ML19296A769
| ML19296A769 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 01/28/1980 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19296A770 | List: |
| References | |
| NUDOCS 8002190020 | |
| Download: ML19296A769 (6) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY C0!HISSION In the Mat.ter of '
)
Docket No. 70-1113 Sp2cial Nuclear Material 1
License No. SNM-1097 General Electric Company P.O. Box 780
)
Amendment No. 11 Wilmington, North Carolina 28401
)
ORDER TO MODIFY LICENSE I
General Electric Company of Wilmington, North Grolina ("the licensee")
is the holder of Special Nuclear Material License No. SNM-1097. issued by the Nuclear Regulatory Commission ("the Commission").
The license authorizes the possession and use of up to 50,000 kgs of U-235 and 7 grams of plutonium in encapsulated form.
The licensee fabricates low-enriched uranium fuel for LWR's.
The current license was renewed on May 24, 1976, and will expire May 31,1981.
II On January 13, 1977, the Environmental Protection Agency issued regulations setting forth environmental radiation protection standards for the uranium fuel cycle.
These regulations are given in Title 40, Chapter 1, subchapter F, Part 190, of the Code of Federal Regulations (40 CFR 190), and for uranium fuel cycle plants (except for uranium mills) became effective on December 1,1979.
In essence, the regulations require that radioactivity in planned effluent releases, radon and its daughters excepted, from fuel cycle plant ^ be limited so that no member of the public will receive an annual dose equivalent of more than 25 millirems to the whole body, 75 millirems to the thyroid or 25 millirems to any other organ.
8002190 h
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,i 2
The Nuclear-Regulatory Commission, as the " Regulatory Agency" defined in 40 CFR 190, is responsible for assuring that uranium fuel cycle plants licensed by the Commission meet the requirements of the new environmental radiation protection standards.
To assure compli..nce with 40 CFR 190, each license is being conditioned to limit the radioactivity in effluents. The limits on releases of radioactive effluents in this order reflect the Commission's policy to main *,ain releases as ' low as reasonably achievable (ALARA) pursuant to 1) CFR 20.1(c) and any other requirement to implement an ALARA program whether imposed by regulation; order or license condition.
The NRC staff has calculated the average annual and quarterly releases which would allow the facility to remain in complianr.e with the standards. These calculations were performed using the following information and methods:
(A copy of the report of the calculations is attached.)
1.
The most current plant operational and release data submitted by the licensee.
2.
Reg. Guide 1.111 for atmospheric dispersion calculations or actual environmental monitoring results of radioactivity in air.
3.
Reg. Guide 1.109 for environmental dose pathways except that for the inhalation pathway, the dose conversion factors are generated using the ICRP Task Group Lung Model.
It was shown from the staff dose calculations that the liquid effluent is not a significant pathway to nan.
Therefore, the staff has proposed action levels based solely on the total quarterly releases of airborne effluents.
i.
3 III Accordingly, in order to assure compliance with Title 40, Code of Federal Regulations, Part 190 and pursuant to Title 10, Code of Federal Regulations,.Part 70 Special Nuclear Material License No. SNM-1097 is hereby amended to add the following conditions:
1.
If the radioactivity in plant gaseous effluents exceeds 1250 pCi per calendar quarter, the licensee shall, within 30 days, prepare and submit to the Comission a report which identifies the cause for exceeding the limit and the corrective actions to be taken by the licensee to reduce release rates.I If the parameters important to a dose assessment change, a report shall be submitted within 30 days which describes the changes in parameters and includes an estimate of the resultant change in dose commitment.I 2.
In the event that the calculated dose to any member of the public in any consecutive 12-month period is about to exceed the limits specified in 40 CFR 190.10, the licensee shall take immediate steps to reduce emissions so as to comply with 40 CFR 190.10. As provided in 40 CFR 190.11, the licensee may petition the Nuclear Regulatory Commission for a variance from the requirements of 40 CFR 190.10.
If a petition for a variance is anticipated, the licensee shall submit the request at least 90 days prior to exceeding the limits specified in 40 CFR 190.10.
3.
Air sampling stations shall be installed and operated in the prevailing wind directions, i.e., N, S, SW and NE (location should I The report or petition should be submitted to the Director, Office of Nuclear Material Safety and Safeguards with a copy to the Director of the Regional Office of the Office of Inspection and Enforcement.
4 be near the fenceline). Air samples shall be collected continuously and in addition to the gross-alpha analysis, the samples at each location shall be composited and analyzed on a monthly basis for uranium isotopes with an analytical sensitivity of at least 10-16 pCi/ml.
- 4. If the results of the sampling program indicate an airborne uranium concentration of greater than 3.45 x 10-15 uCi/ml, the licensee shall, within 30 days, institute an air sampling program at the site boundary in the direction of the nearest resident to determine the particle size distribution of radioactive material with a cascade impactor of multiple stages covering non-respirable and respirable particle size ranger. The particle size distribution -
analysis may be performed on a semi-annual basis.
- 5. Samples taken at the station in the southern location, shall be composited quarterly and analyzed for uranium solubility.
The solubility analysis shall follow the methodology and procedures 2
established by Battelle Pacific Northwest Laboratories ' or an equivalent method acceptable to the NRC.
If a laboratory other than BNWL is used for the analysis, the licensee shall provide the NRC with a split sample so that the NRC can perform a verification analysis.
The licensee may, within twenty (20) days of the date of this notice of amendment, request a hearing. 'The amendment will become effective on the 2 Solubility Classification of Airborne Products from Uranium Ores and Tailings Piles - D. R. Kalkwarf, BNWL, November 1978.
3Second Quarterly Report on Solubility Classification of Airborne Products from LWR-Fuel Plants - D'.. R. Kalkwarf, BNWL, October 15, 1979.
5 expiration of the period during which a hearing may be requested.. In the event a hearing is demanded, the amendment will become effective on a date specified in an order made following the hearing.
In the event a hearing is requested, the issues to be considered at such a hearing shall be:
1.
Whether the procedure described in Part II is reasonable.
2.
Whether this order should be sustained.
FOR THE NUCLEAR REGULATORY COMMISSION Y
Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety e
DISTRIBUTION:
Docket No. 70-1113 NMSS r/f FCUF r/f PDR SHO IE HQ (2)
JCatania BBrooks ACabe11 JPartlow JRobertson DWeiss WTCrow EYShum TRDecker RLStevenson JKahle, R:II TFCarter s
RECunningham RFonner WKreger JHickey LTyson
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