ML20202E982

Application for Amend to License NPF-1,revising RCS Specific Activity Reporting Requirements

ML20202E982
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/09/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20202E967	List: ML20202E963 ML20202E982 ML20202E998
References
TAC-61277, NUDOCS 8604140083
Download: ML20202E982 (3)

Text

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PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD

.' AND PACIFIC POWER & LIGHT COMPANY Operating License NPF-1 Docket 50-344 License Change Application 136 This License Change Application requests modifications to Operating License NPF-1 for the Trojan Nuclear Plant to revise the Reactor Coolant System specific activity reporting requirements.

PORTLAND GENERAL ELECTRIC COMPANY By _-

Bart D. Withers Vice President Nuclear Subscribed and sworn to before me this 9th day of April 1986.

Notary Publ'ic of Oregfin

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LCA 136 Page 1 of 2 DESCRIPTION OF CHANGES

1. Trojan Technical Specification (TTS) 3.4.8, Action, Modes 1, 2, and

3. Item a - The provision limiting operation with specific activity greater than 1.0 pCi/ gram Dose Equivalent I-131 to 10 percent of

• the units' total yearly operating time is deleted.

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2. TTS 3.4.8, Action, Modes 1, 2, 3, 4, and 5, Item a - The requirement that the specific activity analysis results be submitted in the Annual Report is added. l

3. TTS 3.4.8, Bases - The bases of the provision limiting operation with specific activity greater than 1.0 pCi/ gram Dose Equivalent I-131 to 10 percent of the units' yearly operating time is deleted.  ;

4. TTS 6.9.1.5.d is added to specify information regarding the specific activity analysis which must be included in the Annual Report.

REASONS FOR CHANGES Generic Letter 85-19 states the NRC's determination that the reporting requirement for iodine spiking can be reduced from a short-term report (Special Report or Licensee Event Report) to an item which is to be included in the Annual Report. The information to be submitted in the report is also changed to more clearly designate the results to be included from the specific activity analysis and to delete the information regarding fuel burnup by core region.

Additionally, the NRC states that the requirement to shut down a plant if coolant iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period (expressed as 10 percent of total yearly operating time in the TTS) can be eliminated. This limit is no longer considered necessary on the basis that proper fuel management by licensees (with the quality of nuclear fuel greatly improved) and existing reporting requirements

[10 CFR 50.72(b)(1)(ii)] should preclude ever approaching the limit.

SIGNIFICANT HAZARDS DETERMINATION

In accordance with the requirement of 10 CFR 50.92, this License Change Application is judged to involve no significant hazards based upon the following information:

1. Does the license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Changing reporting requirements is administrative only. The provision regarding a percentage of total yearly operating time is no longer considered necessary since proper fuel management, improved fuel quality, and existing reporting requirements [10 CFR 50.72(b)(1)(ii)]

should preclude approaching the limit. No increase in the probability or consequences of an accident is involved.

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LCA 136 Page 2 of 2

2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Changing reporting requirements is administrative only. The elimination of an unnecessary operating limit does not create the possibility of a new or different type of accident.

. Does the proposed amendment involve a significant reduction in a margin of safety?

Changing reporting requirements is administrative only. The elimination of the provision regarding a percentage of total yearly operating time does not involve any reduction in safety margin since proper fuel management, improved fuel quality, and existing reporting requirements should preclude approaching the limit.

SAFETY / ENVIRONMENTAL EVALUATION Safety and environmental evaluations were performed as required by 10 CFR 50 and the Trojan Technical Specifications. This review determined that an unreviewed safety question does not exist since Plant operations remain consistent with the Updated FSAR, adequate surveillance is maintained, and there is no conceivable impact upon the environment.

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