ML19296A778
| ML19296A778 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 01/28/1980 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| Shared Package | |
| ML19296A779 | List: |
| References | |
| NUDOCS 8002190028 | |
| Download: ML19296A778 (5) | |
Text
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UNITED STATES OF AMERICA JAN 2 81980 NUCLEAR REGULATORY COMMISSION In the Matter of
)
Docket No. 70-1151'
)
Special Nuclear Material Westinghouse Electric Corp.
)
License No. SNM-1107 3 Gateway Center, P.O. Box 355
)
Amendment No. 4 Pittsburgh, Pennsylvania 15230
)
ORDEP TO MODIFY LICENSE I
Westinghouse Electric Corp. of Pittsburgh, Pennsylvania ("the licensee") is the holder of Special Nuclear Material License No. SNM-1107 issued by the Nuclear Regulatory Commission ("the Commission").
The license authorizes the possession and use of up to 50,000 kgs of U-235 (<4.15%
enrichment), 2500 kgs of U-235 (4.15% to 5.0%), and 750 kgs of plutonium
(<_6.6% Pu02) in encapsulated form. The licensee fabricates low-enriched uranium fuel for LWR's.
There is no plutonium work at the present time.
The current license was renewed on May 24, 1978, and will expire on May 31,1983.
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 plants 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 0 8
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 compliance 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 Commiss. ion'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 annual dose to the nearest resident and/or an individual at the fenceline using current average source terms 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 data submitted by the licensee.
2.
Reg. Guide 1.111 for atmospheric dispersion calculations or resul's of environmental monitoring for radioactivity in air.
t 3.
Reg. Guide 1.109 for environmental dose pathways except that for the inhalation pathway, the dose conversion factors were 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 man. Therefore, the staff has proposed an action level based solely on the total quarterly releases of airborne ef fl uents.
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-1107 is hereby amended to add the following conditions:
1.
If the radioactivity in plant gaseous effluents exceeds 1500 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 imediate steps to reduce. emissions se as to comply with 40 CFR 190.10. As provided in 40 CFR 190.11, the licensee may petition the Nuclear Regulatory Comission 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.
The licensee may within twenty (2L) 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.
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 Inspection and Enforcement.
4 In the event a hearing is requested, the amendment will become effective on a date specified in an order made followir.g the hearing.
In the event of a hearing, 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 I
$0 Richard E. Cunningha[ Director Division of Fuel Cycle and Material Safety 9
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