ML19296A752
| ML19296A752 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 01/28/1980 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| Shared Package | |
| ML19296A753 | List: |
| References | |
| NUDOCS 8002190004 | |
| Download: ML19296A752 (5) | |
Text
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F JAit 2a 1999 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
Docket No. 70-1257
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Special Nuclear Material Exxon Nuclear Company
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License No. SNM-1227 2101 Horn Rapids Road
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Amendment No. 22 Richland, Washington 99352
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ORDER TO MODIFY LICENSE I
Exxon Nuclear Company of Richland, Washington ("the licensee") is the holder of Special Nuclear Material License No. SNM-1227 issued by the Nuclear Regulatory Commission ("the Commission").
The license authorizes the possession and use up to 10,000 kg of U-235 (15% enrichment) and 100 kg of plutonium of which at least 90 kg is in encapsulated form.
The licensee fabricates low-enriched uranium fuel for LWR's.
There is no plutonium work at the present time. The license is currently active pursuant to the timely renewal provisions of 10 CFR 70.33(b), pending completion of the environmental and safety review of the renewal application.
II On January 13,1977, t! 3 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 Cude of Federal Regulations
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(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 plants be limited so that no mencer 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.
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2 The fluclear Regulatory Commission, as the " Regulatory Agency" defined in 40 CFR 190, is responsiole for assuring that uranium fuel cycle plants licensed by the Commission meet the requiremants of the new environmental radiation protection standards. To assure compliance with 40 CFR 190, the license is being con,ditioned to limit the radioactivity in effluents. The limit on releases of radioactive effluents in this order reflects the Commission's policy to maintain releases as low as reasonably achievable (ALARA) pursuant to 10 CFR 20.l(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 annuii dose to the nearest resident and to an individual at the fenceline using current plant operational data on effluent releases and has used this information to set action levels for the facility.
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 dat.a submitted by the licensee.
2.
Reg. Guide 1.111 for atmospheric disparsion calculations or
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actual environmental monitoring results of radioactivity in
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3.
Reg. Guide '.109 for environmental dose pathways except that for the inhalation pathway, the dose conversion factors were generated using the ICRP Task Group Lung Model.
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It was shown from the staff dose calculations that the liquid effluent from this facility is not a significant pathway to man. Therefore, the staff has proposed an action level based solely on the total quarterly release of airborne effluents.
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-1227 is hereby amended to add the following conditions:
1.
If the radioactivity in plant gaseous effluents exceeds 50 uCi per calendar quarter, the licensee shall, within 30 days, prepare and submit to the Commission a report which identifies the caust 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.
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.
I The report or petition should be submitted to the Director, Office of Nuclear
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Material Safety and Safeguards with a copy to the Director of the Regional Office of Inspection and Enforcement.
4 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 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:
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1.
Whether the procedure described in Part II is reasonable.
2.
Whether this order should be sustained.
FOR THE tiUCLEAR REGULATORY COMt11SSI0ft
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Y Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety m
DISTRIBUTION:
Docket No. 70-1257 NMSS r/f FCUF r/f PDR SHO IE HQ (2)
JCatania BBrooks ACabell JPartlow JRobertson DWeiss WTCrow EYShum TRDecker RLStevenson WCooley, R:V TFCarter RECunningham RFonner WKreger JHickey LTyson
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