ML20072H501

Proposed Tech Spec Revs Re Frequency of Steam Generator Inservice Insp

ML20072H501
Person / Time
Site:	Millstone
Issue date:	03/01/1983
From:	NORTHEAST UTILITIES
To:
Shared Package
ML20072H469	List: B10724, Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Inservice Insp ML20072H501
References
TAC-48062, TAC-49905, NUDOCS 8303290459
Download: ML20072H501 (4)

Text

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( 1. ..l. \\- ri-A Docket No. 50-336 t e) ~e / i .,s 4 s r u l t i \\ ) l N .1 i Millstone Nuclear Power Station, dnit No. 2 Proposed Revisions to Technical Specifications Steam Generator Ingervice Inspection 'i i 1. s q,\\ 1 e \\ e* v g \\ i l s ( [ t ' March 1983 p-A 8303290439 830314 PDR ADOCK 05000336 P PDR -~.. -

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.(.. REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies: a. The first inservice inspection shall be perfomed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be perfonned at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspec-tion results falling into the C-1 category or if two consecu-tive inspections demonstrate that previously observed degrada-tion has not continued and no additional degradation has occurred, the inspection interval may be extended to a maxiriIum of once per 40 months. b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-6 at 40 month intervals fall into Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspec-tions ',atisfy the criteria of Specification 4.4.5.1.3.a; the interval may then be extended to a maximum of once per 40 months. c. Additional, unscheduled inservice inspections shall be per.fomed on each steam generator in accordance with the first sample . inspection specified in Table 4.4-6 during the shutdown subse-quent to any of the following conditions: 1. Primary-to-secondary tubes leaks (not including leaks j originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.* l 2. A seismic occurrence greater than the Operating Basis Earthquake. 3. A loss-of-coolant accident reg +ing actuation of the engineered safeguards: 4. A main steam line or feedwater line break.

• For the outage commencing on March 1,1983 only, the inservice inspection requirements of Category C-1 of Table 4.4-6 are deferred to the 1983 refueling outage.

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