ML20207L705

Safety Evaluation Supporting Amend 116 to License DPR-3

ML20207L705
Person / Time
Site:	Yankee Rowe
Issue date:	10/12/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207L674	List: ML20207L670 ML20207L689 ML20207L705
References
NUDOCS 8810170407
Download: ML20207L705 (2)

Text

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMEN_T N0. 116 TO FACI _LITY CPERATING LICENSE NO. DPR-3 YANKEE ATCMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATIO_N D0CKET NO.50-029 INTRODUCTION By letter dated June 27, 1988 Yankee Atomic Electric Company (YAEC or the licensee) submitted a Technical Specification (TS) change request to enable modifications to the nonsafety class portion of the neutron shield tank cavity leakage collection piping in the Yankee Nuclear Power Station (YNPS or the plant).

The proposed TS changes, specifically, are to delete valve VD-V-752 in the neutron shield tank test line from TS Table 3.6-1 and to modify the Main Coolant Leakage Detection System TS 3/4 4.5.1, regarding both limiting conditions for operation and surveillance to enable addition of the neutron shield tank telltale leakage detection system to the TS. These proposed modifications in the nonsafety class portion of the neutron shield tank cavity leakage collection piping will prevent such leakage from being collected and monitored in the installed Containment Drain Collection System, a safety related system.

The neutron shield tank telltale leakage monitoring connections are currently monitored periodically for evidence of leakage. Should excessive leakage occur, the existing configuration allows the excess fluid to be directed to the Containment Drain Collection System located in the Primary Auxiliary Building. This overflow feature is being eliminated and replaced with a level l switch and the necessary piping and valves to manually align the drains to the 3 Containment Drain Collection System if required. l To facilitate"detection of leakage in both the inner and outer telltale lines, the piping will be modified to connect the drain lines together upstream of the level switch. This will pennit the elimination of one neutron shield tank telltale containment isolation valve (VD-V-752).

The revised Specification 3.4.5.1 also includes changes in the operability and action statements for the Containment Atmosphere Particulate Monitoring System to provide consistency in system name with the applicable surveillance section.

EVALUATION The system name changes involving the Containment Atmosphere Particulate Monitoring System in Section 3.4.5.1 of the TS are administrative and we conclude they are acce table as they provide consistency between various sections of the TS. T e change involving the containment boundary, that is 8810170407 681012 PDR P

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the elimination of valve V0-V-752 will eliminate a potential leak path from the containment. The addition of the new level switch provides a leak detection system equivalent to the one being replaced and has the advantage of distinguishing leakage that originated from within the reactor cavity from other centainment drains. For the reasons stated above we conclude the TS changes related to V0-V-752 and the new level switch are acceptable.

ENVIRONMENTAL CONSIDERATION This amendment involves a change to a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The 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 released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.2?(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

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

ACKNOWLEDGEMENT _

Principal Contributor: Morton B. Fairtile Dated: October 12, 1988 l

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