ML20094L288

Proposed Tech Specs Revising F* Distance Definition to State Total F* Distance Including EC Measurement Uncertainty & Adding Paragraph to Basis for Section 15.4.2, ISI & Testing of Safety Class Components

ML20094L288
Person / Time
Site:	Point Beach
Issue date:	11/16/1995
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20094L284	List: ML20094L282 ML20094L288
References
NUDOCS 9511200149
Download: ML20094L288 (2)

Text

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. -., l Defect is an imperfection of such severity that it exceeds the minirum  !

acceptable tube wall thickness of 50%. A tube containing a defect is I defective. J Pluaaina Limit is the imperfection depth beyond which the tube must be removed from service or repaired, because the tube may become defective prior to the next scheduled inspection. The plugging limit ,

is 40% of the nominal tube wall thickness.

F** OfstisEsTff thi"dist~ahi~e~of"th~e'eMii5ded"pirti os^ ^6f Ttubs'~whi Eh I provides a sufficient length of undegraded tube expansion to' resist pullout of fthe tube from the tubesheet. The F* distance is 1.12~'~~~

measured from thelbottom of the upper roll)transitioninches'(including ed halktoward3he: bottom of_the tubasheet/~ ~ ~ ~~Jfethe repafrj ~ '~

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6. Corrective Measures limit shall All be,plu tubes gedthat leak orby or repaired have degradation a process such as exceeding the plugging.ifj)^I(({sM sleeving *1 ogclass i

agfi u644 prior to return to power from a refueling or inservice i Tnspec; 15~n condition. Sleeved tubes having sleeve degradation exceeding )

40% of the nominal sleeve wall thickness shall be plugged. 1

7. Reports l

4 (a) After each inservice examination, the number of tubes plugged or

repaired in each steam generator shall be reported to the Commission as soon as practicable.

(b) The complete results of the steam generator tube inservice inspection l l shall be included in the Annual Results and Data Report for the l

, period in which the inspection was completed.

l l Reports shall include:

1. Number and extent of tubes inspected.

2. Location and percent of all thickness penetration for each indication.

3. Identification of tubes plugged or repaired.

! (c) Reports required by Table 15.4.2 Steam Generator Tube Inspection 1 shall provide the information required by Specification 15.4.2.A.7(b)

J and a description of investigations conducted to determine cause of

! the tube degradation and corrective measures taken to prevent

! recurrence. The report shall be submitted to the Commission prior to

resumption of plant operation. l

*I Brazed joints shall not be employed. Tubes previously subject to explosive plugging shall not be sleeved.  ;

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l Unit 1 Amendment No. M 15.4.2-4 ";;;:;t 15, 1985

Unit 2 Amendment No. 99 ~l55~dod 9 =a t u

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10 CFR 50.- The same code is utilized for bsth Unit I and Unit 2. Safety--

related components are classified as safety Class 1, 2, or 3. The code boundaries are defined based upon the following documents:

(a} ' Regulatory Guide 1.26, " Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants."

(b) American National Standard N18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants."

, (c) Point Beach Nuclear Plant Units 1 & 2 Final Safety Analysis Report.

Code classified components are tabulated showing each specific examination area and the examination requirements in an inspection interval long-term plan.

This plan is completely revised for each ten-year inspection interval.

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r l Unit 1 - Amendment No. He 15.4.2-6 Auge:t 25, 1004 Unit 2 - Amendment No. M4

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