ML20206F121: Difference between revisions

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.116 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON g
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.116 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON g
PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET NO. 50-344 l
PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET NO. 50-344 l
INTRODUCTION By letter dated April 11, 1986, Portland General Electric Company (the licensee) requested changes to the Technical Specifications for the Trojan Nuclear Plant. At present, Design Features Section 5.3.1., Fuel Assemblies, of the Trojan Technical Specifications identifies a maximum total fuel rod weight of 1,760 grams of uranium. Recent changes to the fuel design by Westinghouse, including chamfered pellets with a reduced dish and use of the integrated dry route process, have slightly increased the fuel density. The resulting weight increases have caused the assembly averaged fuel rod weight for Cycle 9 fuel to exceed the 1,760 limit by as much as 13 grams. The proposed change will        :
INTRODUCTION By {{letter dated|date=April 11, 1986|text=letter dated April 11, 1986}}, Portland General Electric Company (the licensee) requested changes to the Technical Specifications for the Trojan Nuclear Plant. At present, Design Features Section 5.3.1., Fuel Assemblies, of the Trojan Technical Specifications identifies a maximum total fuel rod weight of 1,760 grams of uranium. Recent changes to the fuel design by Westinghouse, including chamfered pellets with a reduced dish and use of the integrated dry route process, have slightly increased the fuel density. The resulting weight increases have caused the assembly averaged fuel rod weight for Cycle 9 fuel to exceed the 1,760 limit by as much as 13 grams. The proposed change will        :
delete the weight limits from the Technical Specifications to allow use of the    I slightly heavier fuel.                                                            ;
delete the weight limits from the Technical Specifications to allow use of the    I slightly heavier fuel.                                                            ;
l DISCUSSION AND EVALUATION The important safety related parameters which are indirectly affected by fuel
l DISCUSSION AND EVALUATION The important safety related parameters which are indirectly affected by fuel

Latest revision as of 11:29, 6 December 2021

Safety Evaluation Supporting Amend 116 to License NPF-1
ML20206F121
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 06/09/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206F115 List:
References
NUDOCS 8606240238
Download: ML20206F121 (2)


Text

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8 UNITED STATES

'[y g NUCLEAR REGULATORY COMMISSION

j WASHINGTON. D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.116 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON g

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

INTRODUCTION By letter dated April 11, 1986, Portland General Electric Company (the licensee) requested changes to the Technical Specifications for the Trojan Nuclear Plant. At present, Design Features Section 5.3.1., Fuel Assemblies, of the Trojan Technical Specifications identifies a maximum total fuel rod weight of 1,760 grams of uranium. Recent changes to the fuel design by Westinghouse, including chamfered pellets with a reduced dish and use of the integrated dry route process, have slightly increased the fuel density. The resulting weight increases have caused the assembly averaged fuel rod weight for Cycle 9 fuel to exceed the 1,760 limit by as much as 13 grams. The proposed change will  :

delete the weight limits from the Technical Specifications to allow use of the I slightly heavier fuel.  ;

l DISCUSSION AND EVALUATION The important safety related parameters which are indirectly affected by fuel

~

weight, such as reactor criticality, power level, power distribution and the rate of decay heat production, are all regulated by requirements in the Limiting Condition for Operation sections of the Technical Specifications.

In addition, the fuel weight is implicitly included in the nuclear design analysis performed for each reactor operating cycle and is used to evaluate conformance with established limits for Design Basis Events. For the slight weight increases reported by the licensee for Cycle 9 fuel, and any similar possible small future fuel weight increases without a significant change in fuel design, there is no impact on the safety analysis. A significant change in the fuel design would be the subject of review and changas to the other governing Technical Specifications.

8606240238 DR 860609 ADOCK 05000344 PDR l

J " * ~~- - -

We therefore conclude that there will be no significant safety impact in deleting the maximum fuel weight restriction from Design Features Section 5.3.1 of the Technical Specifications. We also find this action preferable to changing the Technical Specifications each cycle to accommodate the applicable weight, or to specifying an artificial upper value of the weight to bound future variations.

ENVIRONMENTAL CONSIDERATION This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

l The staff has determined that the amendment involves no significant increase j in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The 3

Commission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(c)(9).

Pursuant to 10 CFR 951.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

CONCLUSION We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. ]

Dated: June 9, 1986

, PRINCIPAL CONTRIBUTOR: M. Dunenfeld l

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