ML19274E662
| ML19274E662 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/13/1979 |
| From: | William Cahill CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904170134 | |
| Download: ML19274E662 (20) | |
Text
{{#Wiki_filter:. William J. Cahill, Jr. Vice Prestent Censol. dated Edesn Company of New York. Inc. 4 Irving Place. New York. N Y 10003 Telephone (212) 460 3819 April 13, 1979 Re: Indian Point Unit No. 2 Docket No. 50-247 Director of Nuclear Reactor Regulation ATI'N: Mr. A. Schencer, Chief , Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Ca mission hbshington, U. C. 20555
Dear Mr. Schwencer:
As required by Attendment Number 40 to Facility Operating License Ib. DPR-26, we are planning a Steam Generator Inspection Program during the third refueling outage of Indian Point Unit No. 2. This outage is scheduleci to ccamence in June , 19T'. As you have requested, we herewith suhnit, as Attacnment A, the details of the Steam Generator Inspection Program planned for Indian Point Unit No. 2. In orc.er to facilitate coordinated planning fa the refueling outage, we require a finalized Program by May 15, 1979. We m uld appreciate your concurrence by that date. Should you or your Staff have any questions regarding thic inspection program, we muld be pleased to discuss than with you at your earliest convenience. Very truly yours,
/
[- f _/ , William J. Cahill, Jr. attach. Vice President
'i904.0013 Y
J.. . ATTACHMENT A INDIAN POINT UNIT NO. 2 DOCKET NO. 50-247 STEAM GENERATOR INSPECTION PROGRAM Planned for the Third Refueling Outage June 1979
INTRODUCTION The first inservice inspection of the steam generators was performed during the first refueling outage for Indian Point Unit No. 2 which occurred in 1976. Eddy current inspections for tube defects and dents were performed on Steam Generators 21 and 22, in accordance with Technical Specification requirements. In addition, a visual and photographic examination of the first (bottom) tube support plate in all four steam generators was made. A special inspection of the steam generators was performed during the November, 1976 unit outage. Eddy current inspections for tube defects and denting were carried out on Steam Generators 23 and 24. During this outage, a " hillside" inspection port was made in Steam Generator 22. Through this port, an inspection was performed on that steam generator's top (sixth) tube support plate. A description of the inspection program was submitted to the NRC by letter dated October 26, 1976. The results of the inspection were submitted to the NRC by letter dated November 18, 1976. In April,1977, another special inspection of the Indian Point Unit No. 2 steam generators was performed. This inspection included eddy current exami-nations for tube defects and denting in Steam Generators 21 and 22. In addi-tien, the lower tube support plates in Steam Generators 21 and 22 were examined and photographed through the lower handholes, and the top tube support plate in Steam Generator 22 was examined and photographed through the " hillside" port. A description of the inspection program was submitted to the NRC by letter dated February 22, 1977. The results of the it.spection were submitted to the NRC by letter dated May 6, 1977. In February and March, 1978, an inspection of steam generators was performed during the unit's second refu111ng outage. These inspections satis-fled both the inservice inspection requirements described in the Facility Technical Snecifications and the requirements for a tube denting / support plate hourglassing examination described in Amendment Number 30 to the Facility Operating License No. DPR-26. The inspection program included: (a) Eddy current examination of tubes in Steam Generators 23 and 24 for defects and for dents. (b) Visual and photographic examination of the first (bottom) tube sup-port plates in all four steam generators. Where feasible, higher tube support plates were photographed and examined. (c) Visual and photographic examination of the innermost tube U-bends and flow slots in~ the top tube support plate of Steam Generator 22 through the " hillside" port provided in the steam generator shell. (d) Photographic examination of the wrapper to support plate annulus using the hand hole above the tube sheet in Steam Generator 24. (e) Sampling and chemical analysis of sludge lanced from all four steam generator tube sheets. (f) Removal of a tube / tube support plate sample from Steam Generator 23 for laboratory metallurgical examination. (g) Installation of five new one-inch inspection ports on the shell of Steam Generator 24 (one inspection port above each of the lower four support plates, and one on the " hillside" above the uppermost support plate). A description of the second refueling outage steam generator inspection program was submitted to NRC by letter dated January 11, 1978. A detailed discussion of the results of the inspection program was sdbmitted to NRC by lctters dated March 24, 1978 and May 4, 1978. The steam generator inspections planned for the upcoming third refuel-ing outage will satisfy both the inservice inspection requirements described in the Facility Technical Specifications and the requirements for a tube dent-ing examination described in Amendment Number 40 to the Facility Operating License No. DPR-26. The third refueling outage is scheduled to commence in June, 1979. PROPOSED PROGRAM DESCRIPTION The following program of steam generator inspections is planned for Indian Point Unit No. 2 during its third refueling outage. (1) Steam Generator Eddy Current Examination A sample group of tubes in the hot legs of Steam Generators 21, 22, 23, and 24 will be eddy current inspected for dents and defects. The scope of the inspection for defects exceeds the requirements of the Indian Point Unit No. 2 Technical Specifications. The sample of tubes selected for inspection is comprised of those in the peripheral hard spot regions, those adjacent to the flow slots and the patch plate / support plate bound-ary, plus a small number of tubes across the bundle. The tubes selected were previously eddy current examined, so that it will be possible to epm-pare results directly on a tube-for-tube basis. Steam Generators 21 and 22 were previously examined in April, 1977, in accordance with Technical Specification requirements. Steam Generators 23 and 24 were previously examined in February, 1978, although Technical Specifications required that only one steam generator be examined at that time. Technical 1cifications require that 12% of the tubes in the fourth steam generator be examined at this time. It is proposed to examine 12% of the tubes in Steam Generator 24 to meet this requirement. To meet the additional requirement of Amendment Number 40, it is proposed to examine 12% of the tubes in each of Steam Generators 21 and 22, and 8% of the tubes in Steam Generator 23. A smaller sample is proposed for Steam Generator 23 because it was previously examined in 1978, tube conditions were fou: d to be essentially symmetrical in the bundle, and it is desired to keep personnel exposure as low as reasonably achievable. A standard '/00 mil eddy current probe will be used to perform eddy current testing. If any tube does not permit passage of the standard 700 mil probe, successively smaller probes shall be used until the size of the restriction is quantified. If a tube does not permit passage of the 610 mil probe, either the tube will be plugged, or an evaluation will be performed to demonstrate why the tube need not be plugged. This evalua-tion will be submitted to the Nuclear Regulatory Commission with the results of this inspection program. In addition, the tubes immediately adjacent to any tube that may not pass the 610 mil probe will be subjected to inspection. Locations of the hot leg tubes in Steam Generator 21, 22, 23, and 24 which will be eddy current inspected for dents and defects are given in Tables 1 through 4 and Figures 1 through 4. To the extent practical, this shall include the length of tube from the point of entry in the steam generator hot leg water box, around the U-bend, and to the top tube support plate of the cold leg.* The eddy current inspection for tube defects will be performed nominally at 400 KHz at standard gain. The inspection to identify tube dents will be performed nominally at 400 KHz and at a reduced gain.
*Because of the small radius bends of the tubes nearer the flow slots (rows 1 through 5) in the steam generators, passage of the probe around the U-bend in these tubes is not practical.
(2) Flow Slot and Support Plate Inspections Using the hand holes above the tube sheet for all four steam generators, a visual and photographic examination of the tube support plates will be made. This examination will include the first (bottom) tube support plate and, where feasible, higher support plates. Data obtained from this inspection will be reported. (3) Top Support Plate Inspection of Steam Generators 22 and 23 The three flow slots in the top tubo support plates closest to the " hillside" inspection ports of Steam Generators 22 and 23 will be visually and photographically exaT.ined, utilizing a borescope. Results will be reported. h (4) Additional Inspections Con Edison is currently working with another company to develop a probe to determine the actual shape of a tube, in order to be able to calculate the strain in the tube wall. It is planned that a sampling of tubes in Steam Generator 23 will be probed, and attempts will be made to correlate projected support plate strain and indicated tube strain. If feasible, and if the information developed is deemed to be reliable, tube plugging criteria will be developed on the basis of a strain level at which tubes may become susceptible to stress corrocinn cracking. The findings will be reported to the Nuclear Regulatory Commission subsequent to our examination. (5) Evaluation and Reporting of Results The results of the planned inspection at Indian Point Unit No. 2 will be evaluated by Con Edison,. A report of these evaluations will be forwarded to the Nuclear Regulatory Commission as soon as it is available. _9_
TABLE 1 PROPOSED 1979 EDDY CURRENT EXAMINATION STEAM GENERATOR 21 (HOT LEG) Row Column Number 2, 3 11 through 20, 27 through 35 80 56 through 66, 73 through 82 6 51 1 7, 8 1 through 5, 88 through 92 20 9 2 through 5, 51, 88 through 91 9 10, 11 2 through 5, 88 through 91 16 12 2 through 5, 51, 88 through 91 9 13, 14 3 through 5, 88 through 90 12 15 3 through 5, 51, 88 through 90 7 18 51 1 21 15, 18, 21, 24, 27, 30, 33, 36, 13 39, 42, 45, 48, 51 24, 27 51 2 28, 29 11 through 17, 76 through 82 28 30 12 through 17, 51, 76 through 81 13 31 15, 16, 17, 76, 77, 78 6 32, 33 15, 16, 17, 39 through 54, 76 44 77, 78 34 16, 17, 39, 40, 53, 54, 76, 77 8 35 17, 39, 40, 53, 54, 76 6 36, 37, 38, 39, 40, 53, 54 20 39, 40 41 27 through 40, 53 through 66 28 42 29 through 40, 53 through 64 24 43 32 through 40, 53 through 61 18 44 35 through 58 24 45 39 through 54 16 Total 405 TABLE 2 PROPOSED 1979 EDDY CURRENT EXAMINATION STEAM GENERATOR 22 (HOT LEG) Row Column Number 2, 3 11 through 20, 27 through 35, 80 56 through 66, 73 through 82 6 50 1 7, 8 1 through 5, 88 through 92 20 9 2 through 5, 50, 88 th'.cugh 91 9 10, 11 2 through 5, 88 through 91 16 12 2 through 5, 50, 88 through 91 9 13, 14 3 through 5, 88 through 90 12 15 3 through 5, 50, 88 through 90 7 18 50 1 21 14, 17, 20, 23, 26, 29, 32, 35, 13 38, 41, 44, 47, 50 24, 27 50 2 28, 29 11 through 17, 76 through 82 28 30 12 through 17, 50, 76 through 81 13 31 15 through 17, 76 through 78 6 32, 33 15 through 17, 39 through 54, 44 76 through 78 34 16, 17, 39, 40, 53, 54, 76, 77 8 35 17, 39, 40, 53, 54, 76 6 36 through 40 39, 40, 53, 54 20 41 27 through 40, 53 through 66 28 42 29 through 40, 53 through 64 24 43 32 through 40, 53 through 61 18 44 35 through 53 19 45 39 through 50 12 Tota l 396 TABLE 3 PROPOSED 1979 EDDY CURRENT EXAMINATION STEAM GENERATOR 23 (HOT LEG) Row Column Number 2, 3 14 through 37 48 4 1 t.. . ugh 14 14 7, 8 1 through 6 12 9 2 through 6, 46 6 10, 11 2 through 6 10 12 2 through 6, 46 6 13, 14 3 through 6 8 15 3 through 6, 46 5 18 46 1 21 16, 19, 22, 25, 28, 31, 34, 37, 11 40, 43, 46 24, 27 46 2 28, 29 11 through 17 14 30 12 through 17, 46 7 31 15, 16, 17 3 32, 33 15, 16, 17, 39 through 46 22 34 16, 17, 39, 40 4 35 17, 39, 40 3 36, 37, 38, 39, 40 10 39, 40 41 27 through 40 14 42 29 through 40 12 43 32 through 40 9 44 35 through 58 24 45 39 through 54 16 Total _ 261 TABLE 4 PROPOSED 1979 EDDY CURRENT EXAMINATION STEAff GENERATOR 24 (ilOT LEG) Row Column Number 2 2 thvsugh 20, 26 through 31, 47 56 chrough 66, 73 through 83 3 10 through 20, 26 through 31, 39 56 through 66, 73 through 83
) 1 through 5 5 8 1 through 5, 88 through 92 10 9, 10, 11 2 through 5, 88 through 91 24 12 2 through 5, 46, 88 through 91 9 13, 14 3 through 5, 88 through 90 12 15 3 through 5, 46, 88 through 90 7 18 46 1 21 13, 16, 19, 22, 25, 28, 31, 34, 12 37, 40, 43, 46 24 46 1 27 10 through 17, 46 9 28 13 through 17, 76 through 82 12 29 11 through 17, 76 through 82 14 30 12 through 17, 46, 76 through 81 13 31 15 through 17, 76 through 78 6 32, 33 15 through 17, 39 through 54, 44 76 through 78 34 16, 39, 30, 53, 54, 76, 77 7 35 18, 39, 40, 53, 54, 75, 76 7 36, 37, 38, 39, 40, 53, 54 16 39 40 39, 40, 54 3 TABLE 4 (CON' T)
PROPOSED 1979 EDDY CURRENT EXAMINATION STEAM GENERATOR 24 (IIOT LEG) Row Column Number 4? 27 through 40, 53 through 66 28 42 29 through 40, 53 through 64 24 43 32 through 40, 53 through 61 18 44 35, 39 through 53, 57 & 58 18 45 40 through 54 15 Total 401 FIGURE 1 m + .. m_ e a . ,~o , n_ . .,~
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