ML19296A824
| ML19296A824 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 01/28/1980 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | BABCOCK & WILCOX CO. |
| Shared Package | |
| ML19296A825 | List: |
| References | |
| NUDOCS 8002190088 | |
| Download: ML19296A824 (5) | |
Text
I elo N 3 999 UNITED STATES OF AMERICA NUCLEAR REG'JLATORY C0t" ISSION In the Matter of
)
Docket No. 70-1201
)
Materiais License No. SNM-1168 Batcock & Wilcox Co.
)
Amendment No. 12 P.O. Box 1260
)
Lynchburg, Virginia 24505
)
ORDER TO V0DIFY LICENSE I
Babcock & 'dilcox Co. of Lynchburg, Virgiria ("the licensee") is the holder of Mater'als License No. SNM-ll68 issued by the Nuclear Regulatory Conmiission ("the Commission").
The license authorizes the possession and use of up to 20,000 kgs of U-235 (<4.05% enrichment), 10,000 kgs natural U or depleted U, and other small quantities of isotopas.
The licensee fabricates low-enriched uranium fuel for LWR's.
The current license was issued on July 29, 1976, and is cae to expire on August 31, 1981.
II On January 13, 1977, the Environmental P otection Agency issued retjulations set:ing forth environmental radiauon protection standards for the uranium fuel cycle.
Thesc 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 Decemoer 1,1979.
In essence, the regulations require that radioactivity in planned effluent releases, radon and its daugnters 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.
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2 The fluclear 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 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 regulations, order or license condition.
The i1RC staff has calculated the average annual dose ta the nearest resident and/or the fenceline using current average source terms and has used this infor.ation to set action levels for the facility. These calculations wert 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 e.tcept that for the inhalation oathway, 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 from this facility is not a significant pathway to man. Therefore, the staff has proposej an action level only on the total quarterly release of airborne ef fluents.
3 III Accordingly, in orcar to assure complianca with Title 40, Code of Federal Regulations, Part 190 and pursuant to Title 10, Code of Federal Regulations, Part; 20 and 70, Materials License w. SNM-ll68 is hereby amended to add the folicwing conditions:
1.
If the racicactivity in plant gaseous effluents exceeds 10 pCi per calendar ;.;arter, the licensee snall, within 30 days, prepare and submit to :ne Commission 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 :escribes the changes in carameters and includes an estimata of the resultant change in dose commitment.I 2.
In the wen: that the calculated cose 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 redu:a e-issicns so as to comply vith a0 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 scecified in 40 CFR 190.10.
The licensee may within twenty (20) days of the date of this notice of amendment request a nearing. The amendment will become effective on the expiration of the period during which a hearing may be requested.
1The 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 anc Enforcement.
4 In the event a hearing is demanded, the amandment will bec:ce effective on a date specified in an order made folicwing the hearing.
In the event a hearing is requested, the issues to be considered 2: such a hearing shall be:
1.
'4hether the procedure described in Part II is reasonable.
9 2.
'4hether this order should be sustainea.
FOR THE NUCLEAR REGUL 7ORY C0?' MISSION O : 4~/
(
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c Richard E. Cunningham, ;irector Division of Fuel Cycle and Material Safety
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GCoryell, R:II TFCarter RECunningham RFonner WKreger JHickey LTyson i
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