ML20207M226
| ML20207M226 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1988 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8810180187 | |
| Download: ML20207M226 (2) | |
Text
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o OPU Nuclear Corporation f9 g
g7 Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct C'lai Number:
(717) 948-8461 September 30,1988 4410-88-L-0162/0356P US Nuclear Regulatory Comission Attn: Document Control Desk Washiryton, DC 20555
Dear Sirs:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No f0-320 StN Accountability By tRC letter dated October 17, 1985, GPU Nuclear was granted exem tion from certain recuirements for periodic inventory and reporting of special ruclear material (SPN) balance for Three Mile Island Unit 2 (TMI-2). As a condition of the exemption, GPU Nuclear is required to conduct an assessment of the StN remaining at TMI-2 following the completion of the defueling ef fort.
Thi a assessment is referred to in the exemption as the "post-defueling survey."
GPU Nuclear has begun the post-defueling survey by corducting assessments in those areas and components for which no further defueling is planned.
Based on an infomal understarding between GPU Nuclear and the PEC TMI Cleanup Prnject Directorate, GPU Nuclear will provide the NRC a copy of the results of eacn post-def ueling survey for information.
In addition, for those surve/s which report residual StN ouantities greater than 1 kilogram, GPU Nucleai will solicit NRC review ard comment as a means of providing independent verifiestion of the technical adeouacy of each assessnent.
The Post-Defueling Survey Report (PGSR) docunents the GPU Nuclear assessment of the amount of t'sidual StN and describes the methodology utilized to determine the cuantity of SPN in each case. Due to the corrplex structure of the comenents to be surveyed, the assessment of the residual StN may utilize a combination of direct measurements, samle analyses, volunetric measurements, anc engineering analyses. The PDSRs are supported by detailed engineering calculations, vendor reports, and research data, go? AR "M!"eB Acd P
f 0 GPU Nuclear Corporation is a subsidlary of the General Public Utilities Corporation
t Document Ccntrol Desk September 30, 1988 e
441D-88-L-0162 The attached PDSRs transmit the post-defueling survey results for the plenum and letdown coolers.
They are the initial PDSRs published and the first survey results reporting SNM ouantities greater than 1 kg.
To facilitate NRC review of these initial packages, GPU Nuclear proposes a meeting with the NRC Staff (hopefully, including representation from thc technical review staff) to discuss the contents and me'.hodology. Supporting technical data, including detailed engineering calculations, vendor repJrts, and research data will be available for review at that meeting. The time and location of the meeting would be as mutually agreed subsea;ent tc your receipt and initial review of these survey reports.
Additional PDSRs will be submitted as they are co@leted.
A compilation of the individual PDSRs will form the basis for the final assessment of the a;antity of residual SNM for accountabiltty purposes.
To facilitate review and corpilation of individual post-defueling survey results, the reports are formatted for incorporation in a loose-leaf binder which also provides a listing of all PDSRs currently anticipated as well as programmatic information concerning the SNM Accountability Program.
It is noteworthy that the survey results are not intended to demonstrate the overall adecuacy of TMI-2 defueling progress, nor should they be construed as a determining factor for transition from Mode i to Mode 2 as defined in Section 1.3 of the THI-2 Technical Specificatinns. Transition to Mode 2 will be based on the TMI-2 Defueling Completion Report which will oemonstrate the r,verall adecuacy of the defueling progress in the context that inadvertent criticality is no longer possible and defueling has progressed to a point which, based on current technology and ALARA considerations, is logically defined as the endpoint for current defualing activities.
Sincerely, P'
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',, F. R.'tanderfer l'
Director, THI-2 RDW/ emf Attachments cc:
R. J. Conte - Senier Resident Inspector, TMI W. T. Russell - Regional Administrator, Region 1 J. F. Stolz - Director, Plant Directorate IV L. H. Thonus - Project Manager, TMI Site i
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