ML20149E102
| ML20149E102 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 01/08/1988 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 4057K, NUDOCS 8801130221 | |
| Download: ML20149E102 (7) | |
Text
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[D) One Fint National Plaza. Chicago,1:nois Common';;ealth Edison i
(\\
s Address Reply to: Post Offica Box 767
(,
Chicago, Illinois 60690 0767 January 8, 1988 t
I i
i' U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i
Washington, DC 20555 L
r
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2
[
Application for Amendment to Facility Operating Licenses NpF-37, 66, 72 and 75, i
Appendix A, Technical Specifications NRC Docket Nos. 50-454/455 and 50-456/457 i
References (a):
February 18, 1987 letter from K.A. Ainger to H.R. Denton (b): November 17, 1987 letter from K.A. Ainger i
to U.S. NRC I
Gentlemen:
Reference (a) transmitted and application for an amendment to the operating licenses for Byron Station Units 1 and 2.
The amendment incorporates i
operability, surveillance, and sampling requirements into the technical specifications for two additional radioactive liquid effluent monitoring instruments.
These instruments will assure the release limits of 10 CFR part 20 are not exceeded when discharging fluids from the condensate cleanup system sump and the turoine building fire and oil sump to the circulating water system. Reference (b) modified the amendment request to include a composite sample of sump effluent prior to discharge into the circulating water system.
l Reference (b) also indicated this amendment request applies to Braidwood Station.
Based on a December 9, 1987 conference call with the NRC staff to discuss the revised amendment request, commonwealth Edison agreed to provide a simplified one-line drawing showing how the fire and oil sump discharge and the condensate polisher discharge interface with the cooling water flume (lake for Braidwood), circulating water blowdown and liquid release tank. This is provided in the attached drawing. Also provided is a drawing showing the j
condensate polishing system with respect to the secondary system of the plant.
i
%11Mh 50 4
g\\
P (b
U.S. NRC January 8, 1988 As noted on the drawing, the condensate polishers can process between 20 and 30% of the secondary side flow at full power.
The condensate polishers are operated as necessary to maintain steam generator chemistry requirements.
Steam generator blowdown is processed separately.
It is sent through a steam generator demineralizer back to the condenser hotwell.
Both the fire and oil sump and the condensate polisher sump will discharge into the 62 million gallon volume of the flume.
At Braidwood, the j
body of water is the lake, which has a volume of approximately 8 billion gallons. The circulating water pumps (not shown) take suction from the flume and discharge to the condenser which flows to the cooling tower which has a water basin adjoining the flume.
At the discharge cf the circulating water pumps, prior to the condenser, the station blowdown line diverts a portion of the water for discharge offsite to the river.
There is a radiation monitor and composite sampler on the station blowdown line.
If the radioactivity limits exceed the radiation monitor setpoint, discharge of radioactive effluent through the station blowdown lines will be terminated. The liquid release tank discharges into the station blowdown line upstream of the blowdown line radiation monitor. There is also a separate radiation monitor on the liquid release tank discharge.
The proposed technical specification amendment incorporates two radiation monitors and composite samplers to monitor discharge from the turbine building fire and oil sump and the condensate polisher (CP) sump. The condensate polisher sump discharges directly into the flume (lake for Braidwood). A radiation monitor and composite sampler are located on the discharge of the CP sump.
The fire and oil sump discharges to the flume (lake for Braidwood) via the treated waste system.
The radiation monitor is located on the fire and oil sump 6ischarge to the treated waste system. The composite sampler is located on the treated waste system discharge to the flume (lake for Braidwood). The fire and oil sump discharges approximately 40,000 gallons per day at a rate of 25 to 30 gallons per minute. The condensate polisher sump discharges approximately 100,000 gallons of water per condensate polisher bed regeneration. The Station estimates that typically two regenerations will be performed per week.
The maximum discharge rate is 600 gallons per minute.
If radioactivity levels exceeded their setpoints, the discharge into the flume (lake) from the fire and oil sump or the condensate polisher sump would be terminated.
Finally, a sample annual Appendix I calculation was performed assuming the discharge is continuous at the radiation monitor setpoint and the amount discharged is in accordance with the discharge rates presented above.
It was determined that the addition of these release paths will not have a measurable effect on the dose to the public. This calculation was conservative because the activity of the discharge was assumed to be right at the setpoint of the radiation monitor, when in actuality, the expected release will be considerably lower. Details of the calculations are provided in Attachment 1.
U.S. NRC January 8, 1988 Please direct any further questions regarding this matter to this office.
Very truly yours, K. A. Ainger Nuclear Licensing Administrator 1m
\\
Attachments cc: Byron Resident Inspector Braidwood Resident Inspector L. N. Olshan - NRR M. C. Parker - IDNS l
4057K
e Commonwealth Edison
~
B/B Nuclear Power Stations Unit Two Flu m e*
Unit One Cooling Tower 62 Million Gallons Cooling Tower g
j (nyron)
(nyron)
C.irculat.ing Water 660,000 gpm/ unit 40,000 apd 100,000 gal / regen 25 - 30'gpm Two regens/ week 600 gpm max.
Rad Monitor (ORE-PR005)
Rod Monitor (ORE-PR041)
& Compostte Sampler
& Composite Sampler Fire and Oil Sump Condensate P01isher Discharge Sump Discharge Condenser 1 I Condenser g
Release Tank Discharge Rod Monitor (ORE-PR010)
Rod Monitor
& Compoelte Sompier (ORE-PR001)
I I Circulating Water Blowdown to River 5,000 - 15,000 gpm
- Lake at Braidwood with as: proximate volume of 8 billion gallons
Commonwealth Edison B/B Nuclear Power Stations Secondary System Ma.in Steam Feedwater Steam Generator
\\
/
i f f
Turbine s/c V
Demin I
Condensate y
Condenser A
l Condensate 1
g-----
d-'
Polishem Side Stream Condensate Polishing 20% - 30% of Feedwater Flow at Full Power Operated As Steam Generator Chemistry Requires
ATTACHMENT 1 The following is a sample, annual Appendix I calculation to determine the impact of discharges from the fire and oil sump and condensate polisher sump on the Station's current Appendix I calculation. The assumptions used to perform the calculations are listed below.
The isotopic mix was determined from actual data from Byron Station for 3rd qua rte r, 1987. This is the most representative because both units were operational during this time period. The relative precentages are believed to be representative of two unit operation for the life of the plant. The isotopic mix is as follows:
Co-58 37%
Co-60 24%
Cs-137 8%
I-131 11%
Fe-59 2%
Mn-54 4%
Cr-51 8%
Nb-95 4%
Zr-95 2%
(1.95E3) (total particulate uCi)
H-3 =
See the later discussion for details on H-3 calculation.
- 1 = Calculation for the CP Regen Waste Water Assumptions a.
Monitor setpoint is 1.0E-6 uCi/ml b.
2 Regens per week c.
Will process 100,000 gallons per regen Therefore:
1.OE-6 uCi x
2 regen x
100,000 gal x
52 weeks x
3785 ml ml week regen year gal
= 3.94E4 uCi/ year maximum Using the isotopic mix above, the following data is used to perforn Appendix I calculations:
Co-58 1.46E4 uCi Co-60 9.45E3 uCi Cs-137 3.15E3 uCi I-131 4.33E3 uCi Fe-59 7.87E2 uCi Mn-54 1.57E3 uCi Cr-51 3.15E3 uCi Nb-95 1.57E3 uCi Zr-95 7.87E2 uCi H-3 7.68E7 uCi The ODCM Appendix I calculations yield the following results:
WHOLE BODY DOSE = 2.33E-3 MREM ORGAN DOSE
= 5.16E-3 MREM Based on these results, this release path will have no measurable effect on the dose to the public.
Atttchm:nt 1 Page 2
Assumptions:
a.
Monitor setpoint is 1.0E-6 uCi/ml b.
TR processes 40,000 gal / day Therefore:
1.OE-6 uCi x
40,000 gal x
365 day x
3785 m1 ml day year gal
= 5.53E4 uCi/ year maximum Using the isotopic mix above, the following data is used to perform Appendix I calculations:
Co-58 2.04E4 uCi Co-60 1.33E4 uCi Cs-137 4.42E3 uCi I-131 6.08E3 uCi Fe-59 1.11E3 uCi Mn-54 2.21E3 uCi Cr-51 4.42E3 uCi Nb-95 2.21E3 uCi Zr-95 1.llE3 uCi H-3 1.08E8 uCi The ODCM Appendix I calculations yield the following results:
WHOLE BODY DOSE = 3.28E-3 MRDi ORGAN DOSE
= 7.25E-3 MRD(
Based on these results, this release path will have no measurable effect on the dose to the public.
As a source of comparison, in 1986 with Unit 1 operational, Byron Station dose to the public was 1986 WHOLE BODY DOSE = 0.498 mram 1986 ORGAN DOSE
= 0.689 mrom Tritium cannot be detected by the radiation monitors so the calculations performed using the radiation monitor setpoint are not applicable to tritium.
The tritium associated with each release path was calculated by applying the ratio of tritium to fission and activation products released in the 3rd quarter of 1987. The proper ratio was determined to be 1950 x fission and activation products.
After the proposed Technical Specification Amendment is approved, the actual contributions to the Appendix I calculations from the fire and oil sump and the condensate polisher sump will be included on an annual basis.
(0236z) l i
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