ML022110275
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ML022110275 | |
Person / Time | |
---|---|
Site: | Indian Point ![]() |
Issue date: | 07/29/2002 |
From: | NRC/NRR/DLPM |
To: | |
Milano, P , NRR/DLPM, 415-1457 | |
References | |
TAC MB5375 | |
Download: ML022110275 (3) | |
Text
g. Pluggingq Limit is the degradation depth at or beyond which the tube must be plugged or repaired.
- h. Hot-Leg Tube Examination is an examination of the hot-leg side tube length. This shall include the length from the point of entry at the hot-leg tube sheet around the U-bend to the top support of the cold leg.
Cold-Leg Tube Examination is an examination of the cold-leg side tube length. This shall include the tube length between the top support of the cold leg and the face of the cold-leg tube sheet.
- 2. Extent and Frequency of Examination
- a. Steam generator examinations shall be conducted not less than 12 months nor later than twenty four calendar months after the previous examination.
- b. Scheduled examinations shall include each of the four steam generators in service.
Amendment No. 230 4.13-2
- c. Unscheduled steam generator examinations shall be required in the event there is a primary to secondary leak exceeding technical specifications, a seismic occurrence greater than an operating basis earthquake, a loss-of-coolant accident requiring actuation of engineered safeguards, or a major steamline or feedwater line break.
- d. Unscheduled examinations may include only the steam generator(s) affected by the leak or other occurrence.
- 3. Basic Sample Selection and Examination
- a. At least 12% of the tubes in each steam generator to be examined shall be subjected to a hot-leg examination.
- b. At least 25% of the tubes inspected in Specification 4.13.A.3.a above shall be subjected to a cold-leg examination.
- c. DELETED
- d. Tubes selected for examination shall include, but not be limited to, tubes in areas of the tube bundle in which degradation has been reported, either at Indian Point 2 in prior examinations, or at other utilities with similar steam generators.
- e. DELETED
- f. Examination shall be by eddy current techniques as specified by the steam generator examination program submitted to the NRC in accordance with TS 4.13.C.1. In all cases, a probe with at least a 610 mil diameter shall be used.
Amendment No. 230 4.13-3
- 4. Additional Examination Criteria
- 1. Degradation
- a. If 5% or more of the tubes examined in a steam generator exhibit degradation or if any of the tubes examined in a steam generator are defective, additional examinations shall be required as specified in Table 4.13-1.
- b. Tubes for additional examination shall be selected from the affected area of the tube array and the examination may be limited to that region of the tube where degradation or defective tube(s) were detected.
- c. The second and third sample inspections in Table 4.13-1 may be limited to the partial tube inspection only, concentrating on tubes in the areas of the tube sheet array and on the portion of the tube where tubes with imperfections were found.
Amendment No. 230 4.13-4