IR 05000289/1986018
| ML20215A948 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/05/1986 |
| From: | Anderson C, Krasopoulos A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20215A916 | List: |
| References | |
| 50-289-86-18-MM, SP, NUDOCS 8610060298 | |
| Download: ML20215A948 (3) | |
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. V U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
86-18 Docket No.
50-289 License No. DPR-50 Priority Category C Licensee: GPU Nucl_ ear Corporation P. O. 86x 480 Middletown, Pennsylvania 17057 Facility Name: Three Mile Island 1 Meeting At: King of Prussia, PA Meeting Conducted: August 12, 1986 Prepared By: -l [[ A~ K/a po s R'eactor Engineer, DRS Id e . Approved By: ,7 . vm
N C. J! Anderson, Chief, Plant Systems Section ~dafe
Meeting Summary: Management meeting at NRC Region I on August 12, 1986 to discuss fire protection related findings identified in Inspection Reports 86-01 and 86-05.
l The items discussed were the violation identified in Report 86-01 which was contested by the licensee and the training of the fire brigade. The adequacy , and realism of fire drills and fire fighting gear were also discussed. The licensee presented their position relative to these items and made commitments to transmit a letter to NRC identifying the change in the training program that address these concerns.
. O 8610060298 860923 PDR ADOCK 05000289 o PDR L -
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. ' - . ! DETAILS 1.
Participants 1.1 GPU Nuclear Corporation (GPUN) R. J. Toole, Operations and Maintenance Director 0. Shalikashvili, Plant Training Manager C. W. Smyth, Licensing Manager S. M. Otto, Licensing Engineer D. Laudermilch, Fire Protection Training Supervisor T. A. O'Connor, Lead Fire Protection Engineer R. J. McGoey, Licensing Manager 1.2 Nuclear Regulatory Commission (NRC) S. D. Ebneter, Director, Division of Reactor Safety W. V. Johnston, Deputy Director, Division of Reactor Safety J. Durr, Chief, Engineering Program Branch A. R. Blough, Chief, Reactor Projects Section IA 2.
Purpose i - This management meeting was held at the request of NRC Region I to discuss the violation identified in Inspection Report 86-01 and clarification of the licensee's position.
Since there were several other findings in the area of fire brigade training, characterized as Unresolved Items, the NRC Regional management , questioned the adequacy of the licensee's fire brigade training program.
3.
Presentation and Discussion Following the initial introductions, the conference was opened by the Director of the Division of Reactor Safety, Mr. S. Ebneter. The NRC management conveyed to the licensee concerns about the quality of training given to the fire brigade.
The primary concern is that fire brigade members are instructed to respond to drills and fires without protective equipment such as turnout coats, firefighter helmets, and respiratory protection, unless they pass by the firefighters locker on the way to the fire. Also, when a drill is announced not only the assigned brigade members respond, but, anyone who wishes to attend may attend.
Fire fighters maintain their qualification by partici-pating in drills and drills designed for five to eight firefighters can not be effective when fifteen to twenty or more firefighters respond.
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t .. , The' licensee presented a detailed description of the TMI fire program, the additional equipment and training beyond requirements and the implementa-tion of the program. The licensee's response to the concerns was that they believe that it is better to respond to the fire before it fully develops and that is the reason for not requiring the.firefighters to be dressed in turnout. gear. The licensee, however, agreed to review this procedure and require some members of the brigade to respond with the proper gear. With regard to drill participation by too many firefighters, the licensee stated that only firefighters who are actively participating in drills are given credit for the drill.
The licensee diso stated that the improvements to the brigade training program will be documented in a letter to the NRC identifying these changes. As mutually agreed, the Region will not reply to the response to the violation until this letter is received and its contents evaluated.
4.
Concluding Statements The Director of the Division of Reactor Safety thanked the licensee for i their presentation and stated that the information presented would be considered in the resolution of the items identified as unresolved.
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