ML20132C564
| ML20132C564 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/26/1985 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| 0296A, 296A, 4410-85-L-0160, 4410-85-L-160, 6211-85-0580, 6211-85-580, NUDOCS 8507300367 | |
| Download: ML20132C564 (3) | |
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b GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8461 6211-85-0580 4410-85-L-0160 Document ID 0296A July 26,1985 TMI Program Office Attn: Dr. B. J. Snyder Program Director US Nuclear Regulatory Commission Washington, DC 20555
Dear Dr. Snyder:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Fuel Handling Senior Reactor Operator Training On July 17, 1985, a phone conversation was held between Dr. W. Travers and Mr. J. Buzy of the NRC and Mr. S. Newton of my staff concerning the Fuel Handling Senior Reactor Operator (FHSRO) Training Program. During this conversation, the NRC requested specific information to aid them in their review of the FHSRO Trair51ng Program. The attachment to this letter contains the NRC requests for information and the GPU Nuclear responses. This information, provided in support of the NRC's on-going review of the FHSRO Training Program, supplements the original submittal of January 14, 1985.
8507300367 850726 9
ADOCK0500gO DR rlI GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
-4 Dr. B. J. Snyder July 26,1985 4410-85-L-0160 If there are any questions regarding the responses, please contact Mr. B. Leonard, Operator Training Manager, at (717) 948-8046.
Sincerely, f
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i F. R. Standerfer Vice President / Director, TMI-2 FRS/JCA/eml Attachment cc: Operator Licensing Branch - Division of Human Factors, Mr. B. A. Boger Section Chief - Reactor Projects Section 1C, Mr. R. A. Keller Chief - Projects Branch I, Mr. H. B. Kister Regional Administrator - Offices of I&E, Dr. T. E. Murlef Depo' Program Director - TMI Program Office, Dr. W. D. Travers 1
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ATTACHMENT (4410-85-L-0160)
TMI-2 Fuel Handling Senior Reactor Operator Training Program 1.
Comment:
Explain the rationale behind the program prerequisite of three years experience in operations or support of operations at a nuclear power plant in light of the requirement for four years of responsible power plant experience established in Section I. A.2.1 of NUREG 0737.
Response: The regular TMI-2 Senior Reactor Operator (SRO) Training Program meets the four year power plant experience requirement of NUREG 0737. The FHSRO position is significantly reduced in scope and responsibility from that of the SRO such that a lesser experience prerequisite, which is consistent with that of a Reactor Operator (RO), is both justifiable and logical.
However, the FHSRO experience requirement is more stringent than that of an RO in that there is no provision for substitution of experience by academic or related technical training. Incidentally, all the current FHSRO candidates meet the four year power plant experience requirement of Section I.A.2.1 of NUREG 0737.
2.
Comment:
Please describe the length and content of on-shift training.
Response: The programmatic requirement for FHSRO candidates t3 serve as an extra man on-shift is thirty days. This on-shift requirement is compatible with that for the normal SRO upgrade program. In actuality, the time allotted to complete the initial On-the-Job Training (0JT) section of the program, as detailed in the program description previously submitted, was approximately two months. This portion of the OJT consisted of the candidates preparing for and obtaining checkouts on appropriate administrative procedures (including switching and tagging), radiological cont.rols procedures, plant systems interfacing with defueling activities and emergency and abnormal procedures.
As the actual defueling systems have been developed, additional OJi has been developed fur the following subject areas:
Coordination Center Early Defueling Fines / Debris Vacuuming System Defueling Water Clearup System Long Handled Tools and Auxiliary Equipment Service and Jib Cranes Canister Handling Bridge and Transfer Systems Canister Positioning System Defueling Viewing System In-Vessel Dewatering System Shielded Work Platform Control Syr.tems
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s ATTACHMENT (4410-85-L-0160)
The final portion of this additional 0]T is still in progress and it is anticipated that the time frame for its accomplishment is approximately three weeks from the date of this letter, including mock-up training on the Defueling Test Assembly.
Additionally, various FHSRO candidates have been involved in the development and vendor testing of much of the special defueling equipment (e.g., the shielded work platform, the fuel handling bridge, and the debris vacuum system).
Finally, the FHSR0 candidates and the currently existing SRO's have participated in three days of training at Pennsylvania State University's Braezeale Reactor. This training is discussed in more detail below.
3.
Comment:
How does the training program address requirement A.2.c.3 from Section I.A.2.1 of NUREG 0737 so as to provide increased emphasis on both reactor and plant transients?
Response: The OJT training on applicable abnormal and emergency procedures addresses this area to some degree. However, the training at Pennsylvania State University's Braezeale Reactor was specifically designed to address possible transients involving the reactor core in its present state. Five experiments were conducted to simulate conditions for the following topics:
1.
Criticality safety concerns at a high baron concentration with a controlled deboration 2.
Reactor response during a fuel collapse 3.
Movement of fuel within the vessel 4.
Loading of fuel fragments into a canister 5.
Draining of the reactor vessel The training afforded at the Braezeale Reactor at Pennsylvania State University allows for in-depth reactor transient response for a degraded core. Coupling reactor theory classroom instruction with criticality calculational instruction, as well as " hands on" experience afforded by the Defueling Test Assembly, has provided the FHSRO candidate a superior knowledge of anticipated reactor transient response.
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