ML20214P956
| ML20214P956 | |
| Person / Time | |
|---|---|
| Issue date: | 08/29/1986 |
| From: | Raglin K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20214P901 | List: |
| References | |
| NUDOCS 8612040441 | |
| Download: ML20214P956 (1) | |
Text
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UNITED STATES g
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j TECHNICAL TRAIN 4NG CENTER OSSORNE OFFICE CENTER, SUITE 2D0
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%,, *... * /g CHATTANOOGA, TN 37411 Aus 29 5 Views of Kenneth A. Raglin on DP0 dated 8/27/86 I have spoken with Mr. Evans to explore and probe his' views 6n this differing professional opinion. His concern is that the BWR technology training program at the TIC is oriented too heavily toward the BWR/6 design. His unwritten but orally communicated concern is that the simulator control panels used in TTC reactor technology training should so closely resemble those of most of the operating BWR's that essentially no control room familiarization is required on the part of inspectors who have been through the training pipeline.
The Reactor Inspector training program, outlined in IE Manual Chapter 1245 does not rely exclusively on technology training in the particular vendor design. It has never been the intent that students who complete the TTC BWR technology training program be able to immediately conduct inspections of safety-related equipment at reactor facilities without further effort on the part of the both the individual and the region to which he is assigned. The reactor technology training is only part of the process by which NRC inspectors become certifind to conduct independent inspections through the Regional Qualification Journal Program. Site specific familiarization on the part of NRC inspectors will always be required since no two units are the same.
In the specific case of BWR technology training, use of the BWR/6 as a curriculum base leads to much more effective technology training of reactor inspectors because of the smooth integration of classroom, simulator, and engineering model training. The acquisition of both an on-site simulator and an en-site engineering model have opened new dimensions in the BWR technology curriculum. The curriculum, as it presently exists in contrast with the previous curriculum, provides the inspector with a much better understanding of a generic BWR design, allowing him to cope with a broader spectrum of situations in the field. I concur with Mr. Roessler's views and particularly endorse the concept that the reactor technology training is designed to provide the inspector with a sound technical background which then gives the inspector tools to use in his job.
I consider that no further action is required in response to this differing professional opinion.
Should potentially significant areas of weakness in the technical training program be identified, they will be evaluated and incorporated into the curriculum if appropriate.
Kenneth A. Raglin, Direct
)r Technical Training Centat, DQAVT, OIE 8612040441 861128 PDR ORO NIEDPDR l
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