ML20206G148

Special Rept 86-06:on 860303-31,first Eddy Current Inservice Insp Performed on Steam Generators a & D to Meet Tech Spec 3/4.4.5 Surveillance Requirements.Number of Tubes Containing Imperfections Encl

ML20206G148
Person / Time
Site:	Callaway
Issue date:	03/09/1987
From:	Randolph G UNION ELECTRIC CO.
To:	Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
86-06, 86-6, ULNRC-1459, NUDOCS 8704140462
Download: ML20206G148 (6)

Text

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      ' Union                                                                                       .

Etscraic March 9, 1987 Caraway Plant Mr. A. Bert Davis Acting Regional Administrator . T g U.S. Nuclear Regulatory Commission , Region III - tb 799 Roosevelt Road Glen Ellyn, IL 60137

                                                                               -{7 fctd       -

ULNRC-1459 M^

Dear Mr. Davis:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPEPATING LICENSE NPF-30 SPECIAL REPORT 86-06 RESULTS OF FIRST STEAM GENERATOR TUEE INSERVICE INSPECTION Ref: ULNRC 1283, dated April 15, 1986 The enclosed Special Report is submitted pursuant to the requirements of Callaway Technical Specification 4.4.5.5.b concerning the first Inservice Eddy Current Inspection of Steam Generators 'A' and

                 'D' performed from 3/3/86 to 3/31/86 during Refuel I. This report is also being submitted to forward the final Westinghouse results of the inspection.

42LA) G. L. Randol Manager, Callaway Plant

                      / S/$f /drs

Enclosures:

Special Report 86-06 Westinghouse Field Service Report cc: Distribution attached 8704140462 870309 RDR ADOCK 05000483 l 3# PDR S\ l MaMg ktitess P.O. Box GQ FuM MO 65251 3&Ol E_

x -+ a  % a cc distribution for ULNRC-1459 Mr. Paul O'Connor- (2 copies) Manager, Electric Department (Encl: Westinghouse Sve. Report) Missouri Public Service Commission Office of Nuclear Reactor Regulation P. O. Box 360 1 U.S. Nuclear Regulatory Commission Jefferson City, MO 65102 Mail Stop P-316 l 7920 Norfolk Avenue Mr. O. Maynard i Bethesda, MD 20014 Wolf Creek Nuclear Operating' Corp. P. O. Box 208 ! American Nuclear Insurers Wichita, KS 62701 c/o Dottie Sherman, Library The Exchange Suite 245 Mr. Nicholas A. Petrick 270 Farmington Avenue Executive Director, SNUPPS Farmington, CT 06032 5 Choke Cherry Road Rockville, MD 20850 , Mr. N. P. Coel

Bechtel Power Corporation Records Center 1

SNUPPS Project Institute of Nuclear Power Operations ] 15740 Shady Grove Road Suite 1500 1 Gaithersburg, MD 20877-1454 1100 circle 75 Parkway j Atlanta, GA 30339 NRC Resident Inspector Mr. Merlin Williams i D. F. Schnell (400) Supt. of Regulatory Quality & i R. J. Schukai (470) Administrative Services S. E. Miltenberger Wolf Creek Nuclear Operating Corp. ' J. F. McLaughlin P. O. Box 309 , J. E. Davis (Z40LER) Burlington, KS 66839 i (Z40LER) (w/c) { D. W. Capone /R. P. Wendling (470) F. D. Field (480) A. P. Neuhalfen

A. C. Passwater/D. E. Shafer/D. J. Walker (470)

G. A. Hughes

Z40.03 (QA Record)

J. M. Price 1 R. D. Affolter 4

M. E. Taylor H. Wuertenbaecher, Jr. (100) i S. L. Auston (470)(NSRB)

S. J. Bellers/J. D. Schnack l GLR Chrono i

3456-0021.6

;                   3456-0260 Z40ULNRC C56.37 i                    N. Date (Sandra Auston) (470) i
)

j 1 i

SPECIAL REPORT 86-06 RESULTS OF FIRST STEAM GENERATOR TUBE INSERVICE INSPECTION This report is being submitted in accordance with Technical Specification (T/S) 4.4.5.5.b which states:

               "The complete results of the steam generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.

This Special Report shall include:

1) Number and extent of tubes inspected,

2) Location and percent of wall-thickness penetration for each indication of an imperfection, and

3) Identification of tubes plugged."

From 3/3/86 to 3/31/86, the first Steam Generator (SG) Eddy Current Inservice Inspection was performed on SG's 'A' and 'D' to meet the surveillance requirements of T/S 3/4.4.5, " Steam Generators." The inspection was performed by Westinghouse Electric Corporation and their formal results are detailed in the Field Service Report (FSR) which is being submitted with this Special Report. The inspections commenced on 3/3/86 with the plant in Mode 4, Hot Shutdown, and continued during the refueling. The inspections were completed on 3/31/86 with the plant in Mode 5, Cold Shutdown, while returning the plant to power operation. Although the Westinghouse FSR provides details on the inspection, the results are summarized below and are numbered to correspond with the information requested per T/S 4.4.5.5.b:

1. Number / Extent of Inspected Tubes

a. Steam Generator 'A': A total of 401 tubes were inspected from the Hot Leg side; 37 of these were tested through the U-bend, 363 were tested full length, and I was inspected to the eighth Tube Support Plate (TSP)-Hot Leg,

b. Steam Generator 'D': A total of 1136 tubes were inspected from the Hot Leg side; 122 were tested through the U-bend, and 1014 were tested dull length.

2. Location / Percent of Wall-Thickness Penetration for Each Indication of Imperfection

SPECIAL REPORT 86-06 Page 2

                                                                                         )

Number of Tubes Containing Imperfections in Steam Generator

                          'A' - 22 (detailed below)                                      l Table 1 Tube Imperfections on Steam Generator 'A' Indication                Inch (+)

(% of Wall (from Row Column Leg Thickness) Location Location) 9 3 C <20 2 2.5 20 5 C <20 2 36.8 21 6 C <20 1 6.4 28 9 H <20 7 34.6 32 10 H DI V3 0.0 27 30 H DI 7 12.4 27 30 H DI 7 30.5 30 31 C 31 6 15.7 27 39 C <20 2 33.5 5 42 C <20 2 19.3 19 42 C 22 1 12.9 49 48 C 25 7 3.4 21 49 C <20 6 27.1 54 57 H 25 2 19.0 55 58 H 29 5 18.1 6 61 C 36 4 22.1 28 87 H 23 TS 2.8 15 91 H 25 4 15.6 15 91 H 22 4 20.6 45 91 H 35 4 31.9 36 97 C <20 6 7.5 33 100 H 27 6 6.4 44 102 H

                                        ,               <20          7          10.9 37            103           C           23         4            2.6 Key 7- Tables 1 and 2:

DI - Distorted Imperfection TS - Tube Sheet INR - Indication Not Recordable (<10%) TH - Inside Hot Leg Portion of Tube Sheet

     /

VI,3 - Anti-Vibration Bar #1 and #3 1,2,3,4,5,6,7 - Tube Support Plate Numbers F W m

SPECIAL REPORT 86-06 Paga 3 Number of Tubes Containing Imperfections in Steam Generator

                      'D' - 27 (detailed below)

Table 2 Tube Imperfections on Steam Generator 'D' Indication Inch (+) (% of Wall (from Row Column Leg Thickness) Location Location) 13 5 H <20 2 3.7 41 19 H <20 3 23.9 41 19 H <20 3 32.1 41 19 H <20 4 2.7 41 19 H <20 4 5.5 43 21 H 28 TH 0.0 19 22 H <20 4 32.3 1 23 H INR 7 30.0 1 23 H INR 7 31.0 1 23 H INR 7 32.0 41 23 H 29 6 21.4 5 27 H <20 7 38.7-39 30 H <20 1 7.4 15 34 H <20 1 15.5 13 36 H <20 2 36.0 36 38 H 20 5 30.1 39 38 H 22 2 38.0 17 44 H 27 5 28.3 17 44 H <20 5 34.0 23 58 C <20 3 34.0 7 64 H 25 7 13.5 49 64 H DI 3 23.7 45 68 C <20 1 4.7 45 71 H 35 VI 2.8 33 79 H <20- 5 15.0 33 80 H <20 4 12.6 56 81 H 38 TS 4.2 33 83 C 24 6 31.9

e . SPECIAL REPORT 86-06 Page 4 Table 2 Tube Imperfections on Steam Generator 'D' (Cont.) Indication Inch (+) (% of Wall (from Row Column Leg Thickness) Location Location) 27 91 C 21 5 24.9 1 96 H 27 7 23.7 7 96 H <20 7 29.4 ' 30 103 H 26 4 37.5 5 115 C <20 3 14.3

3. Identification of Tubes Plugged None.}}