ML20205J610

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Safety Evaluation Supporting Amend 109 to License NPF-1
ML20205J610
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 02/10/1986
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205J603 List:
References
NUDOCS 8602260129
Download: ML20205J610 (2)


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'8 NUCLEAR REGULATORY COMMISSION

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e SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.109 TO FACILITY OPERATING LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT L

DOCKET NO. 50-344 Introduction i

By letter dated April 19. 1985, Portland General Electric (PGE), the licensee,

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submitted a request for an amendment to the Trojan Technical Specifications to revise: (1) the definition of Operable, (2) the Action statement associated with the structural integrity of the Reactor Coolant System (RCS), and (3) the survaillance requirements of the Control Room Emergency Ventilation System.

This evaluation contains the review and approval of the revised definitions of Mode and Operable and the review and approval of the licensee's November 8, i

1985 request to withdraw the requested revis? ns to the Action statement I

associated with the structural integrity of the RCS.- The review of the licensee's request to revise the surveillance requirements of the Control Room Emergency Ventilation System is being handled separately and will be the subject of a future Safety Evaluation.

Discussion and Evaluation 3

1.

The Definitions of Mode and Operable i

The amendment would expand the definition of Operational Mode to include

" Mode" as its equivalent since the word " Mode" is used in most applicability statements. The staff concludes that since the operational definition of the word " Mode" is quite common, this change is acceptable.

b The amendment would also specify that only items necessary for the system to perform its safety-related function (s) are necessary to demonstrate

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Operability. Since.GDC-21 of 10 CFR 50, Appendix A, states that:

"The protection system shall be designed for high functional reliability and inservice testability commensurate with the safety functions to be L

performed,"

the limitation of the definition of the word " Operable" to safety functions L

is also acceptable.

2.

Structural Integrity The amendment requested a revision to the Trojan Technical Specifications Section 3.4.1.0.d. Structural Integrity of ASME Class 1, 2, and 3 components, which currently reads:

8602260129 B60210 PDR ADOCK 05000344.

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"If the requirements of the above ACTION items are not met, in lieu of the requirements of Specifications 3.0.3, an evaluation can be performed to determine the consequences of continuing to operate with reduced structural integrity or with a temporary repair made to the affected.. components (s) or be in a COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />."

4 The request would have allowed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to perform.the above. evaluation and an additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to complete repairs..By letter dated November 8, 1985 1

the licensee requested a withdrawal of the above modification.

Since the current Technical Specifications are more conservative than those proposed the staff accepts this withdrawal.

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However, during our. revise of Section 3.4.10.1.d, the staff became concerned with the provision to allow an evaluation "... to determine the consequences.

of continuing to operate with reduced structural integrity or with a temporary.

repair made to the affected components..." as an alternative to restoring 1

structural integrity. Safety related components, especially those which are part of the reactor coolant pressure boundary or attached thereto, should not be placed in service with reduced structural integrity.

The licensee is requested to review paragraph 3.4.10.1.d of. the Trojan Specification and propose revised Technical Specifications.

ENVIRONMENTAL CONSIDERATION This amendment relates to changes in recordkeeping, reporting, or i

administrative procedures or requirements. Accordingly, this amendment meets i?

the-eligibility criteria for categorical exclusion set forti in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this 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.

Date: February 10,-1986 PRINCIPAL CONTRIBUTORS:

K. Johnston

0. Rothberg E. Lantz i

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