ML20141H318

Safety Evaluation Supporting Amend 196 to License NPF-1

ML20141H318
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/19/1997
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141H292	List: ML20141H287 ML20141H303 ML20141H318
References
NUDOCS 9705230274
Download: ML20141H318 (2)

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[I k1 UNITED STATES i' NUCLEAR REGULATORY COMMISSION  ;

f WASHINGTON, D.C. 20566-0001

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SAFETY EVALVA110N BY THE OFFICE OF NUCLEAR REACTOR REGULATIQN RELATED TO AMENDMENT NO.196 EL POSSESSION ONLY LICENSE NO. NPF-1 M TLAND GENERAL ELECTRIC COMPANY THE C PY OF EUGENE. OREGON ,

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

1.0 INTRODUCTION

By letters dated January 16 and February 24, 1997, Portland General Electric Compar.), et al. (PGE or licensee) submitted a request for changes to the Possession Only License for Trojan Nuclear Plant. The proposed changes would delete. the prohibition on moving a spent fuel assembly shipping cask into the Nel building. This will allow PGE to perform pre-operational testing and load handling of empty spent fuel trans6 and storage casks in the T.ojan Fuel Building. These ac?ivities must bc completed prior to transferring fuel from the spent fuel pool in the Trojan Fuel Building to an Independent Spent Fuel Storage Installation (ISFSI). The construction and operation of the L ISFSI and transfer of fuel to the ISFSI are' subject to separate NRC review and approvals.

2.0 BACKGROUND

The licensee announced permanent cessation of power operations of the Trojan uclear Plant on January 4, 1993. The licensee submitted a proposed ,

decom,issioning plan on January 26, 1995, which was approved by the NRC on '

April 15, 1996. lhe facility is currently in an active decommissioning phase.

In order to complete decommissioning and permit radiological release of the site for unrestricted use, PGE must remove the fuel from the spent fuel pool. ,

PGE has proposed to store the fuel in an ISFSI and, in March 1996, submitted a licence application under 10 CFR Part 72 to construct and operate the ISFSI.

3.0 EVALUATION The activities proposed by the licensee include pre-operational testing and load handling'of empty spent fuel transfer and storage casks in the Trojan Fuel Building. The casks will be empty and not contain spent fuel or radioactive waste. 'Therefore, load handling events do not involve a potential dispersal of radioactive materials from the casks. The potential' impact on safety is'through' damage to structures, systems, and components important to safe storage of fuel resulting from a ~1oad handling event.

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PGE will use administratively controlled safe load paths for all movements of the empty casks. There will be no heavy load handling over the spent fuel pool as this is outside 'hec limits of the authorized heavy load paths. In addition there are mechanical and electrical interlocks on the crane to preclude movement over the spent fuel pool. The safe load paths have sufficient structural strength to withstand a load drop with no damage to structures, systems, and components important to safe storage of spent fuel.

In some instances load impact limiters are used to absorb and dampen potential impacts to provide this structural protection. The load impact limiters are required to be in place during cask movements over the affected area. In addition to load drops involving the transfer cask (loaded with a basket and dummy fuel) PSE and the NRC staff have evaluated a number of lesser load drops involving components such as the cask lid, backet lid, and basket. The safety impacts of these potential load handling events is within that of the larger cask drop.

The NRC staff has cb;arved the safe load paths and the mechanical interlocks and found ther, to te adequate to assure the safety of structure , systems, and components required for the safe storage of spent fuel at Trojan. PGE will complete crane inspection and' testing prior to moving the casks. PGE's load handling program complies with Section 5.1.1 of NUREG-0612 " Control of Heavy  :

Loao's at Nuclear Power Plants." This program includes: l

1. Definition of safe load paths

2. Development of load handling procedures

3. Periodic inspection and testing of cranes

4. Qualifications, training, and specified :onduct of operators

5. Special lifting devices should satisfy the guidelines of American National Standards Institute (ANSI) N14.6.6

6. Lifting devices that are not specially designed should be installed and used in accordance with the guidelines of ANSI B30.9

7. Design of cranes to ANSI B30.2 or Crane Manufacturers Association of America (CMAA)-70.

The staff concludes that PGE has taken adeque'e measures to assure safety during the proposed activities. Accordingly, the staff finds removal from the license of prohibition on moving a spent fuel assembly transfer cask into the Fuel Building acceptable.

4.0 SIATE CONSULTATION In accordance with the regulations of Commission, the Oregon State official was notified of the proposed ,3suance of the amendment. The State official had no comments.

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5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be reisased offsite, and that there is no significant increasc in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves ne significant hazards consideration, and there has been no public comment on such finding (62 FR 14467). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

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 rtigulations of the ,

Commission, and (3) the issuance of the amendment will not be inimical to the i common defense and security or to the health and safety of the public.

Principal Contributor: Lee H. Thonus Date: May 19, 1997 1

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