUM FOR:
D. B. Vassallo, Assistant Director for Light Water Reactors, DPM FROM:
R.1t. Vollmer, Assistant Director for Site Analysis, DSE
?UBJECT:
ETSB INPUT TO SAFETY EVALUATION REPORT FOR BSAR-205 Plant Name: BSAR-205 l
Licensing Stage:
CP Docket Numbers: STN 50-561 Milestone No.:
24-3 i
Responsible Branch: LWR No. 1-Project Manager:
T. Cox Description of Response:
Draft SER Input Requested Completion Date:
December 6,1976 Review Status:
Complete j
l Enclosed is our Draft Safety Evaluation Report for Chapter 11.0, i
" Radioactive Waste Management," of the BSAR-205 NSSS.
In accordance l
with Amendment 1 to WASH-1341, the radioactive waste treatment systems j
are excluded from the NSSS of a standard plant. Hence our review of Chapter 11.0 has consisted of a review of the interfaces between the NSSS and the radioactive waste treatment systems.
t The following items are site dependent or are not included in the scope of BSAR-205 and will be reviewed for individual license appli-l cations.
I 1.
The seismic design classification of the foundations and adjacent walls of structures housing radioactive waste management systems.
2.
The capability of the liquid and gaseous radwaste treatment systems to meet the requirements of Appendix I to 10 CFR Part 50.
3.
The monitoring, sampling, and control of radioactive effluents from building ventilation systems, the containment purge, the main condenser air ejector and the turbine gland sealing system exhausts.
8201190749 810403 PDR FOIA MADDEN 80-515 PDR
g i 3 137E D. Vassallo.
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4.
Provisions to collect and process spills from tanks outside containment containing radioactive material.
5.
The consequences of component failure that could result in the release of radioactive liquids to potable water supplies
- l and the nearest surface water.
6.
Provisions to collect, process, and monitor turbine building floor drains.
7.
Process and effluent radiological monitoring systems.
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8.
Plant sampling systems.
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9.
ESF. Filter systems.
The applicant has provided sufficient NSSS information for a design basis for the B0P liquid, gaseous and solid radwaste and ventilation systems and the sampling systems. We find these NSSS interfaces to be acceptable.
_ &,ci Y W%.
Richard H. Vollmer, Assistant Director for Site Analysis Division of Site Safety and Environmental Analysis i
Enclosure:
Draft SER i
cc:
H. Denton S. Hanauer R. Boyd l
J. Miller S. Varga J. Stolz T. Cox J. Collins W. Kreger F. Miraglia W. Mcdonald (w/oencl)
J. Panzarella (w/o encl) )
M. Shuttleworth (w/o enc 1 M. Bell J. Minns D. Muller
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ETSB INPUT TO SAFETY EVAL.UATION REPORT FOR BSAR-205 Docket No. STN 50-561 11.0 RADI0 ACTIVE WASTE MANAGEMENT 11.1 Sumary Description Radioactive materials i:1 liquid effluents may be released to the environment by a nuclear plant utilizing a pressurized water reactor from the liquid waste processing :ystem, the boron recycle system, the steam generator-blowdown system and the turbine building floor drain system. Of these, only the boron recycle system is within the standard scope of BSAR-205 as defined in Amendment 1 to WASH-1341. However, BSAR-205 contains interface information to be used as a design basis for the B0P radwaste system.
i' terface infonnation for the 1
liquid radwaste system consists of the concentrations of i
j radicactive materials, volumes, and total curie content of f
liquids from NSSS equipment, which are collected by the liquid radwaste system.
Interface infonnation for the gaseous waste l
l treatment and ventilation systems consists of the concentra-tions of radioactive materials, volumes, and total curie i
content of gases from NSSS equipment, which are input to the gaseous waste treatment and ventilation systems.
In addition to the above, we have reviewed the NSSS interfaces with the
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80P solid radwaste treatment systems. Solid radwaste inter-face information consists of volumes and total curie content s
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,- 2 of radioactive materials in solid wastes generated by NSSS equipment.
Interface information for the sampling systems were also reviewed and found to be acceptable.
11.2 Liquid Waste Systems The only liquid waste system that is within the standard scope of BSAR-205 as defined in Amendment 1 to WASH-1341, is the i
boron recycle system. Other radioactive waste systems will be described in applications which utilize BSAR-205, i
l The boron recycle system described in Section 9.3.4 of this I
report will be a potential release pathway for radioactive I
i materials in liquid effluents. Although the system is designed l
to extensively recycle r rocessed liquids, discharges of evapor-j ator condensate will be required. Babcock & Wilcox considers that 100 percent of these liquids will be recycled for reuse in the plant, but in our analysis, we assumed that 10 percent of the treated wastes will be discharged due to operational upsets and to control the tritium inventory in the plant.
Spent demineralizer resins and evaporator concentrates from the boron recycle system will be periodically transferred to the solid waste management system for packaging and shipment of fsite.
The principal components that will makeup the boron recycle system, along with their principal design criteria, are listed i
in Table 11-1 on the next page.
i f
w Table 11-1 Design Parameters of Principal Components of Boron Recycle Systems
_ Component Number Capacity (gal./ min.)
Quality Group RC Bleed Evaporator 2
20 D
Evaporator Distillate Demineralizer 2
60 D
RC Bleed Evaporator Demineralizer 2
60 D
Deborating Demineralizer
's 100 D
RC Bleed Degasifier 1
200 D
The design capacity of the boron recycle evaporator will be 29,000 gallons per day, whereas the expected input rate will be 1260 gallons per day.
The difference between the expected flows and design capacity provides adequate reserve for processing surge flows. The proposed system design has sufficient capacity, redundancy, and flexibility to meet the concen-tration limits of 10 CFR Part 20 during periods of equipment downtime.
We have concluded that the system design and capacity will be adaquate for meeting the demands of the facility during anticipated operational occurrences.
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