ML20064L166
| ML20064L166 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Robinson |
| Issue date: | 02/26/1982 |
| From: | Houston R Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20064E577 | List: |
| References | |
| FOIA-82-389 NUDOCS 8203220514 | |
| Download: ML20064L166 (7) | |
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DISTP.lBUT 10!!:
Docket File 50-261 ETSB Reading File ETSB Docket File Doci:et !!o. 'iG-261 FEB 2 61992 RP Reading File
!!T!in2N!Dirl FDP.:
Thonas 11. flaval:, Assistant Director for Oneratinn Reactors, DL F P.C":
R. Uavne lionste n, l s ri stcn! Director for Radiation Protection, DSI SUPJECT:
TAC a78.99 - SAFETY EVAll:^.T10't FOR TliE CilAllGE I!' TIE APPEPDIX A 0F LICEl'EE l'P. PPR-23,11. B. P.091':50" STEA'l ELECTRIC PLA'!T, U'!IT f:0. 2 Attached are an environnental innact annraisal and a safety evaluation which address Carolina Power and Light Conpany's rr> quest for a chance to LCO 3.9.1.4 of !!. B. P.obinson's, Unit 110 2, f.npendix A to license DPR-23.
In accordance with a discussion uith the licenseo on Feburar,v 10, 1982, we have narle two minor editorial corrections on Carolina Pouer and Light Conpany's suhnittal on paqe 3.9-3.
11e find the proposed channe acceptable.
This revieu was conducted bv J. Lee (x?7637), connizant ennineer for this facility, of the Ef fluent Treatnent Ses tens Dranch, DSI.
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R. V.*3.n.* Houstart C. '.'avne flouston, Assistant Director for Radiation Protection Division of Systers Intenration Attachnents:
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SAFETY EVALUATION FDP. N1ENDING OF APPENDIX A TO OPERATING LICENSE NO. DPR-23 H. B. ROBINSON STENT ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 INTRODUCTION Carolina Power and Light Conpany (the licensee) requested in their letter dated January 28, 1982, that Limiting Condition for Operation (LCO) 3.9.1.4 and its basis in Appendix A to Operating License No. DPR-23, be amended to allow the use of the H. B. Robinson, Unit No.1, (a fossil plant) circulating water pump discharge flow as a back-up source for dilution in calculating the release rate of radioactive liouid effluent from Unit No. 2 during periods when the Unit No. 2 circulating water pumps are out of service.
The main condenser circulating water intakes for Unit Nos. I and 2 are located on Lake Robinson, just east of the plant, and discharged via the discharge canal at a point about four miles north of the plant.
Discharge flow rates are 482,000 gpm with three Unit No. 2 circulating water pumps operating and 87,000 gpm with two Unit No. I circulating water pumps operating.
Both units share the same discharge canal.
The radioactive liquid ef fluent from Unit No. 2 enters the Unit No. 2 circulating water discharge pipe before it reaches the discharge canal.
Circulating water from both Unit Nos. I and 2 is dicharged into the canal through separate circulating water pipe at a close proximity to one another. The canal is approximately four miles long.
The amendment requested will allow the licensee to discharge the radioactive liquid effluent from Unit No. 2 with Unit No. I circulating water flow for the required dilution while Unit No. 2 circulating pumps are out of service.
In any given situation regarding a liquid waste release, the ratio of release rate to dilution flow will remain the same.
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. EVALUATION The staff has conducted an independent review of the potential radiological impact associated with the proposed amendment to Appendix A to the license and found that the amending of LCO 3.9.1.4 and its basis, as proposed, will not result in (1) any increase of radioactivity concentration in the discharge canal or in the lake, and (2) any additional releases of radiaoctive liquid ef flue nt.
The change only allows a reduced radioactive liquid ef fluent discharge rate by maintaining the same ratio of discharge rate to dilution water flow rate available.
The use of Unit No. I circulating water pump discharge (providing less dilution flow) will proportionally reduce the allowable radioactive liquid discharge rate from Unit No. 2.
The annual average release rate limits of unidentified radionuclides (26 mci / day),
exclusive of tritium, and the annual average release rate of tritium (10.5 Ci/ day) specified in LC0 3.9.1.1 remain the same.
The licensee will revise the plant operating procedures governing radioactive liquid releases and the liquid waste release pemit foms when this amendment is approved and issued.
CONCLUSION Based upon the above evaluation, the staff concludes that the health and safety of the public will not he endangered by amending LCO 3.9.1.4 and its basis.
In addition, the amending of this LC0 will not increase the probability or consequences of accidents and does not involve a decrease in safety margin nor involve a significant hazards consideration.
E!!VIR0!DiENTAL I!1 PACT APPRAISAL FOR 5!!ENDING APPENDIX A 0F OPERATING LICENSE NO. DPR-23 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 Carolina Power and Light Company is presently licensed to operate H. B.
Robinson Steam Electric Plant, Unit No. 2, in Darlington County, South Carolina.
There is one pressurized water reactor at the site capable of generating 22001Nt of power. The proposed amending of Limit Condition for Operation (LCO) 3.9.1.4 and its basis of the unit's Appendix A technical
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specifications will not affect the reactor power level ~ or the fuel burnup n
and, therefore, not affect the benefits of the electrical power production considered in the Commission's Final Environmental Statement, Docket s
No. 50-261.
A.
Radiolopical Impact As evaluated in the associated Safety Evaluation, the proposed requests, do not affect the conclusions of the SER which were that the radioactivity release rates specified in LCO 3.9.1 would result in concentrations in the circulating water and in the lake that are well below the concntration limits of 10 CFR 20, Appendix B, Table II, Column 2.
B.
Conclusion On the basis of the foregoing evaluation, it is concluded that there would be no significant environmental impact attributable to the amending of LCO 3.9.1.4 and i ts basis.
As a result of this conclusion, the Commission has further concluded that no environmental inpact statement for the pro-posed action need be prepared and that a negative declaration to this effect is appropriate.
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3.9 RADICACTIVE :.2:LUENTS Acolicability
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Applies to the gaseous and liq'uid radioactive effluents from the plant.
CM eetive To assure that radioactive material is not released to the environment in an unecntrolled =anner and to assure that any =aterial released is kept as lov as practicable and, in any event, is within the limits of 10 CFR Part 20.
Soecification It is expected that releases of radioactive =aterial in effluents #11 be kep: at snall fractions of the limits specified in Section 20.106 of 10 CFR Part 20.
At the sa=e ti=e the licensee is per=itted the flexibility of opera-tic., cecpatible with considerations of health and safety, to assure. chat the public is provided a dependable cource of power even under unusual operating c=nlitiens which cay te=porarily result in releases higher than such scall fracticus, but st31' within the limits specified in Section 20.106 of 10 CFR Part 20.
It is expected that in using this operational flexibility under unusual cperating conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.
3.9.1 Liouid Wastes 3.9.1.1 The release rate of radioactive liquid effluents shall he such that the annual average concentration of radionuclides in the circulating water discharge does not exceed the li=1ts specified in 10 C7R 20, Appendix 3, for unrestricted areas.
This condition vill be met by ensuring that:
a.
The a=nual average release rate of unidentified radionuclides vill not exceed 26 nC1/ day, caelusive of tritit=2, and the annual averzge release rate of critiu= vill not exceed i
10.5 Ci/ day or 3.9-1
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- b. Measuring the activities of specific radionuclides in the discharge and adding to the equilibrium activity in Lake Robinson.
3.9.1.2 The concentration of radioactive liquid effluents when averaged over a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shall not exceed 10 times the value permitted by 3.9.1.1 above.
3.9.1.3 Prior to release of liquid waste, a sample shall be taken, and analyzed for beta-ga=ma activity and tritium activity to demonstrate compliance with 3.9.1.1 and 3.9.1.2 above.
3.9.1.4 During release of liquid radioactive wastes, the following conditions shall be met:
- a. A least one condenser circulating water pump shall be in -
operation.
The Unit #2 circulating pumps shall be used when available.
When the Unit #2 circulating water system is out-of-o 1
service, the Unit 0.1 circulating pumps shall be employed.
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- b. The gross activi,ty monitor in the discharge in the discharge b
shall be operable.
3.9.2 Caseous Wastes 3.9.2 The annual average release rates of gaseous wastes shall be limited as follows:
I 3
i EfMPC) 5.0 x 10' (m /sec) where og is the annual release rate (Ci/sec) of any radioisotope,1, and (MPC)g in units of uCi/cc are defined in Colu=n 1, Table II of Appendix B to 10 CFR 20*, except that for isotopes of iodine and particulates with half lives greater than 8 days, the values of (MIC)g shall be reduced by a factor of 1/700.
3.9.2.2 The maximum averaged release rate over 15 minutes shall not exceed 8202030146 820128* * --
+'-
-a rly ave rage limit of 3.9.2.1.
PDR ADOCK 05000261 3.9-2 P
.;i-3.9.2.3 Prior to relessa of gascous vastes, the contents of the gas holdup n
tank shall be sampled and analyzed for radioactivity to determine compliance with 3.9.2.1 and 3.9.2.2 above.
p 3.9.2.4 During release of gaseous vastes to the plant vent, the following conditions shall be met:
- a. At least one auxiliary building exhaust l
fan shall be in operation.
- b. The plant vent activity monitor shall be operable during discharges, or the containment and plant vent monitor shall be sampling from the stack.
3.9.2.5 During power operation, whenever the air ejector discharge monitor is inoperable, gas discharge f rom the air ejector will be routed to the plant vent for monitoring.
Basis Liquid wastes from the Radioactive Waste Disposal System are diluted in the Circulating Water System discharge, and then released to the lake via the discharge canal.(1) With the three Unit #2 circulating pumps operating, the rated capacity of the Circulat'ing Water System is 482,000 gpm. 1Fith both Unit #1 circulating pumps operating, their flow to the discharge canal seuld uulto be 87,000 gpm.7 The actual circulating water flow under various operating conditions will be calculated watar "~' -hr "'rie"r operating condi*ient wt11 F^ calented. from the head differential across the pumps and the manuf acturer's head-capacity curves.
Because of the low radio-activity levels in the circulating water discharge, the concentration of liquid radioactive effluents at this point cannot be measured directly. The concentrations in the circulating water discharge will be calculated from the measured concentration in the Waste Condensate Tank, the flow rate of the Raste Condensate Tank, the flow rate of the Waste Condensate Pumps, and the flow in the C1rculating Water System. To this released concentration. it is necessary
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to add the concentration ' f radionuclides in the o
Circulating Water.
This concentration is significant because the circulating unter flow is usually greater than the flow through Lake Robinson.
The method of calculating the equilibrium concentration of radinuclides in Lake in the FSAR.(2)
Robinson will be as detailed 3.9-3
.