ML20011F536
| ML20011F536 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/22/1990 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20011F537 | List: |
| References | |
| 4410-90-L-0012, 4410-90-L-12, NUDOCS 9003060232 | |
| Download: ML20011F536 (3) | |
Text
{{#Wiki_filter:-r,
- g t
s + d n,P nn Iva a 17057 0191 717 944 7621-TELEX 84 2386 Writer's Direct Dial Number: (717) 948-8400 February 22,- 1990 (, 4410-90-L-0012/0477P l
- US Nuclear Regulatory Commission' Washington,'DC 20555-Attention: Document Control Desk Three Mile Island Nuclear Station, Unit 2 (TMI-2)
- Operating License No. DPR-73 ~ Docket No. 50-320 Defueling Completion Report, Final Submittal
Dear Sirs:
s Attache'd is the fifth and final submittal of the Defueling Completion Report -(DCR)'.. Previous submittals were provided by GPU Nuclear letters ?4410-89-L-0070 dated July 5,1989; 4410-89-L-0078 dated August 18,.1989, J 4410-89-L-0102 dated October 9,1989; and 4410-89-L-0128 dated January.18, F 1990.' The. attachment provides an Executive Summary, a discussion of the residual i fuel: Quantities in the Reactor Vessel (Section 5.4), the results of i . criticality analyses performed for the remaining fuel (Section 5.5), an J assessment of major residual fuel deposits (Section 6.0), a historical review l L -of the; occupational exposure accumulated during defueling (Section 7.0), and a L discussion of the conclusions reached (Section 8.0). .Page changes incorporating minor corrections to previously sutmitted sections -of the DCR are also attached. Changes are annotated by change bars in the' margin.. These changed pages and the new material submitted herein are identified as Revision 4 to the initial submittal of the DCR. License Amendment No. 30 to the TMI-2 Technical Specifications defined three .j facility modes for the TMI-2 facility. The amendment also stated that at le_ast 60 days prior to transition to each successive facility mode, a report shall be submitted to the NRC providing the.necessary basis and justification for the transition. Specifically, the Technical Specifications reouire a detailed report prinr to transition from Mode 1 to Mode 2 affirming that: 90 O fDy3060232900ho$20 N I 2^ ADOCK 050 Pnn b GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
[~ Document Cbntrol Desk
- ' February 22, 1990 4410-90-L-0012 4
...T Page 2- / =1. The Reactor Vessel and Reactor Coolant System are defueled to the extent 4 3: reasonably achievable, 2. The possibility of criticality in the Reactor Building is pmeluded, and 3. There are no. canisters containing core material in the Reactor Building. In conjunction with issuance of License Amendment No. 30, the NRC granted GPU
- f Nuclear an exemption from 10 CFR 70.24 for the criticality monitoring reouirements in the TMI-2 Reactor Building (RB).
This action imposed the following mode transition provision: " Prior to transition to Mode 2, the licensee will provide a criticality analysis that will address each separate cuantity of residual fuel in each defined location. The criticality analysis will estimate the cuantity of fuel remaining, its location, its dispersion within the location, its physical form (i.e.,-film, finely fragmented, intact fuel pellets), its mobility, the presence of any mechanism that would contribute to the mobility of the material, the presence of any moderating or reflecting material, and its potential Tor a critical event. In this submittal the licensee must demonstrate that the cleanup has progressed far enough such that an inadvertent criticality is precluded..." The DCR' concludes that the TMI-2 facility has been oefueled to the extent reasonably achievable and demonstrates-that inadvertent. criticality has been- . precluded. It accuments compliance with the NRC mode transition reouirements - identified above and provides the basis for TMI-2 entering Mode. 2. Currently, GPU Nuclear is engaged in an NRC-sponsored Reactor Vessel Lower Head Sampling. Program. Some core debris (i.e., including fuel) has been removed as a result of this activity and other debris has been released from - confined spaces (e.g., during cutting of incore nozzles) to the bottom head. . As a result, -we will perform a Reactor Vessel'-(RV)- cleanup following the completion of the sampling program and prior ~ to RV draindown. However, completion of these activities is not expected to materially affect the . conditions reported in the DCR. Any fuel removed during this process would provide.for more stable, long-term facility conditions. Although some defueling canisters remain in the RB to support the -NRC-sponsored Reactor Vessel Lower Head Sampling Program and post-sampling program cleanup, these defueling canisters will be removed from the RB upon completion of these' activities. GPU Nuclear will inform the NRC when all defueling canisters have been removed. 1 I l l
ffs) ]l l"' y,X -i. -{. p rg i '-5 i ~ 0 . Document Control Desk l ::.9:- ' February 22, 1990 F. 4410-904.-0012 L-Page-3 7 X 'In accordance with the ' provisions of License Amenoment No. - 30, GPU Nuclear ~ ' intends-to-transition to TMI-2 Facility Mode 2 60 days hence. .j l Sincerely, e na:- 1"' 7/< 6 Q M. B. Roche Director,-TMI-2 'EDS/ emf . Attactinent ' . cc: W. T. Russell - Regional Aami_nistrator, Region I J. F. Stolz - Director, Plant Directorate I-A L. H. Thonus - Project Manager, TMI Site F. I. Young - Senior Resident Inspector, TMI s D E 4 r' h$ 1 i r----- -}}