ML20008E510
| ML20008E510 | |
| Person / Time | |
|---|---|
| Site: | 07000036, 07001100 |
| Issue date: | 02/11/1981 |
| From: | Cunningham R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| Shared Package | |
| ML20008E502 | List: |
| References | |
| NUDOCS 8103090128 | |
| Download: ML20008E510 (6) | |
Text
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O UtilTED STATES OF AMERICA NUCLEAt REGULATORY CCMMISSICN In the Matter of
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Docket No. 70-1100
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Materials License Combustion Enginaering, Inc.
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No. SNM-1067 1000 Prospect Hill Road
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Windsor, Connecticut 06095
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CRDER TO MODIFY LICENSE I
Comcustion Engineering, Inc. of Windsor, Connecticut, ("the licensee") is j
the holder of Materials License No. SNM-1067 issued by the Nuclear Regulatory Commission ("the Commission"). The license authorizes the possession and use i
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of up to 20,500 kg of U (< 4.1% enrichment), 4,800 g of U (> a.1% anc
< 20% enrichment),10,IO0 kg of source material,138 g of plutonium in encapsulated form, and 160 pg of plutonium as analytical samcles.
The licensee facricates low-enriched ' uranium fuel for L'nRs.
The current license was renewea on January 30, t
1975, and is due to expire on January 31, 1981.
II Before issuance of a license to operate, staff review of the acclication determined tnat the licensee can ocerate the facility in a safe manner.
Nonetheless, based on the lessons learned from the accident at Three Mile
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Island and new perscectives on emergency preparedness and planning, the Commission has reevaluated the emergency preparedness requirements for its fuel cycle and materials licensees.
The Commission has decided that significant improvements need to be mace promptly to ensure that adequate onsite emergency resconse l
810gogg tss actions will be taken by licensees with major coerations in cases wnere, even though unif kely, potentia?ly serious radiation accidents could occur.
The operations licensed to be carried out pursuant to Materials License No. SNM-1067 appear to fall in this category and require the development of a more comorenensive onsite radiological contingency plan than previously submitted to the Commission for review.
Specifically, considerations are needed to ensure (1) that tne plant contains adequate engineered safety features and is otherwise designed to limit releases of radioactive materials and radiation exposures in the
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event of an accident, (2) that a cacability exists for measuring and assassing the significance of accidental releases of racioactive materials, (3) tnat appropriate emergency equipment and clanning are provided ansite to orotect workers against radiation hazards that mignt be encountered following an accident, (4) that notifications are made promotly to federal, state, and local government agencies, and (5) that necessary recovery actions are taken in a timely fashion to return the plant to a safe condition following an accident.
The information to be develoced and documented is described in the enclosed
" Standard Format and Content for Raciological Contingency Plans for Fuel Cycle and Materials Facilities" (Enclosure 1).
In summary, the information to be sucmitted to NRC for review incluces a (1) description of plant systems imcortant to safety; (2) characteri:ation of classes of credible e,ergencies that mignt occur; (3) description of radiological contingency measures for eacn class of emergency; (4) designation of authorities and responsibilities of key indivicuals and groucs emoloyed cy the licensee; and (5) a description of equipment and facilities designated for use curing radiation emergencies. The pian is to be l
. cirected toward mitigating the consecuences of raciological emergencies anc providing reasonable assurance that acprcpriate measures will be taken during an emergency to assure protection of the public and minimize adver:e environ-mental impacts.
In preparing the plan, consiceration should be given to a set of crecible accidents ranging from almost everyday occurrences of small conse-cuence througn highly imor:bable, but not imcossible, accicents sucn as tnose resulting from severe natunal phenomena, human error, and multiple equipment
'silures, anc sacotage.
Y III In addition to onsite radiological contingency planning, as discussed in Section II acave, offsite emergency response planning is also highly imcortant.
Offsite planning requirements for fuel cycle and materials facilities are being developec separately and will be c:nsidered in a preposed rulemaking to be published in the c: ming months. Within the framework of that rulemaking, i
NRC will carry out extensive coordination with state governments and tne Federal Emergency Management Agency (FEMA) concerning apolicable requirements.
IV The Commission believes that it is prudent and necessary to recuire the licensee to cevelop and sucmit within 180 days of the effective cate of this Orcer, or before, an onsite raciological contingency plan, as discussac in Section II above, acolicable to operations licensed pursuant to Materials License No. SNM-1067. Scen a plan can be developed and effectively implemented acart from offsite emergency response planning, wnica necessarily involves state and 1 cal government emergency planning actions.
The onsite raciciogical
. contingency plan is a necessary extension of protective actions taken by the licensee during normal operations. Such planning is essential to ensure that proper plans are made by the licensee to protect the public from accidents that could result from the licensed operations. A lessan learned from the Three Mile Island accident is that accidents thougnt to be hignly improbable can and will occur, and that proper emergency preparedne.ss is required to mitigate radiological consequences.
The reporting and record keecing part of this onsite radiological contin-gency plan is subject to clearance by the General Accounting Office. GA0 I
review ar.d clearance will not stay the effective date of this Order as regards the requirement that the licensee develop the plan. Unless savised to the contrary, GAO clearance will be effective within 45 days from tne date of this Orcer.
V Accordingly, pursuant to sections 161b and 161o of the Atomic Energy Act of 1c54, as amended, 540.41(e) of 10 CFR Part 40, 1570.32(a)(3), 70.32(b)(2),
and 70.32(b)(5) of 10 CFR Part 70, and $2.204 of 10 CFR Part 2, IT IS HERE3Y ORDERED THAT within 180 days of the effective date of this Order, the licensee shall submit:
1.
A radiological contingency plan in accordance with Enclosure 1 of this Orcer, " Standard Format and Content for Radiological Contingency Plans for Fuel Cycle and Matarials Facilities," and an apolication M
. for license amendment to incorporate sucn plan as a:provec as a condition of the license; or alternative 1v, 2.
An application for license amencment to recuce the possession limits for radioactive materials below those specified in 5nclosure 2 of this Order.
VI
- l ihe licensee or any person wnose interest may be affected by this Orcer may, within 20 days of the date of the Order, request a hearing with rescect to all or part of the Orcer. A request for a nearing shall be accressed to the Secretary of the Commission, U.S.N.R.C., Washington, D.C.
20555. A cocy of :ne hearing request sna11 also ce sent to the Executive Legal Director, U.S.N.R.C., Wasnington, D.C.
20555. If a persen other than the licensee requests a hearing, that person shall set forth with particularity the nature of his or her interest and the canner in which his or her interest may be affected by this Order in accordance with 10 CFR $2.714(a)(2) of the Commission's Rules of Practice.
If a hearing is requested by the licensee er a person wnc has an interest affected by this.Orcer, the Commission will issue an creer cesignating the time anc place of the hearing.
If no hearing is requested, this Order will bec:me effective 20 cays from the cate of the Order.
If a hearing is requested, tais Orcer will be; cme effective on the data specified in an creer made following the hearing.
6-VII If a hearing is held, the issue to be considered at the hearing shall be whether the licensee (1) shall submit a radiological contingency plan whien complies with Enclosure 1 of this Order, " Standard Format and Content for Radiological Contingency Plans for Fuel Cycle and Materials Facilities," or (2) if a plan is not submitted as required in Section V (1) of the Orcer, snould an acplication for a license amencment to reduce its possession limits for radioactive materials below those specified in Enclosure 2 of this Order be sucmitted.
FOR THE NUCLEAR REGULATCRY CCMMISSICN 4 -- 'IC.
9_
7 Richard E. Cunningham, Director Division of Fuel Cycle and Material Safety Dated at Silver Spring, Maryland this 11 th day of February,1981 a
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