ML20059E287
| ML20059E287 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, Zion, LaSalle File:ZionSolutions icon.png |
| Issue date: | 12/30/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059E252 | List: |
| References | |
| NUDOCS 9401110069 | |
| Download: ML20059E287 (4) | |
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WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 57 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 57 TO FACILITY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 45 TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMfNT NO. 45 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO, 93 TO FACILITY OPERATING LICENSE NO. NPF-11, AMENDMENT NO. 77 TO FACILITY OPERATING LICENSE NO. NPF-18, AMENDMENT NO. 152 TO FACILITY OPERATING LICENSE NO. DPR-39, AND AMENDMENT NO. 140 TO FACILITY OPERATING LICENSE N0. DPR-48 COMMONWEALTH EDISON COMPANY BYRON STATION. UNITS 1 AND 2 BRAIDWOOD STATION. UNITS 1 AND 2 LASALLE COUNTY STATION. UNITS I AND 2 ZION NUCLEAR POWER STATION. UNITS 1 AND 2 DOCKET NOS. STN 50-454. STN 50-455. STN 50-456. S.I!L5_0;151_,.
50-373. 50-374. 50-295. AND 50-304
1.0 INTRODUCTION
By letter dated November 10, 1993, Commonwealth Edison Company (Ceco, the licensee) submitted proposed changes to the Byron, Braidwood, LaSalle, and Zion Stations' Technical Specifications (TS) in support of its plan to implement the revised 10 CFR Part 20.
2.0 EVALUATION The licensee has proposed to revise the TS to include wording that is consistent with the revised 10 CFR Part 20, " Standards for Protection Against Radiation," and will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10.CFR Part 50.
The proposed TS changes and evaluations follow:
9401110069 931230 PDR ADOCK 05000295 P
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1 2.1 L10VID EFFLUENT RELEASE tIMITS (TS 6.8.4.e.2 for Byron and Braidwood)
(TS 6.2.6. A.2 for Zion)
(TS 6.2 F.4.b for LaSalle)
The licensee has proposed to revise the limitation on the concentrations of radioactive material released in liquid effluent to UNRESTRICTED AREAS to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.
The licensee has proposed this change in order to retain operational flex-ibility consistent with Appendix I to 10 CFR Part 50, concurrent with the implementation of the revised 10 CFR Part 20.
The current requirements for the content of the licensee's TS concerning radioactive effluents are contained in 10 CFR 50.36a.
10 CFR 50.36a requires licensees to maintain control over radioactive material in gaseous and liquid effluents to unrestricted areas, produced during normal reactor operations, to levels that are as low as reasonably achievable (ALARA).
For power reactors, Appendix I to 10 CfR Part 50 contains the nur.1 scal guidance to meet the ALARA requirement.
The dose values specified in Appendix I of 10 CFR Part 50 are small percentages of the implicit limits in 10 CFR 20.106 and the explicit limits in 10 CFR 20.1301.
As secondary controls, the instantaneous dose rates required by this TS were chosen by the staff to help maintain annual average releases of radioactive material in gaseous and liquid effluents to within the dose values specified in Appendix I of 10 CFR Part 50.
For the purposes of this TS,10 CFR Part 20 is used as a source of reference values only.
These TS requirements allow operational flexibility, compatible with considerations of health and safety, which may temporarily result in release rates which, if continued for the calendar quarter, would result in radiation ooses higher than specified in Appendix I of 10 CFR Part 50.
However, these releases are within the implicit limits in 10 CFR 20.106 and the explicit limits in 10 CFR 20.1302 which references Appendix B, Table II concentrations. These referenced concentrations in the old 10 CFR Part 20 are specific values which relate to an annual dose of 500 mrem.
The liquid effluent radioactive effluent concentration limits given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402 are based on an annual dose of 50 mrem total effective dose equivalent.
Since an instantaneous release concentration corresponding to a dose rate of 500 mrem / year has been acceptable as a TS limit for liquid effluents, which applies at all times to assure that the values in Appendix 1 of 10 CFR Part 50 are not likely to be exceeded, it is not necessary to reduce this limit by a factor of ten.
The licensee states that use of effluent concentration values that are ten times those listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402 will not have a negative impact on the ability to continue ~to operate within the design objectives in Appendix I to 10 CFR Part 50.
Based on the above, it is acceptable that the instantaneous limits associated with the liquid release rate TS are based on ten times the effluent
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i concentration values given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, to apply at all times, 2.2 UPDATE OF A 10 CFR PART 20 SECTION REFERENCE (TS 6.8.4.e.3 for Byron and Braidwood)
(TS 6.2.6.A.3 for Zion)
(TS 6.2.F.4.c for LaSalle)
The licensee has m oposed to replace the reference "10 CFR 20.106" with "10 CFR 20.1302."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
2.3 GASEOUS EFFLUENT RELEASE LIMITS (TS 6.8.4.e.7 for Byron and Braidwood)
(TS 6.2.6.A.7 for Zion)
(TS 6.2.F.4.g for LaSalle)
The licensee has proposed to revise this specification to read as follows:
" Limitations on the dose rate resulting from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNOARY shall be limited to the following:
a)
For noble gases:
less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b) for Iodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
less than or equal to a dose rate of 1500 mrem /yr to any organ."
The licensee has proposed this change in order to retain operational flex-ibility consistent with 10 CFR Part 50, Appendix 1, concurrent with the implementation of the revised 10 CFR Part 20.
The current requirements for the content of the licensee's TS concerning radioactive effluents are contained in 10 CFR 50.36a.
10 CFR 50.36a requires licensees to maintain control over radioactive material in gaseous and liquid effluents to unrestricted areas, produced during normal reactor operations, to levels that are ALARA.
For power reactors, Appendix 1 to 10 CFR Part 50 contains the numerical guidance to meet the ALARA requirement.
The dose values specified in Appendix 1 of 10 CFR Part 50 are small percentages of the implicit limits in 10 CFR 20.106 and the explicit limits in 10 CFR 20.1301.
As secondary cor.trols, the instantaneous dose rates required by this specifi-cation were chosen by the staff to help maintain annual average releases of radioactive material in gaseous and liquid effluents to within the dose values specified in Appendix I of 10 CFR Part 50.
For purpose of the bases of this
.TS,10 CFR Part 20 is used as a source of reference values only.
These TS
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requirements allow operational flexibility, compatible with considerations of health and safety, which may temporarily result in release rates which, if continued for the calendar quarter, would result in radiation doses higher than specified in Appendix I of 10 CFR Part 50. However, these releases are within the limits specified in 10 CFR 20.106 (10 CFR 20.1302).
This specification, which is based on guidance contained in NUREG-0133, is acceptable as a TS limit for gaseous effluents, which applies at all times as an assurance that the values in Appendix I of 10 CFR Part 50 are not likely to be exceeded.
The licensee states that the use of the proposed. will not have a negative impact on the ability to continue to operate with.a the design objectives in Appendix I of 10 CFR Part 50.
Based on the above, it is acceptable that the gaseous release rate TS for radioactive material be based on the proposed dose rates.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0
[NVIRONMENTAL CONSIDERATION Pursuant to 10 CFR 51.21, 51.32, and 51.35, an eavironmental assessment and finding of no significant impact has been prepared and published in the fedtral Reaister on December 30, 1993 (58 FR 69412).
Accordingly, based upon the environmental assessment, the Commission has determined that the issuance of this amendment will not have a significant effect on the quality of the human environment.
5.0 CONCLUSION
The Commission has 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 manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
S. P. Klementowicz Date:
December 30, 1993