ML20038B309
| ML20038B309 | |
| Person / Time | |
|---|---|
| Site: | 07000572 |
| Issue date: | 11/17/1981 |
| From: | Miller V NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Schimmel R MONSANTO RESEARCH CORP. |
| References | |
| NUDOCS 8112070582 | |
| Download: ML20038B309 (4) | |
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'V0V Docket File No. 70-0572 I 7 L%1 PDR FC Central File
..i RGPage SHO Monsanto Research Corporation FDFisher OELD Dayton Laboratory VLMiller SBurns, OELD ATTN: Mr. Robert L. Schimmel DDecker Manager Engineered Products J ong 1515 Nichols Road ERE3S Licensee Folder P. O. Box 8, Station B IE Headquarters Dayton, Ohio 45407 IE Regional Office ERESS R/F Gentlemen:
NMSS R/F We have completed our pre-acceptance review of the radiological contingency plan that you submitted on August 20, 1981, for the Monsanto Research Corporation's Dayton Laboratory (License No. SNM-567). Our review has revealed some needed changes in the content and format of the infomation submitted. These are described in the enclosure.
You are requested to send us additional infomation concerning these matters by December 12, 1981. Please submit the indicated information as properly numbered replacement or additional pages suitable for insertion into your plan. The infomation should be prepared in accordance with the " Standard Fomat and Content for Radiological Contingency Plans for Fuel Cycle and Materials Facilities," which was enclosed with the February ll,1981, Order.
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OFFICIAL RECORD COPY
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Enclosure Staff Comments From Pre-Acceptance Review Of the Monsanto Research Corporation Radiological Contingency Plan Submittal Section 2.1.1 A description is to be provided of the manner in which process systems are intended to provide for the maintenance of primary confinement, control of conventional process hazards, and control of effluents in the event of abnormal occurrences.
The description should include the manner in which the safety features are activated.
If there are no automatically controlled safety features, the appropriate operating procedures for activation of safety features should be incluied. The performance of safety systems such as glove boxes or process boxlines should be discussed.
The description is to include the systems' expected capability to contain radioactivity and to maintain reduced pressure during accident conditions. A discussion should be included of at least the operating procedures necessary to ensure that processing operations can be safely terminated following an accident.
The plan indicates that subiects such as " shutdowns", automatic safety equipment to accomplish a shutdown and performance of equipment for maintaining a shut-down are not appropriate since the licensee does not operate a nuclear power reactor and the majority of operations to fabricate the sources are manually controlled with few automatic operations.
In the context of this review,
" shutdown" refers to the rapid, orderly cessation of process operations and subsequent securing of licensed material in a planned, controlled manner.
The
" Standard Review Plan (NUREG-0810)" calls for a description of the need for automatic or manual systems to provide a safe shutdown. The requirerrent to discuss safe shutdown provisions, either automatic or manual, are appropriate for your facility and are to be addressed.
Section 2.1.3.1.2 The location of the neighboring activities described in this section should be indicated on graphics in Chapter 1.
Activities at the licensee's facility which are in proximity to those involved in storing or processing radioactive materials are to be addressed to the extent that accidents such as fire, explosion and others impact the licensed activity.
i Section 2.1.4 Performance goals for assuring continued proper performance of plant engineered systems important to safety through monitoring, auditing, and appropriate maintenance operations should be provided.
For example, per-formance goals for maintenance and surveillance procedures involving ventilation, alarm and confinement systems should be addressed.
To some extent this requirement is met by the discussion in Sections 1.2.3 and 2.2.4 but should be repeated here.
Section 2.2 The plan indicates that the licensed activities rely heavily on manual control of the various manufacturing processes instead of automatically actuated engineered safety systems.
A description of the administrative controls to accomplish the performance goals of Section 2.1 shoul-be included.
More information on the handling of lithium in a cell should be given including the locations where it is used as well as the chemical form and maximum amount expected to be in one cell at a time.
Section 3.3.1 The descriptions of accident scenarios presented in this section are to include analytical treatments of the accident assessments,imilar to those which were given in Sections 3.3.2 and 3.3.3.
Sections 3.2.3 and 3.2.4 The NRC is to be notified promptly for the Site Area and General Emergency classes. See comments for Section 4.3.6.
Section 4.3.6 The correct address for the appropriate regional office is:
US.luclear Regulatory Commission Region III Glen Ellyn, Illinois 60137 Section 5.2 The description of the actions to be taken in assessing the extent of the problem is not adequately described.
The procedural steps necessary to gather and transmit information as well as the methodology and parameters to be used in calculating consequences are to be provided. A description of the staff designated to analyze consequences of accidents is to be provided including assignments and responsibilities.
Section 5.3 The corrective actions are to be identified for each cla;s and type of accident.
Procedures for initiating corrective actions are to include identification of the responsible individuals and/or teams.
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Section 5.6 i
Arrangements for the transport of injured and possibly radiologically contaminated personnel should be described as in Section 5.7.
A letter of agreeement between the licensee and transporting and medical facilities
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