ML18086B384

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Forwards Addl Info Re Steam Generator Tube Insps 11 & 13. Info Provided in Support of 820209 License Change Request LCR 82-02
ML18086B384
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/05/1982
From: Liden E
Public Service Enterprise Group
To: Varga S
Office of Nuclear Reactor Regulation
References
NUDOCS 8203260176
Download: ML18086B384 (9)
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{{#Wiki_filter:. -* PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, }ID 20014 Attention: Gentlemen: Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing ADDITIONAL INFORMATION STEAM GENERATOR TUBE INSPECTIONS NO. 1 UNIT SALEM GENERATING STATION DOCKET NO. 50-272 March 5, 1982 PSE&G hereby submits, in the enclosure to this letter, a discussion and summary of the No. 11 and No. 13 steam generator tube inspections. This information is provided in support of our License Change Request, LCR 82-02, dated February 9, 1982. Should you have any questions, do not hesitate to contact us. Enclosure CC Mr. Leif Norrholm NRG Senior Resident Inspector Mr. William J. Ross NRG Licensing Project Manager 8203260176 820305 PDR ADOCK 05000272 G PDR Very truly yours, /f&w~ ,.l" / E. A. Liden / Manager - Nuclear Licensing & Regulation 95-2001 !100M) 1-81

Summary STEAM GENERATOR TUBE INSPECTION THIRD REFUELING OUTAGE SALEM GENERATING STATION UNIT NO. 1 Stearn generators No. 11 and No. 13 at Salem Unit No. 1 were inspected by eddy current methods during the third refueling outage as a direct result of tube wall indications detected in the cold leg (outlet) side of peripheral tubes in steam generators No. 12 and No. 14 earlier in the outage. The examinations were performed by Westinghouse Nuclear Service Division during the period February 18-22, 1982, using rnultifrequency techniques. Examinations were essentially limited to the cold leg of the peripheral tubes up to the top (seventh) support plate, although approximately 50 tubes were selected at random from each steam generator for full length tube inspection. As a result of these inspections, six (6) tubes in steam generator No. 11 and seven (7) tubes in steam generator No. 13 were determined to have indications greater than 20% of wall. Of these, four (4) tubes in No. 11 and three (3) tubes in No. 13 had indications equal to or greater than 30% of wall and were subsequently plugged. No indications greater than 39% of wall were observed in either steam generator. Concurrently with these examinations, a defective tube was pulled from No. 14 steam generator and found to have an area of localized wall thinning similar to that observed previously at Prairie Island. Discussion Eddy Current examinations performed on No. 12 and No. 14 steam generators by Virginia Corporation during the early weeks of the third refueling outage indicated a number of defects at lower support plate intersections of peripheral tubes on the cold leg side. According to evaluations performed by a Level II evaluator from Zetec, under contract to Virginia Corp., and a Westinghouse evaluator, under contract to PSE&G, the condition was similar to, or the same as, that observed at Prairie Island in 1980 and 1981. Details of the No. 12 and No. 14 steam generator inspections were provided earlier in License Change Request 82-02, dated February 9, 1982. Since a number of these indications were evaluated as flaws greater than 40% of wall, additional inspections were scheduled for No. 11 and No. 13 steam generators in accordance with Technical Specifications.

.. These inspections were performed by Westinghouse Nuclear Service Division because of their capability of inspecting two steam generators simultaneously. Evaluation was again performed by a Zetec representative under contract to Westinghouse and by a Westinghouse representative. Equipment and technique used was essentially the same as for the earlier inspections, namely a Zetec Ml2-12 multifrequency eddy current system with a Zetec modified Hewlett Packard Model 3968A2 eight-channel magnetic tape recorder, a Brush Model 220 two-channel strip chart recorder and zetec 0.720-inch diameter straight flex probes. Channels wereset for 400 KHz, 100 KHz, and 10 KHz differential at normal gain and 400 KHz differential at reduced gain. Signals from the 400 KHz normal gain and from the 100 KHz mix wereused to evaluate the wall thinning problem. Initial tube samples of 506 tubes each were selected from the cold leg periphery of the two steam generators. This represented a "2S" sample, or 12% of the 3388 tubes in each steam generator plus additional tubes to fill in an arc completely around the periphery. From the initial samples, seven degraded tubes were detected in No. 11 steam generator and four degraded tubes in No. 13. No defective tubes (i.e., 40% of wall or greater) were detected in either steam generator. These results placed the two steam generators into Categroy C-1 according to Technical Specifications, and no further inspections were required. However, to provide an extra margin of safety and additional information for technical purposes, a second sample of 346 tubes, representing an arc approximately 3 tubes wide, was inspected. No additional indications were observed in No. 11 generator but three more degraded tubes were detected in No. 13. Consequently, a third sample of 561 tubes, representing an arc 4 to 5 tubes in from the innermost degraded tube, was examined in No. 13 steam generator. No further indications were observed and examinations were concluded on these two steam generators. Tubes examined and indications recorded are identified in Table 1 and tube maps attached to this report. All examinations were done from the cold leg side, up to the top support plate but approximately 50 tubes were selected at random for a full length inspection in each steam generator. As a result, two indications were observed on tube R20C89, No. 11 generator on the hot leg (inlet) side at 20" and 40" above the fifth support plate. Additional tubes in a cluster around this tube were then inspected, bringing the total full length inspections in this steam generator to 62, but no additional indications were observed in the hot leg side. The

" indications on tube R20C89 were tentatively identified as minor mechanical damage which could have possibly been incurred during fabrication or installation. This was confirmed by Westinghouse after the preservice and first inservice inspection eddy current tapes were reviewed by their Nuclear Technology Division. The cold leg portion of one tube was removed from No. 14 steam generator. This was tube R44C62, which had exhibited a 59% of wall indication at the second support plate. Preliminary on-site visual examination of the tube essentially confirmed the eddy current signal. A broad pit or localized wall thinning penetrating approximately halfway through the wall was observed at the location of the second support plate. One sample tube, in pieces 2 1/2 to 3 1/2 ft. long, has been forwarded to the Westinghouse R&D Center where it is currently undergoing metallurgical examination and chemical analysis. RFB/EAL:sw 3/4/8 2 QD 8 Ol/03A

(' p p p p TABLE 1 STEAM GENERATOR TUBE INSPECTION THIFD REFUELING OUTAGE SALEM GENERATING STATION UNIT NO-~ l EDDY CURRENT TEST RESULTS

  1. 11 Steam Generator Degraded Tubes ( > 20%-< 40% of Wall)

Row Column-9-of-Wall Suppt; Plates*- 0 44 55 35 2 44 56 38 2 45 5-6 39 2 44 59 23 2 44 60 / 30 2 44 62 29 2 Indications were also recorded on the hot leg *side of: one. tube, R20 C8.9, at 20" and.4.0." above.the.5th. suppo"rt..plate;... both to a* depth*of-"24% of-wall'; identifie:d as* me*chanic-al . __ damage.

  1. 13 Steam Generator Degraded' -rubes -(- > 2 0 % < 40% of Wall)

Reported Indications ( < 20% of t.~a-11) Row Column % of Wall p ~ 35 33 p 40 47 ~3 38 63 29 p 36 66 36 34 78 29 34 79 29 30 83 27 P Plu9ged _Suppt. Plate 1 3 -5 3 1 2 1 Row Column Suppt. Plate 39 58 6 All indications on cold leg (outlet) side of steam generator at support plate locations listed above except where noted "\\

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