ML20057C197
| ML20057C197 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/21/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057C194 | List: |
| References | |
| NUDOCS 9309280060 | |
| Download: ML20057C197 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION
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- p W ASHINGTON, D. C. 20555 1.,
JF SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
100 TO FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 92 TO FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY. INC.
JOSEPH M. FARLEY NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated August 24, 1992, as revised December 17, 1992, March 4, 1993, and April 29, 1993, the Southern Nuclear Operating Company, Inc. (the licensee),
submitted a request for changes to the Joseph M. Farley Nuclear Plant, Units 1 and 2 (Farley), Technical Specifications (TS). The requested amendments change the Technical Specifications to implement the revised 10 CFR Part 20, Standards for Protection Against Radiation.
2.0 EVALUATION The licensee has revised the.ir 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:
1.
Bases Section 3/4.3.3.1, Radiation Monitoring Instrumentation The licensee has proposed to revise the TS to replace the reference to "10 CFR 20 Appendix B, Table 2, MPC values" with " concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 -- 20.2410), Table 2, Column 1."
The change is administrative in nature and would incorporate the corresponding revised 10 CFR Part 20 section references into the Bases and is acceptable.
2.
Bases Section 4.11.1.4, Liquid Holdup Tanks The Bases section is being revised to read: " Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentratio'ns would be less than the limits of 10 CFR Part 20, Appendix B (to paragraphs 20.1001-20.2401), Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area."
9309280060 930921 PDR ADOCK 05000348 P
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. l The licensee performed an evaluation which demonstrates that the use of the revised effluent conce~ntrations are conservative with respect to the tank i
activity limit which remains unchanged at 10 curies.
i Based on the above, it is acceptable that the liquid concentrations associated with the liquid holdup tanks are based on the effluent 1
concentration values given in 10 CFR Part 20, Appendix B (to paragraphs 1
20.1001-20.2401), Table 2, Column 2.
i 3.
TS 6.8.3.e, Radioactive Effluent Controls Program The licensee has proposed to revise item ii of this TS which specifies the j
limitations on the concentrations of radioactive material released'in liquid effluents.
The licensee has proposed that the TS be revised to I
allow " ten times the concentrations stated in 10 CFR Part 20, Appendix B (to paragraphs 20.1001 - 20.2401), Table 2, Column 2."
The licensee has proposed this change in order to retain operational i
flexibility consistent with Appendix I to 10 CFR Part 50, concurrent with the implementation of the revised 10 CFR Part 20.
l The current requirements for the content of the licensee's TS concerning i
radioactive effluents are contained in 10 CFR 50.36a.
Section 50.36a requires that the gaseous and liquid effluents produced during normal
-l reactor operations must be maintained at levels that are as low as reasonably achievable (ALARA) to unrestricted areas.
For power reactors, i
Appendix I to 10 CFR Part 50 contains the numerical guidance to meet the ALARA requirement.
The dose values.specified in Appendix I of 10 CFR Part l
50 are small percentages of the implicit limits in 10 CFR 20.106 and the j
explicit limits in 10 CFR 20.1301. As secondary controls, the instantaneous dose rates required by this TS were chosen by the staff to keep annual average releases of radioactive material in gaseous and liquid i
effluents to within the dose values specified in Appendix I of 10 CFR Part i
50.
For the purposes of this TS, 10 CFR Part 20 is used as a source of i
reference values only.
These TS requirements allow operational flexibility i
compatible with considerations of health and safety, which may temporarily
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result in release-rates which, if continued for the calendar quarter, would l
result in radiation doses higher than specified in Appendix I of-10 CFR l
Part 50.
However, -these releases are within the implicit limits in 10 CFR l
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 - 20.2401 are based.on an annual dose of 50 mrem total effective dose equivalent.
S'ince a 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 I 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 operational history at Farley has demonstrated that the use of the concentration values associated with 10 CFR 20.106 as the TS limits has resulted in calculated maximum individual doses to a member of the public that are small percentages of the values given in l
Appendix I to 10 CFR Part 50. Therefore, the use of effluent concentration values that are ten times those listed in Appendix B, Table 2, Column 2 to i
10 CFR 20.1001 - 20.2401 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.
The licensee further states that compliance with the limits of 10 CFR 20.1301 will be demonstrated by operating within the design objectives in Appendix I to 10 CFR Part 50 and 40 CFR Part 190.
Based on the above, it is acceptable that the limits associated with the liquid release rate TS are based on ten times the effluent concentration values given in Appendix B, Table 2, Column 2, to 10 CFR 20.1001 - 20.2401, and are to apply at all times.
4.
TS 6.8.3.e, Radioactive Effluent Controls Program The licensee has proposed to revise item iii of this TS to replace the reference to "10 CFR 20.106" with "10 CFR 20.1302".
This change is administrative in nature, incorporates the corresponding revised 10 CFR Part 20 section number and is acceptable.
5.
TS 6.8.3.e, Radioactive Effluent Controls Program The licensee has proposed to revise item vii of this TS which specifies the limitations on the concentrations of radioactive material released in gaseous effluents.
The licensee has proposed that the TS be revised to i
read as follows:
" Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary as follows:
a.
For noble gases:
Less than or equal to a dose rate of 500 mrem / year to the total body and less than or equal to a dose rate of 3000' mrem / year to the skin, and b.
For Iodine-131, Iodine-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 / year to any organ."
The licensee has proposed this change in order to retain operational flexibility consistent with 10 CFR Part 50, Appendix I, concurrent with the implementation of the revised 10 CFR Part 20.
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.. The current requirements for the content of the licensee's TS concerning radioactive effluents are contained in 10 CFR 50.36a. Section 50.36a requires that tt.e gaseous and liquid effluents produced during normal reactor operations must be maintained at levels that are as low as i
reasonably achievable (ALARA) to unrestricted areas.
For power reactors, Appendix I to 10 CFR Part 50 contains the numerical 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 specification were chosen by the staff to keep 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 requireuents 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 operational history at Farley has demonstrated that the use of the dose rate values listed above (i.e., 500 mrem / year, 3000 mrem / year, and 1500 mrem / year) as TS limits has resulted in calculated maximum individual dose to members of the public that are small percentages of the limits of Appendix I to 10 CFR Part 50 and 40 CFR Part 190.
The licensee also states that compliance with the limits of 10 CFR 20.1301 will be demonstrated by operating within the limits of Appendix I to 10 CFR Part 50 and 40 CFR Part 190.
Based on the above, it is acceptable that the gaseous release rate TS for radioactive material be Based on the stated dose rates.
6.
TS 6.
High Radiation Area The licea ae has proposec to revise section 6.12.1 of this TS to replace the rs*c tree to "20.203(c)(2)" with "20.1601(a)."
This croo s O, administrative in nature to incorporate the corresponding revised in ? Part 20 section number and is acceptable.
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7.
TS 6.12, High Radiation Area The licensee has proposed to revise the footnote to section 6.12.2 to-change the distance, from 18" to 30 cm, used to make measurements from a source of radioactivity to determine the dose an individual might receive in I hour.
l This change i.s consistent with the requirement in 10 CFR 20.1601 and is acceptable.
8.
TS 6.9.1.4, Annual Report
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The licensee has proposed to revise section 6.9.1.5 of the TS to replace i
the reference to "20.407" with "20.2206."
l This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
9.
TS 6.14, Offsite Dose {alculation Marual (0DCM) l The licensee proposes to revise section 6.14.2.1.b of the TS to replace the f
reference to "20.106" with "20.1302."
i This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable 10.
TS 6.12, High Radiation Area In response to an NRC request, the licensee has proposed adding an upper limit of 500 rads in one hour as measured at 1 meter from the radiation source for which the TS is valid.
This will ensure that the measures which dre in place for Controlling access to high radiation areas are not used for very high radiation areas (20.1602), which require additional controls, i
t This change is consistent with the requirement of 20.1602 and is i
acceptable.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of Alabama official
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was notified of the proposed issuance of the amendment.
The State official had no comments.
l 4.0 fNVIRONMENTAL CONSIDERATION This amendment changes recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR
- SJ '>2(b) no environmental impact statement or environmental assessment need be pr%. ed in connection with the issuance of this amendment.
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5.0 CONCLUSION
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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 i
be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
1 Principal Contributor:
Steve Klementowicz Date:
September 21, 1993 b
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