ML20057A145
| ML20057A145 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/27/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A142 | List: |
| References | |
| NUDOCS 9309130112 | |
| Download: ML20057A145 (3) | |
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NUCLEAR REGULATORY COMMISSION
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wAsmucTon. o.c. mswon SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. NPF-47 GULF STATES UTILITIES COMPANY RIVER BEND STATION. UNIT 1 DOCKET NO. 50-458
1.0 INTRODUCTION
By letter dated July 2,1993, Gulf States Utilities (GSU) (the licensee) requested an amendment to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1.
The proposed amendment would revise Technical Specifications (TS) 3.3.7.10 " Radioactive Liquid Effluent Monitoring i
i Instrumentation," TS 3.3.7.11, " Radioactive Gaseous Effluent Monitoring Instrumentation," TS Table Notation c to Table 4.11.1.1.1-1, " Radioactive Waste Sampling and Analysis Program," TS 3.11.1.4, " Liquid Holding Tanks,"
Table Notation b to Table 4.11.2.1.2-1, " Radioactive Gaseous Waste Sampling and Analysis Program," TS 3.12.1, " Monitoring Program," Table Notation a to Table 3.12.1-1, " Radiological Environmental Monitoring Program," TS 3.12.2,
" Land Use Census," TS 6.9.1.8, " Semiannual Effluent Release Report," TS 6.13,
" Process Control Program," TS 6.14, "Offsite Dose Control Manual," TS 6.15,
" Major Changes Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems," to change the frequency for submittal of the Radioactive Effluent Release Reports from semiannual to annual. Additionally, TS 6.9.1.8,
" Semiannual Effluent Release Report," is also being revised to extend the preparation period from 60 days to 90 days and change the listed reference for acceptable calculation methods from Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants." An editorial correction was made to include a change to the reference of the semi-annual radioactive effluent report in the Index.
This change was discussed with your staff and was found to be acceptable, j
Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation are currently submitted within 60 days after January 1 and July I of each year. The report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21,
" Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and i
Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Pcwer Plants," Revision 1, June 1974, with data 1
j summarized on a quarterly basis as well as a summary of hourly meteorological data collected over the previous year (January I report only), and an l
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assessment of the radiation doses from radioactive liquid and gaseous i
effluents to members of the public due to activities inside the site boundary during the report period. All assumptions used involving these assessments (i.e., specific activity, exposure time and location) are included in these reports. The assessment of radiation doses is performed in accordance with the methodology and parameters of the offsite dose calculation manual (ODCM).
The Semiannual Radioactive Effluent Release Report submitted 60 days after
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January I of each year also includes an assessment of radiation doses to the i
likely most-exposed member of the public from reactor releases and other i
nearby uranium fuel cycle sources (including doses from primary effluent 1
pathways and direct radiation) for the previous calendar year to show conformai & with 40 CFR Part 190, " Environmental Radiation Protection i
Standards for Nuclear Power Operation."
The reports also include a list and description of unplanned releases of radioactive materials in gaseous and liquid effluents from the site to unrestricted areas made during the reporting period and any changes made during the reporting period to the process control program (PCP) and to the ODCM, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census.
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2.0 EVALUATION Title 10, Code of Federal Regulations, Section 50.36a, " Technical Specifications on Effluents from Nuclear Power Reactors," was changed effective October 1, 1992 to require that a report to the Commission specifying the quantity of each of the principle radionuclides released to i
unrestricted areas during the previous twelve months should be prepared and submitted. The new regulation also requires that the time between submissions of the report must be no longer than twelve months.
Previously, 10 CFR 50.36a required these reports be submitted semiannually and within sixty days after January I and July 1 of each year.
TS 3.3.7.10, TS 3.3.7.11, Table Notation c to Table 4.11.1.1.1-1, TS 3.11.1.4, Table Notation b to Table 4.11.2.1.2-1, TS 3.12.1, Table Notation a to Table 3.12.1-1, TS 3.12.2, TS 6.9.1.8, TS 6.13.2, TS 6.14.2, and TS 6.15.1 have been revised to refer to the annual Radioactive Effluent Release Report rather than the semiannual Radioactive Effluent Release Report. Since the TS changes are consistent with the new requirements in 10 CFR 50.36a, the staff finds the s
1 above changes acceptable. TS 6.9.1.8 has also been changed to require that the Radioactive Effluent Release Report cover the operation of the unit during i
the previous calendar year and to require the submittal of this report within ninety days after January 1 of each year. The extension from 60 days to 90 days reduces the possibility of having to file an addendum due to composite data and is acceptable.
Additionally, TS 6.9.1.8 has been revised to change the reference for acceptable methods for calculating the dose from liquid and gaseous effluents from Regulatory Guide 1.109, Rev.1, October 1977 to NUREG 0133, Rev. O, October 1978. Since the methods for calculating dose in the NUREG are i
consistent with those in the Regulatory Guide and the methods in both documents have been found acceptable to the staff previously, the staff finds the change acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official i
had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
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The amendment relates to changes in 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 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
i The Consnission 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 pcblic.
Principal Contributor: Edward T. Baker, PDIV-2/NRR j
Date: August 27, 1993 i
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