ML20058M700
| ML20058M700 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 09/30/1993 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | PORTLAND GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20058M699 | List: |
| References | |
| NUDOCS 9310060342 | |
| Download: ML20058M700 (4) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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I PORTLAND GENERAL ELECTRIC COMPANY
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Docket No. 50-344
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(Trojan Nuclear Plant)
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EXEMPTION I.
The Portland General Electric Company (PGE or the licensee), is the holder of Facility Operating License No. NPF-1, which authorizes possession and maintenance of the Trojan Nuclear Plant (TNP or plant). The license provides, among other things, that the plant is subject to all rules, The regulations, and Orders of the Comission now or hereafter in effect.
facility is a permanently shutdown pressurized water reactor, currently iti the process of being decomissioned, and is located at the PGE site in Columbia County, Oregon.
II.
The 'icensee, by letter dated February 2,1993, informed the NRC that TNP-had permanently ceased power operations, all fuel hid been removed from the reactor to the fuel pool, and that PGE had begun to develop detailed plans to decommission the facility. The NRC, in License Amendment 190, dated May 5, The license 1993, modified License NPF-1 to a Possession Only License (POL).
is conditioned so that TNP is not authorized to operate the reactor or place fuel in the reactor vessel, thus formalizing the commitment of the licensee to permanently cease power operations.
9310060342 930930 PDR ADDCK 05000344 P
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~~ 1 By letter dated June 17, 1993, the licensee requested an exemption from
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certain safeguards requirements of 10 CFR 73.55 as discussed in Section V which were designed for an operating power reactor facility and are unnecessary for TNP in its defueled condition.
III.
The bases of the licensee for the exemption request are that the reactor has been defueled, the fuel placed in the spent fuel storage pool, and that t
the reactor cannot be returned to operation because of the provisions of the May 5, 1993, POL. The request is also premised on a TNP Threat Analysis which documents that an act of radiological sabotage will not result in a radiation dose greater than the limits provided in the Environmental Protection Agency Protective Action Guides (PAGs) and that the proposed TNP Defueled Trojan Security Plan reflects a level of security commensurate with the security threats associated with a permanently shutdown and defueled TNP.
The requirements of 10 CFR 73.55 were promulgated to provide protection of a facility against a design basis sabotage threat in consideration of the conditions associated with an operational power reactor. When compared with,
an operational power reactor facility, the status of TNP provides a significantly reduced risk from a radiological release as a consequence of sabotage. The range of credible accidents and accident consequences for TNP were limited because of the currently shutdown and defueled condition. The Defueled Security Plan, which remains relevant to the defueled status, provides an adequate basis for an acceptable safeguards program, r
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r IV.
The staff, based on its independent evaluation, agrees with the analyses of the licensee and concludes that sufficient bases have been presented for our approval of the exemption request, Documents submitted with the June 17, 1993 exemption request of the licensee, and subsequent Ju'y 29, 1993 submittal 1
of changes requested by the NRC staff, with the exception of the Defueled i
Trojan Nuclear Plant Security Force Training and Qualification Plan (PGE-1059, Revision 0), are classified as Safeguards Information and consequently are not publicly available.
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V.
Based on Sections III and IV, above, the Comission has determined that pursuant to 10 CFR 73.5, this exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security.
Accordingly, the Comission hereby grants an exemption to the Portland General Electric Company from certa:n requirements of 10 CFR Part 73.55 as requested in its letter of June 17, 1993. This exemption concerns portions of an onsite physical protection system and security organization which are no longer needed fcr the Trojan Nuclear Plant in its permanently defueled sondition, as determined by the Comission in its review of the revised i
security and training and qualification plans of the licensee, provided that (1) the reactor is void of all fuel, (2) the fuel is stored in the spent fuel pool, and (3) the TNP Security Plan (Defueled Condition), Revision 0 dated July 26, 1993, and TNP Security Force Training and Qualification Plan (Defueled Condition), Revision 0 dated June 17, 1993 are implemented.
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Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a signicant effect on the quality of the human environment (58 FR 51116).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Brian K. Grimes, Director Division of Operating Reactor Support Office of Nuclear Reactor Regulation Dated at Rockville, Maryland this 30th day of September 1993 f
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