ML20198D233

Proposed Tech Specs Change Request 214 Re OTSG primary-to- Secondary Leak Rate Limit

ML20198D233
Person / Time
Site:	Three Mile Island
Issue date:	05/13/1992
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20198D225	List: ML20198D222 ML20198D227 ML20198D233
References
NUDOCS 9205190228
Download: ML20198D233 (1)

Text

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(8) Re3 aired Steam Generatori in order to cafirm the leak-tight integrity of the Reactor Coolant System, including the steam generators, operation of the facility shall be in accordance with the following:

1. Prior to initial criticality, GPU Nuclear Corporation shall submit to NRC the results of the steam generator hot test program and a summary of its management review.

e. GPU Nuclear Corporation shall confirm baseline primary-to-secondary leakage rate established during the steam generator hot test program. The leakage rate limit shr.11 be 0.1 gpm above i the baseline leakage rate, unless the observed leakage is judged to be caused by leaking plugs or joints, in which case the leakage rate limit may be increased to 0.2 gpm above baseline, and shall not exceed this limit from all sources.- If leakage exceeds the established leakage rate limit, the facility sh11 be shut down and leak tested. If any increased leakage abwe baseline is due to defects in the tube free span, the leaking tube (s) shall be removed from service. The baseline leakage shall be re-established, provided that the leakage limit of Technical Specification 3.1.6.3 is not exceeded.

3. GPU Nuclear Corporation shall complete its post-critical test program at each power range (0-5%, 5%-50%, 50%-100%) in conformance with the program described in Topical Report 008, Rev. 3, and shall have available the results of that test program and a summary of its management review, prior to ascension from each power range and prior to normal power operation.

-4. GPU Nuclear Corporation shall conduct eddy-current examinations, cons 4 tent with the extended inservice inspection plan defined in 1 ole 3.3-1 of NUREG-1019, either 90 calendar days after reaching full power, or 120 calendar days after exceeding 50%

power operation, whichever comes first. In the event of plant operation for an extended period at less than 50% power, GPU Nuclear Corporation shall provide an assessment at the end of

, 180 days of operation at power levels between 5% and 50%, such l assessment to contain recommendations and supporting information as to the necessity of a special eddy-current testing (ECT) shutdown before the end of the refueling en .e. (The NRC staff will evaluate that assessment and determine the time of the next i

$ eddy-current -examination, consi: tent with the M'ier provisions j%g-

of the license conditions.) In the absence of such an

.no assessment, a special- ECT shutdown shall take place before an l  ;

additional 30 days of operation at power above 5%.

ms 50 le RE NL n.

Amendment No. Jp), JS)

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