ML20151E003
| ML20151E003 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/22/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151E001 | List: |
| References | |
| TAC-64719, TAC-64720, TAC-67113, TAC-67114, NUDOCS 8804140544 | |
| Download: ML20151E003 (3) | |
Text
.
o UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION
- E WASHINGTON, D. C. 20555 5
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.15 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO.15 TO FACILITY OPERATING LICEME NO. NPF-66, AMENDMENT N0. 6 TO FACILITY OPERATING LICENSE NO. NPF-72 AND AMENDMENT NO. 6 TO FACILITY OPERATING LICENSE NO. NPF-75 COMMONWEALTH EDIS0N COMPANY BYRON STATION, UNITS 1 AND 2 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-455, STN 50-456, AND STN 50-457 TAC NOS. 64719, 64720, 67113, AND 67114
1.0 INTRODUCTION
By letter dated February 18, 1987, supplemented by letters dated November 17, 1987 and January 8,1988, Commonwealth Edison Company (the licensee) requested a change to the Technical Specifications for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, relating to the addition of two radioactive liquid effluent monitoring instruments at each station and the addition of a requirement that a composite sample of sump effluent be taken prior to discharge into the circulating water system.
The licensee requested changes to Table 3.3-12. "Radioactive Liquid Effluent Monitoring Instrumentation," 3.3-12, "Action Statements," 4.3-8, i
"Raaicactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements, and 4.11-1, "Radioactive Liquid Waste Sampling and Analysis Program".
2.0 DISCUSSION The licensee proposes that the Technical Specifications be revised for the addition of two new radioactive liquid effluent sources per station, their associated monitoring instrumentation, and modifications to the sur-veillance requirements presented in the Technical Specifications.
The two new release points per station are the condensate cleanup system
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sump and the fire and oil sump. The Condensate Cleanup (CP) System was proposed as a new release point because operating experience has indicated the need to run the system during normal plant operation. This system was originally intended to be utilized for system flushing during startup.
The potential therefore exists for low level radioactivity ih the CP sump from regeneration effluent and system leakage.
Because activity levels are 8804140544 090322 PDR ADOCu G5000454 P
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l antic *ted to be negligible and water q;ality is expected to be accept-able for environmental discharge, sump discharge will be routed to the fiume after being monitored. On detection of an unacceptable activity level, the addad monitor will alann, stop sump discharge, and terminate CP operation.
The original plant design for turbine building equipment and floor drains j
was to collect drain effluent into the oil separator, then route the separated water directly to the radwaste treatment system for processing
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and release via the release tank.
Present operating experience has shown j
that the water volume is higher than originally anticipated, generating a l
heavy load for the radwaste treatment system for a negligible reduction in 1
activity release. Therefore, the licensee is proposing that the :eparated water will be drained to the fire and oil sump, monitored for potential radioactivity, sent to the treated run-off system to ensure environmental standards are met, and then released to the flume.
On detection of unacceptable activity levels, the monitor will alarm and automatically halt sump discharge.
j 3.0 EVALUATION The staf f has evaluated the radiological aspects of the two radiation rronitors and composite samplers to monitor discharge from the turbine l
building fire and cil sump and the condensate polisher (CP) sump and finds the changes meet the acceptable criteria for the process and effluent radiological monitoring instrumentation and sampling systems based on the following regulations and guidance:
(1) 10 CFR Part 20,920.16 as related to radioactivity monitoring of effluents to unrestricted areas; (2)
Regulatory Guides 8.8 and 1.21 as related to sampling frequencies, required analyses, instrument alann/ trip setpoints, calibration and sensitivities.
gross beta-gamma measurements, etc; (3) 10 CFR Part 50, Appendix I as related to the numerical guides for design objectives and limiting conditions for operation to meet the criterion "as low as is reasonable achievable" given in Appendix I; (4) General Design Criterion 60 as related to control releases of radioactive materials to the environment, and (5) Drawings showing how the monitors are located in the effluent release path and describing the actuation logic of the monitors and how the monitors isolate the valves as per NUREG-0472, "Standard Radiological Effuent Specifications for PWR's, "Revision 2, February 1980.
The staff finds that the licensee's proposed Technical Specification changes adding the radioactive liquid effluent monitoring instruments to Table 3.3-12, new surveillance requirements for these monitors (Table 4.3-8) and new sampling and analysis requirements (Table 4.11-1), meet the current Standard Technical Specifications and are consistent with 10 CFR Part 20, 10 CFR Part 50 Appendix I, Regulatory Guides 8.8 and 1.21, and General Design Criterion 60.
4.0 FINDING 0F NO SIGNIFICANT IMPACT Pursuant to 10 CFR 51.32 the Commission has previously determined in an environmental assessment of the proposed action publishe'd in the Federal s
3 Register that granting this amendaent will have no significant impact oa the environment (53 FR 8824).
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed nenner, and (2) such activities will be conducted in compliance with the Commission's regula-tions and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
J. Minns C. Willis Dated:
March 22,1988 l
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