ML20138J020
| ML20138J020 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/24/1985 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| 0340A, 340A, 4410-85-L-0208, 4410-85-L-208, NUDOCS 8510290218 | |
| Download: ML20138J020 (3) | |
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GPU Nuclear Corporation Nuclear
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- r8o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number
(717) 948-8461 i
4410-85-L-0208 Doctrnent ID 0340A October 24, 1985 TMI t'rogram Office Atta: Dr. 8. J. Snyder Program Director US Nuclear Regulatory Commission f
Wasnington, DC 20555
Dear Dr. Snyder:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Commencement of TMI-2 Preliminary Defueling Operations The Early Defueling Safety Evaluation Report (SER), Revision 4, which was forwarded by GPU Nuclear letter 4410-85-L-0200, dated October 10, 1985, describes in detail the currently planned activities and supporting tooling and equipment for completion of the early stages of defueling of the TMI-2 reactor vessel. Based on the current state of readiness of the TMI-2 Project, the start of certain preliminary defueling activities, which are a prerequisite to the actual loading of core deuris into the defueling canisters, is imminent. In addition, the need exists to select core debris samples for analysis by INEL to further our knowledge of the condition of the damaged core. The purpose of this letter is to advise you that we plan to begin such activities during the week of October 28, 1985, (potentially, initial activity will begin as early as October 29th) and to define the limit of these activities in the context of the above referenced SER.
Except as specifically defined herein, defueling operations described in the Early Defueling SER will not commence until NRC approval of the Early Defueling SER and Defueling Canister Technical Evaluation Report (TER) nave been received by GPU Nuclear. For example, the planned activities will not include the installaticn of defueling canjsters in the reactor vessel, loading of canisters with core deoris or movement of fuel-loaded canisters to the canister storage rack 3.
As exceptions, the filter canisters currently install'ed in the DWCS will oe used in their intended 8510290219 h h 20 PDR ADOCA PDR GPU Nuclear Corporation i a subsidiary of the General Public Utilities Corporation O
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T Dr. B. J. Snyder October 24, 1985 4410-85-L-0208 mode as it is expected that the Reactor Vessel Loop portion of the DWCS (including the sidestream flow to the SDS) will begin full operation prior to the start of defueling activities, and a single filter canister will be emplaced within the Reactor Vessel for a brief period for the sole purpose of conducting a canister dewatering system test.
The preliminary defueling activities will be performed wholly within the reactor vessel and will consist of the segmentation and movement of core deoris (i.e., core alterations) necessary to permit full operation of the Canister Positioning System (CPS) as a prerequisite to fuel loading, and selection of samples needed for early transfer to INEL.
These activities may include the loading of small pieces of core debris into debris oaskets but will not include actual loading of fuel debris into fuel l
canisters. The reconfiguration of the core debris will be conducted in l
accordance with Section 6.2.2 of the TMI-2 Technical Specifications and I
will be bounded by the TM1-2 Criticality Analysis previously forwarded by GPU Nuclear letter 4410-84-L-0199, dated Novemoer 8, 1984. The handling of loads over the reactor vessel will be in accordance with the SER for Heavy Load Handling Over the Reactor Vessel.
l The above described operations will involve the use of defueling tooling
- including nydraulically operated tools - and equipment described in the Early Defueling SER, which is currently pending NRC approval. Operating procedures for these activities are subject to NRC approval, as appropriate. To the extent that these activities are bounded by existing defueling procedures, it is intended that those procedures will be utilized within the operating limits defined aDove. Therefore, provisional approval of Procedure 4200-OPS-3255.01 for the purpose of conducting the activities specified herein, is requested. In addition, prior to conducting operations using the hydraulically operated tools, we will provide the results of the tests of the borated hydraulic fluid to demonstrate its miscibility, compatability with the canister recombiner catalyst and stability as a homogeneous borated fluid.
Tne preliminary defueling operations will be supervised, most likely from the Command Center, by NRC-licensed Fuel Handling Senior Reactor Operators (FHSRO).
Actual loading of fuel into TMI-2 defueling canisters, planned to begin early in the month of November,1985, will require NRC' approval of the Canister Technical Evaluation Report (TER) and tne Early Defueling SER.
The movement of defueling canisters from the reactor vessel to the storage racks in either the deep erd of the Fuel Transfer Canal or in Fuel Pool 'A' is currently expected to begin by mid-November, 1985, and will require NRC approval of Revision 2 of the Heavy Load Handling SER.
i l
. Dr. B. J. Snyder
- October 24, 1985 f '
4410-8S-L-0208 GPU Nuclear will advise you of any changes to the plan and schedule t
described above.
Sincerely, l.
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1
' F. R. Standerf 4
Vice President / Director, TM1-2 FRS/JJB/eml l
Attacnment
. cc: Deputy Program Director - TMI Program Office, Dr. W. D. Travers 4
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