E910-05-060, Experimental Corporation (Snec) Application for Termination of License
| ML052640047 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 09/15/2005 |
| From: | Byrne J GPU Nuclear, Saxton Nuclear Experimental Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| E910-05-060 | |
| Download: ML052640047 (5) | |
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f'u_ GPU Nuclear, Inc.
G NUCLEAR NUCLA Three Mile Island Nuclear Station Route 441 South Post Office Box 480 September 15, 2005 Middletown, PA 17057-0480 E91 0-05-060 Tel 717-948-8461 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
Saxton Nuclear Experimental Corporation (SNEC)
Operating License No., DPR-4 Docket No. 50-146 Application for Termination of License Gentlemen, In accordance with 10 CFR 50.82(a)(9), this letter submits the SNEC facility application to the Nuclear Regulatory Commission (NRC) for termination of the GPU Nuclear, Inc. Operating (Possession Only) License No. DPR-4. Specifically, as detailed in the attached application, GPU Nuclear, Inc. has completed remaining radiological decommissioning and final radiation surveys of the SNEC facility and associated PENELEC area site in accordance with an NRC-approved license termination plan. The final radiation surveys demonstrate that the facility and site area meet the criteria for decommissioning and release of the site for unrestricted use stipulated in 10 CFR 20, Subpart E. Thus, GPU Nuclear has satisfied the requirements governing termination of a facility license that are stipulated in 10 CFR 50.82(a)(11 ), and requests that the NRC approve this application and terminate the GPU Nuclear, Inc. license by October 31, 2005.
If there are any questions regarding this letter, please contact Mr. A. F. Paynter of my staff at (717) 948-8425.
Sincerely,
'. Byrne Program Director, SNEC Attachment - Application for Termination of License cc: NRC Project manager, NRR NRC Project Scientist, Region I
Attachment E900-05-060 September 15, 2005 Pace I of 4 APPLICATION FOR TERMINATION OF LICENSE 10 CFR 50.82(a)(11) states:
The Commission shall terminate the license if it determines that--
(i) The remaining dismantlement has been performed in accordance with the approved license termination plan, and (ii) The final radiation survey and associated decontamination, including an assessment of dose contributions associated with parts released for use before approval of the license termination plan, demonstrate that the facility and site have met the criteria for decommissioning in 10 CFR part 20, subpart E.
GPU Nuclear, Inc. has satisfied the criteria of 10 CFR 50.82(a)(11 )(i) and (ii) as cited above that allow NRC termination of the SNEC facility license. Specifically, pursuant to 10 CFR 50.82(a)(11)(i), GPU Nuclear, Inc. has completed remaining dismantlement, including radioactive component removal and/or decontamination and confirmatory final radiation surveys, in accordance with the NRC-approved SNEC facility License Termination Plan (LTP).
Radioactive plant components have been removed and disposed of, or have been decontaminated to levels well below regulatory site release criteria. Similarly, contaminated or activated portions of plant structures have either been decontaminated or removed and disposed. As detailed further below, final radiation survey of the site has also been completed in accordance with the NRC-approved SNEC facility License Termination Plan.
Pursuant to 10 CFR 50.82(a)(1 1)(ii), the final radiation survey and associated documentation demonstrate that the SNEC facility and PENELEC site areas have met the criteria for decommissioning in 10 CFR 20, Subpart E. Details of the final radiation survey results are documented in SNEC facility Final Site Survey Reports that have been submitted to the NRC for review and approval (see table on the following page). Collectively, these reports document the conclusion that the facility and site meet the radiological criteria in 10 CFR 20.1402 for release of the site for unrestricted use.
Attachment E900-05-060 September 15, 2005 Paqe 2 of 4 Table 1, FSS Report - Submittal Listing
'Title Submittal Date Letter No.
FSS Report for CV Interior, 774' El. And Below April 24,2003 E910-03-016 FSS Report for CV Interior, 774' El. And Below May 13, 2003 E910-03-021 FSS Report for CV Interior, 774' El. And Below, Rev 1 September 4, 2003 E910-03-031 FSS Report for CV Interior, 774' El. And Below, Rev 1, Errata September 17, 2003 E910-03-035 FSS Report for SNEC CV Interior Above 774' EL. & Exterior October 29,2003 E910-03-041 FSS Report for SNEC PENELEC Line Shack June 29, 2004 E910-04-018 FSS Report for SNEC PENELEC Line Shack, Revision 1 August 18, 2004 E910-04-023 Final Status Survey Report for the Containment Vessel Excavation July 22, 2005 E910-05-013 FSS Report Open Land Area MA2 June 8, 2005 E910-05-016 FSS Report for Open Land Area 0L5 June 8, 2005 E910-05-017 FSS Report for Open Land Area 0L9 June 8, 2005 E910-05-018 FSS Report for East Yard Excavation OL 1-7 June 8, 2005 E910-05-019 FSS Report Open for Spray Pond Area SP1 June 8, 2005 E910-05-020 FSS Report for Open Land Area 0L4 June 22, 2005 E910-05-022 FSS Report for Open Land Area MA9 June 22, 2005 E910-05-023 FSS Report for Open Land Area O1 3 June 22, 2005 E910-05-024 FSS Report for Open Land Area OLI 1 June 22, 2005 E910-05-025 FSS Report for Open Land Area 0L8 July 8, 2005 E910-05-029 FSS Report for PENELEC Switchyard July 8, 2005 E910-05-030 FSS Report for Remediated Soils July 14,2005 E910-05-031 FSS Report- PENELEC Switch Yard Control Building July 14, 2005 E910-05-032 FSS Report for OL6 and OL10 July 14, 2005 E910-05-033 FSS Report for Open Land Area 0L7 July 22, 2005 E910-05-035 FSS Report for SSGS Firing Aisle July 22, 2005 E910-05-036 FSS Report for SSGS Basement July 22, 2005 E910-05-037 FSS Report for SSGS Seal Chambers July 22, 2005 E910-05-038
Attachment E900-05-060 September 15, 2005 Page 3 of 4 Table 1, FSS Report - Submittal Listing (continued)
Title., Submittal Date Letter No.
FSS Report for SSGS Discharge Tunnel Transition Area July 22, 2005 E910-05-039 FSS Report for Open Land Area OLI - Soils July 26, 2005 E910-05-041 FSS Report for Open Land Area 0L7 - Paved Surfaces And Concrete July 26, 2005 E910-05-042 FSS Report for SSGS Structural Surfaces - Intake Tunnel July 26, 2005 E910-05-043 FSS Report for SSGS Structural Surfaces - Discharge Tunnel July 26, 2005 E910-05-044 FSS Report for SSGS Structural Surfaces - CV Steam Tunnel July 26, 2005 E910-05-045 FSS Report for SSGS Spray Pump Area July 27,2005 E910-05-046 FSS Report for Seal Chamber Roofs July 27, 2005 E910-05-047 FSS Report for Open Land Area 0L3 - Paved Surfaces and Concrete July 27, 2005 E910-05-048 FSS Report for Open Land Area 0L2 July 27, 2005 E910-05-049 FSS Report for Residual Concrete in OL1 July 27, 2005 E910-05-050 FSS Report for Residual Macadam in OLI July 27,2005 E910-05-051 FSS Repot for Open Land Area Survey Unit OL1-6 July 27, 2005 E910-05-052 FSS Report for Site Areas MA3/MA4 Weir Discharge Area July 27, 2005 E910-05-053 FSS Report for Small PENELEC Garage GAl-1 July 27, 2005 E910-05-054 FSS Report for Embedded/Buried Piping July 27, 2005 E910-05-055 FSS Report for Open Land Area OL3 July 27,2005 E910-05-056 As indicated above, the SNEC facility Final Site Survey Reports document that the residual radioactivity associated with facility structures, systems, and components and site grounds meet the dose (25 mrem/y) and ALARA criteria specified in 10 CFR 20.1402.
OTHER LICENSE TERMINATION CONSIDERATIONS A previous submittal issued March 1994 and titled, "Reactor. Support Building Demolition Report", discussed the demolition and subsequent survey work of the reactor support buildings (e.g. the Control and Auxiliary Building). These facilities were demolished between June and September 1992, and along with the Radioactive Waste Disposal Facility (RWDF) and Yard Pipe Tunnel (demolished by 1989), were surveyed in accordance with survey methodology predating MARSSIM (Regulatory Guide 1.86). These earlier survey efforts were documented in the report titled, 'SNEC Final Release Survey of the Reactor Support Buildings, Rev 3, March
Attachment E900-05-060 September 15, 2005 Page 4 of 4 1992. Following this earlier work report number 91/F-93 titled, 'Confirmatory Radiological Survey for Portions of the Saxton Nuclear Experimental Facility (Independent Verification Survey)", by Oak Ridge Associated Universities (ORAU), for the NRC documented the validity and acceptability of this earlier dismantlement and subsequent survey work. In addition, License Amendment 11, dated May 28, 1992, allowed removal of these buildings but deferred Final Release until containment decommissioning and termination of the facility license. Finally, these earlier survey results were reviewed by an independent contractor (CoPhysics), retained by GPU Nuclear, who found the resulting TEDE to be well below the current criteria of
- 25 mrem/y. The report detailing this analysis was provided to the US NRC via GPU Nuclear letter E910-00-010 dated June 23, 2000, and was summarized in the SNEC LTP.
In preparation for termination of the Saxton Nuclear Experimental Facility license, GPU has reviewed the requirements of 10 CFR 50, as well as those contained in 10 CFR 20, and 10 CFR 30, and has identified several regulations requiring the forwarding of specified records to the appropriate NRC Regional Office prior to license termination. In GPU letter E910-05-061 to the NRC Region I submitted concurrently, GPU addresses these record-forwarding requirements and documents the manner in which they are satisfied.
SUMMARY
Based on the above, GPU Nuclear, Inc. has satisfied the requirements governing termination of a facility license that are stipulated in 10 CFR 50.82(a)(11). Therefore, on behalf of the SNEC facility operators, GPU Nuclear, Inc. respectfully requests that upon the acceptance of all Final Status Survey Reports (FSSR) and the resolution of all comments, the NRC approve this application and terminate the SNEC facility license by October 31, 2005.