ML20206H450

Safety Evaluation Supporting Amend 201 to License NPF-1

ML20206H450
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/05/1999
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206H435	List: ML20206H433 ML20206H441 ML20206H450
References
NUDOCS 9905110215
Download: ML20206H450 (3)

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p i UNITED STATES s"

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20061 MOO 1 j

. . . . . ,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 201 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER AND ELECTRIC BOARD I l

PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCK'ET NO. 50-344

1.0 INTRODUCTION

By letter dated February 12,1997, the Portland General Electric Company (PGE or the licensee) transmitted License Change Application (LCA) 242 requesting changes to the Permanently Defueled Technical Specifications. The proposed change would delete the ,

proposed Independent Spent Fuel Storage Installation (ISFSI) area.  !

2.0 BACKGROUND

The licensee announced permanent cessation of power operatns of the Trojan Nuclear Plant (TNP) on January 4,1993. The licensee submitted a proposed Drommissioning Plan (DP) on January 26,1995, which was approved by the NRC on April 15,1996. The facility is currently undergoing active decontamination and dismantlement. In order to complete decommissioning and permit radiological release of the spent fuel pool (SPF) for unrestricted use, PGE must remove the spent fuel and all other radioactive components stored in the pool. PGE's DP stated that relocating the contents of the SPF to an ISFSI would be the most economical method for storing the spent fuel until offsite shipment. This interim storage in tk JFSI would allow decontamination and decommissioning of the TNP PGE submitted in M , a 1996, a 10 CFR Part 72 license application to the NRC for cc istruction and operation of an ISF31. On March 31,1999, the NRC issued a Part 72 licento.

3.0 EVALUATION The LCA requests deletion of +5e proposed ISFSI area from the technical specifications. The deletion of the ISFSI area fr( t .he technical specifications is concurrent with the initiation and l the issuance of a 10 CFR Part 72 license for the same area.

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3 c PGE indicated that " positive control of ingress and egress of personnel and materials will be maintained." The personnel and vehicular access for the ISFSI access controlled area will be consistent with the Part 72 license security plan.

The NRC staff approved a Physical Security Plan for the proposed ISFSI by a letter dated November 20,1996.

Exclusion Area .

The ISFSI area is within the exclusion area of the TNP facility. .The potential for radiological release consequences for the exclusion area, including the ISFSI area, from postulated accidents during decontamination and decommissioning has been addressed in the DP, Section 3.4, " Event Analysis." Public access to the ISFSI area will be controlled by the Part 72 Security Plan and license. Therefore, the release of the ISFSI area from the Part 50 license will not alter dose consequences to the public.

Radioloalcal Survevs and Release The release criteria for the licensee's final survey of the ISFSI area was based on the Site Decommissioning Management Plan guidelines. In addition, the licensee elected to meet a total effective dose equivalent (TEDE) to the average individual of 15 mrem /yr. To demonstrate

- compliance with the 15 mrem /yr release criteria, the licensee used the default concentration values for soil as recommended in NUREG-1500, ' Working Draft Regulatory Guide on Release Criteria for Decommissioning: NRC Staff's Draft for Comment," dated August 1994 in the residential scenario. For the principal gamma emitters, the limits for Cobalt-60 and Cesium-137, the values were 3.96 and 14.25 picoeurie per gram (pCi/g), respectively. The default values in NUREG-1500 are less conservative than current default values provided in the DandD model residential scenario. For a dose limit of 25 mrem /yr (NRC's release criteria, 10 CFR 20, Subpart E), the DandD default values limits for Cobalt-60 and Cesium-137 are 3.68 pCi/g and 9.83 pCi/g, respectively.

The NRC staff reviewed the licensee's final radiological survey report dated October 30,1996, for the licensee's ISFSI site. From the results of the licensee's final survey, the average value for both Cobalt-60 and Cesium-137 was 0.01 pCi/g of soi! tested. NRC and its contractors, the Oak Ridge Institute for _ Science and Education (ORISE) conducted a limited confirmatory survey of this areac The licensee's results were confirmed. The results of the limited confirmatory survey are documented in ORISE's trip rt. port dated September 27,1996, for the ISFSI area, and in NRC Inspection Report 50-344/96-07; 72-17/96-01 dated September 10, 1996. Since, the October 30,1996, report indicates that all soil samples analyzed were well below the DandD default values, NRC has determined that the TEDE to an average member of the critical group would be well below the 10 CFR 20, Subpart E, limit of 25 mrem /yr.

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l Based on the staff's review of the licensee's LCA 242 dated February 12,1997, and related information, the staff concluded that the license amendment request for the deletion of the i proposed ISFSI area from the Permanently Defueled Technical Specifications is acceptable.

4.0 STATE CONSULTATION

in accordance with the Commission's regulations, the Oregon State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

S Pursuant to 10 CFR 51.21,51.32 and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Reaister on May 5,1999 (64 FR 24190).

Accordingly, based upon the environmental assessment, the Commission has determined that issuance of the amendment will not have a significant effect on the quality of the human environment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the license amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: S. Nalluswami L.Thonus Date: May 5, 1999

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