ML20134J631

Proposed Tech Specs 4.10.C.2 Re SG Tube Surveillance Requirements

ML20134J631
Person / Time
Site:	Maine Yankee
Issue date:	02/07/1997
From:	Maine Yankee
To:
Shared Package
ML20134J627	List: ML20134J626 ML20134J631
References
NUDOCS 9702120227
Download: ML20134J631 (5)

Text

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ATTACHMENT B l I

Proposed Technical Specification Pages i 4.10-2 l l

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9702120227 970207 PDR ADOCK 05000309 P PDR ,

Cateoorv Insoection Results C-2 One or more tubes, but not more than 1% of i the total tubes inspected are defective, or i between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.

C. Insoection Frecuencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

1. Inservice inspections shall be performed at interval 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 inspection results falling into the C-1 category or if two consecutive inspections

.. demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

2. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.10-2 at 40 month intervals fall in 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 inspections meet the conditions specified in C.1 and the interval can be extended to a 40 month period.

Excention: The surveillance related to the steam generator inspection.

due in June 1997, may be deferred until the next refueling outage or no later than March 31, 1998, whichever is earlier.

3. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.10-2 during the shutdown subsequent to any of the following conditions:  !

(a) Primary-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.14.C.5, (b) A main steam line break or feedwater line break, (c) A seismic occurrence greater than the Operating Basis Earthquake, or  !

(d) A loss-or-coolant accident requiring actuation of the engineered I safeguards.

Amendment No. 28, 84 M9, 4.10-2

' ATTACHMENT C Proposed Technical Specification Page.s 4.10-2 & 4.10-2a (This page applies only if Maine Yankee Proposed Change No. 169 is approved before this Proposed Change)

Cateoorv Insoection Results i C-2 One or more tubes. but not more than 1% of I the total tubes inspected are defective, or ,

between 5% and 10% of the total tubes '

inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations. .

C. InsDection Frecuencies - Inspections of steam generator tubes shall be performed as follows:

1. Inservice inspections shall be performed at interval 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 inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

2. If the results of the inservice inspection of a steam generator  !

conducted in accordance with Table 4.10-2 at 40 month intervals fall in j Category C-3. the inspection frequency shall be increased to at least 1 once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections meet the conditions specified in C.1 and the interval can be extended to a G month period.

Exceotion: The surveillance related to the steam generator inspection, due in June 1997, may be deferred until the next refueling outage or no later than March 31, 1998, whichever is earlier.

3. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.10-2 during the shutdown subsequent to any of the following conditions:

(a) A main steam line break or feedwater line break.

(b) A seismic occurrence greater than the Operating Basis Earthquake, or (c) A loss-or-coolant accident requiring actuation of the engineered 3

safeguards.

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Amendment No. 28, 84 H9, 4.10-2

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. 4. Unsceduled inspections shall be performed during the shutdown following '

a primary-to-secondary tube leak (not including leaks originating from tube plugs or tube to tubesheet welds) in excess of the limits of ,

Specification 3.14.C.5. When leaks are discovered, the cause of the leak should be evaluated and the leaking tube (s) repaired or removed from service. The evaluation should form the basis for additional inspections confined to the critical area and should focus on >

identifying defects similar to the leaking tube (s). These inspections should include: ,

(a) A review of available historical ECT information to determine l

whether additional tubes require reinspection and conduct a 20%

ECT sample inspection (using appropriate methods) of the critical area for that steam generator looking for the same defect mechanism.

l L (b) If more than 1% of the inspected tubes are found defective, expand the inspection to a 100% sample inspection in the critical area for the same defect mechanism and conduct a 20% sample inspecticn in the same critical area in the other two steam i gener6 tors. l (c) If more than 1% of the inspected additional tubes are found defective in the other two steam generators, expand to a 100% '

sample ins'pection in the critical area for those steam generators.

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Amendment No. 4.10-2a

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