ML20127E526
| ML20127E526 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/06/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127E515 | List: |
| References | |
| NUDOCS 9301190357 | |
| Download: ML20127E526 (5) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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,%,.....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.104 TO FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT N0, 98 TO FACILITY OPERATING LICENSE NPF-52 DUKE POWER COMPANY. ET AL.
CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 1.0 Jntroduction By letter dated November 5, 1992, as supplemented on December 9 and 18, 1992, Duke Power Company (the licensee), submitted proposed changes to the Catawba Nuclear Station, Units 1 and 2 Technical Specifications (TS) in support of their plans to implement the new 10 CFR Part 20.
The December 9 and 18, 1992, letters provided clarifying information and corrections which were not outside the scope of the original Federal Reaister notice and did not change the initial proposed no significant hazards consideration determinatien.
The changes proposed by the licensee involve four items:
1.
Revise the liquid effluent concentration release rate limit.
2.
Revise the 10 CFR 20.106 section number to reflect the relocation of the old requirements to the new 10 CFR 20.1302.
3.
Revise the gaseous effluent release rate limit.
4.
Revise the TS BASES for the LIQUID HOLDUP TANK activity limit.
2.0 Evaluation The licensee has revised the TS to include wording that is consistent with the revised 10 CFR Part 20, Standards for Protection Aaainst 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 NRC staff's evaluation on item four regarding the bases for the liquid holdup tank activity limit was not completed and will be addressed by separate correspondence.
The proposed TS changes and evaluations follow:
1.
The licensee has proposed to revise the liquid effluent concentration release rate limit. This specification is being revised to read:
" Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times 10 CFR Part 20.1001 - 20.2401, Appendix B, Table 2, Column 2."
930119035> 930106 PDR ADOCK 05000413 P
. 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 Technical Specifications (TS) concerning radioactive effluents are contained in 10 CFR 50.36a. Under 10 CFR 50.36a, licensees are-required 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 Appendix I to 10 CFR Part 50 contains the(ALARA).For power reactors, 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 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 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 releases 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 11 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.
Since 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 as an assurance 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 Catawba Nuclear plant 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 given in Appendix I of 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 continuo to operate within the design objectives in Appendix I _of 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 of 10 CFR Part 50 and 40 CFR Part 190, f
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. 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, to apply at all times.
2.
The licensee has proposed to revise the TS containing the 10 CFR 20.106 requirements to read:
"Honitoring, sampilng, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302."
The licensee has proposed this change to reflect that the requirements in 10 CFR 20.106 are now located in the new 10 CFR 20.1302.
This change is administrative in nature to incorporate the corresponding new 10 CFR Part section number and is considered acceptable.
3.
The licensee has proposed to revise the gaseous effluent release rate limit.
This specification is being revised to read:
" 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 a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr 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 mrems/yr to any organ."
The licensee has proposed this change in order to retain operational flexibility 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 Technical Specifications (TS) concerning radioactive effluents are contained in 10 CFR 50.36a. Under 10 CFR 50.36a, licensees are required 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 ! to 10 CFR Part 50 contains the numerical guidance to meet the ALARA requirement. The dose values specified in Appendix ! of 10 CFR Part 50 are small percentages of the limits specified in 10 CFR 20.106 (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 the purposes of this TS, 10 CFR Part 20 is used as a source of reference values only.
These TS requirements allow operational flexibility, f
1
4 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 1 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 the Catawba Nuclear plant has demonstrated that their calculated maximum individual doses to a member of the public are mil percentages of the values given in.
Appendix I of 10 CFR Part 50.
Therefore, the use of the proposed TS will not have a negative impact on the ability to continue to operate within the design objectives in Appendix 1 of 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 ! of 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.
4.
The licensee proposed to revise the BASES for the TS on LIQUID HOLDUP TANKS.
The NRC staff's evaluation of this item is not complete and it is therefore not addressed in this evaluation.
This item will be addressed by separate correspondence.
Based on the above, with the exception of item four, the staff finds that the proposed changes to the licensee's Technical Specifications submittal to be acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ERVIRONMENTAL CONSIDERATION Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Reaister on January 6, 1993 (58 FR-588).
Accordingly, based upon the environmental' assessment, the Commission has determined that iss:'ance of the amendments will not have a significant effect on the quality of the tuman environment.
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5.0 CDMCLUSION 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:
Stephen Klementowicz Date: January 6, 1993 i
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20%6 January 13, 1993 Docket No. 50-285 MEMORANDUM FOR:
George T. Hubbard, Acting Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation FROM:
Steven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
SUBJECT:
FORTHCOMING MEETING WITH OHAHA PUBLIC POWER DISTRICT - FORT Call 10VN STATION DATE & TIME:
Wednesday, February 3, 1993 - 1:00 to 2:30 LOCATION:
One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Room 12 B 11 PURPOSE:
Discuss significant fort Calhoun Station issues such as PTS, PRA and power uprate and current status.
PARTICIPANTS *: LE QPfD T. Murley B. Jones J. Partlow W. Gates J. Roe S. Gambhir M. Virgilio R. Short G. Hubbard S. Bloom 1
l Steven D. Bloom, Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V l
Office of Nuclear Reactor Regulation cc:
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- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy," 43 Federal Reaister 28058, 6/28/78.
-.