ML20059F913
| ML20059F913 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/10/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F911 | List: |
| References | |
| NUDOCS 9401140222 | |
| Download: ML20059F913 (5) | |
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}t UNITED STATES fj j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205Ei64001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. ill TO FACILITY OPERATING LICENSE NO. NPF-29 ENTERGY OPERATIONS. INC.. ET AL.
.'y GRAND GULF NUCLEAR STATION. UNIT 1
~
DOCKET N0. 50-416 "s
3
1.0 INTRODUCTION
By letter dated August 11, 1993, the licensee (Entergy Operations, Inc.),
submitted a request for changes to the Grand Gulf Nuclear Station, Unit 1 (GGNS) Technical Specifications (TSs).
2.0 EVALUATION The licensee has revised the TSs to include wording that is consistent with the revised 10 CFR Part 20, entitled " 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. An evaluation was not performed on Item 3 regarding the definition of " UNRESTRICTED AREA" because this item is still being evaluated.
The proposed TS changes and evaluations follow:
1.
Technical Specification 1.24 DEFINITIONS The licensee has proposed to change the definition of MEMBER (S) 0F THE PUBLIC to conform to the wording in 10 CFR 20.1003.
The change is administrative in nature to implement the corresponding revised 10 CFR Part 20 definition and is acceptable.
2.
Technical Specification 1.40 DEFINITIONS The licensee has proposed to change the definition of SITE BOUNDARY to conform to the wording in 10 CFR 20.1003.
The change is administrative in nature to implement the corresponding revised 10 CFR Part 20 definition and is acceptable.
3.
Technical Specification 1.46 DEFINITIONS The licensee has proposed to change the definition of UNRESTRICTED AREA to conform to the wording in 10 CFR 20.1003.
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. The staff is continuing the evaluation of this item and therefore will not address it at this time.
4.
Technical Specification 6.8.3.d Radioactive Effluent Controls Program The licensee has proposed to revise Item 2 of this TS to change the liquid effluent release concentration values to " ten times the concentration values in 10 CFR Part 20.1001 - 20.2401, Appendix B, Table 2, Column 2."
The licensee has proposed this change in order to retain operational flexibility 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. Title 10 Code of Federal Regulations Section 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 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 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, cc,mpatible 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 implicit limits in 10 cr 10.106 and the explicit limits in 10 CFR 20.1302 which referr. A n i n.ndix B, Table II concentrations.
These referenced concentr. ion n the old 10 CFR Part 20 are specific values which relate to an t
- dose of 500 mrem.
The liquid effluent radioactive effluent oncentration 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.
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 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 the Grand Gulf Nuclear Station has demonstrated that the use of the concentration values associated with 10 CFR 20.106 as TS limits has resulted in calculated maximum individual doses to a member of the public that are small percentages of the values giver in 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 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 and 40 CFR Part 190 which are a fraction of the 10 CFR 20.1301 limits.
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 concentration values given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 - 20.2401.
1 5.
Technical Specification 6.8.3.d Radioactive Effluent Controls Program The licensee has proposed to revise Item 3 of this TS to replace the reference "10 CFR 20.106" with "10 CFR 20.1302."
The change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
6.
Technical Specification 6.8.3.d Radioactive Effluent Controls Program The licensee has proposed to revise Item 7 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 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 shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin, and b.
For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to 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.
The current requirements for the content of the licensee's TS concerning radioactive effluents are contained in 10 CFR 50.36a. Title 10 Code of Federal Regulations Section 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 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 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 requirements allow operational flexibility, compatible with considerations of health and safety, which may tem m arily result in release rates which, if continued for the calendac wter, would result in radiation doses higher than specified in Appenci
! 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 Grand Gulf Nuclear station has demonstrated that the use of the dose rate limits of 500 mrem / year
~:000 mrem / year, and 1500 mrem / year as TS limits has resulted in calculmd maximum individual doses to members of the public that are small percentages of the limits of 10 CFR Part 50, Appendix 1.
Based on the above, it is acceptable that the gaseous release rate TS for radioactive material be based on the stated dose rates.
7.
Technical Specification 6.9.1.5.1 ANNUAL REPORTS The licensee has proposed to revise this TS to replace the reference "20.407 of 10 CFR Part 20" with "10 CFR 20.2206."
This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.
8.
Technical Specification 6.12 HIGH RADIATION AREA The licensee has proposed to replace the reference to " paragraph 20.203(c)(2) of 10 CFR 20" with "10 CFR 20.1601(a)" and to change the radiation measurement distance for classifying a high radiation area from 18 inches to 30 cm.
The changes are consistent with the requirements of the revised 10 CFR 20.1601 and are acceptable.
It should be noted that this TS is not valid for very high radiation areas (10 CFR 20.1602).
9.
BASES 3/4.11.1.4 LIQUID HOLOUP TANKS The licensee has proposed to revise the BASES to replace the reference to
" Appendix B, Table II" with " Appendix B, Table 2".
The change is administrative in nature and is acceptable.
. 10. Technical Specification 6.10.2 RECORD RETENTION The licensee has proposed to revise Item c of this specification which reads " Records of radiation exposure for all individuals entering radiation control areas" to read " Records of radiation exposure as required by 10 CFR 20."
The change is administrative in nature and is acceptable.
- 11. Technical Specification Index 6.9 Technical Specification Definition 1.26 Technical Specification Section 3.ll.l.4.a Technical Specification Section 6.9.1.8 Technical Specification Section 6.14.c The licensee has proposed to revise the listed specifications that refer to the semiannual submittal frequency requirements of the Radiological Effluent Release Report to be changed to an annual submittal frequency.
Additionally, in TS 6.9.1.8, the licensee has proposed to change the report submittal date from "...within 60 days after January 1..." to
...within 90 days after January 1..."
The changes are consistent with the revised reporting requirements in 10 CFR 50.36a and are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Mississippi State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact has been prepared and published in the Federal Reaister on January 7, 1994 (59 FR 1038). 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
S. Klementowicz Date: January 10, 1994
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