1981 refueling outage report for oconee station unit #3 · subject: revision 1 to the 1981...
TRANSCRIPT
REPORT NUMBER: ASSIGNED TO:
CONTROLLED: UNCONTROLLED: X
OWNER: DUKE POWER COMPANY P. 0. Box 33189 Charlotte, NC 28242
1981 REFUELING OUTAGE
INSERVICE INSPECTION REPORT FOR OCONEE STATION UNIT #3
LOCATED AT: SENECA, SOUTH CAROLINA
599-0443-14-08
REVISION: 1 DATE:
COMPONENTS: B&W NSS-9 and other components as
identified in this report
MANUFACTURER: BABCOCK & WILCOX COMPANY LYNCHBURG, VIRGINIA 24505
GROSS GENERATING CAPABILITY: 2568 MWT COMMERCIAL SERVICE DATE: December 16, 1974 DATE OF INSPECTION: See Preface ABSTRACT OF INSPECTION: See Summary Report
APPROVED BY: M C. R. Honey d, Manager, Manuals & Report Date
Babcock & W cox Company
APPROVED BY: ti/ C-.( 7L/ J .p. hinney, Msnager, Inservice Inspection Date Babco & Wilcox Company
APPROVED BY: _ _ _ ___ _ _ J/ . rbour, Quality Assurance, Operations Date ak1 Power Company
BABCOCK & WILCOX INSERVICE INSPECTION P. 0. Box 1260 Lynchburg, VA 24505
8107210421 810714 -1 PDR ADOCK 05000287 G _ PDR
Babcock & Wilcox Nuclear Power Generation Division
a McDermott company 3315 Old Forest Road P.O. Box 1260 Lynchburg, Virginia 24505 (804) 384-5111
July 6, 1981
Mr. C. B. Cheezem Duke Power Company Quality Assurance Operations P. O..Box 33189 Charlotte, NC 28242
File: 0443-B.039 Ref: 599-0443-14-08
Subject: Revision 1 to the 1981 Inservice Inspection Report for Oconee Station, Unit #3
Dear Mr. Cheezem:
The following changes are being transmitted to you for your approval and insertion into the .two copies of the report (1 and 2) in your possession.
Action; Replace, Description of Item Description Remove, or Insert Modification
1. Title Page (Sign) replace at Revision #1 later date
2. Table of Contents Replace Revision #1 to page T-1 Changed date to 7-6-81 Changed Revision to #1 in Sections 11.0-11.4, and 15.0
3. Page 11-1 thru Replace Changed Revision to #1 11-3 Changed date to 7-6-81
Changed the first sentence of the third paragraph on page 11-2 to read; Steam Generator "B" had 24 tubes ... of wall thickness.
4. Page 15-1 thru Replace Changed Revision to #1 15-6 Changed date to 7-6-81
Changed page 15-2, item #8 under "Date", by adding "Revised page 2, on 7-6-81".
*e 0
-2
5. Section 11, Tab-G Replace Corrected the Levels
Page 90 of 179 of the evaluator and the reviewer.
6. Section 15, Tab-Q Replace Corrected the last Page #2 of M. J. sentence to read 24 Gallagher's letter tubes, and remove3the dated 3-6-81. last tube in column
under "B" generator.
Upon approval, please sign the Revision #1 title page in the place indicated and return it to P. L. Pitz at the address indicated below. Please note that the revision #1 title page is not yet dated. The date that will be shown is that of the Duke Power
Compan's approval signature. Copies of the approved title page will then be sent to you for inclusion in your copies of the
report.
Babcock & Wilcox Co. Customer Service, Inservice Inspection P. 0. Box 1260 Lynchburg, VA 24505
Sincerely,
THE BABCOCK & WILCOX CO.
T. E. Smith Contract Management Inservice Inspection
TES:meh Distribution:
Report Assigned To:
1 CB Cheezem 2 CB Cheezem 3 CR Honeycutt 4 File 5 File (Microfilm)
REV. 1
DATE: 7-6-81
PAGE: T-1
TABLE OF CONTENTS
Section Revision
PREFACE 0
SUMMARY REPORT 0
1.0 CURRENT-INSERVICE INSPECTION PLAN, OUTAGE 5 0
2.0 REACTOR VESSEL DATA 0
3.0 PRESSURIZER DATA 0
4.0 CLASS 1 STEAM GENERATOR DATA 0
5.0 CLASS 1 PIPING DATA 0
6.0 CLASS 1 PUMP DATA 0
7.0 CLASS 1 VALVE DATA 0
8.0 CLASS 2 VESSEL DATA 0
9.0 CLASS 2 PIPING DATA 0
10.0 CLASS 2 HANGERS 0
10.1 CLASS 3 HANGERS 0
11.0 AUGMENTED INSPECTION DATA 1
11.1 AUGMENTED LEAK TEST 1
11.2 STEAM GENERATOR TUBES 1
11.3 REACTOR COOLANT PUMP MOTOR FLYWHEEL 1
11.4 CLASS 1 LEAK TEST 1
12.0 PERSONNEL CERTIFICATIONS 0
13.0 MATERIAL AND EQUIPMENT CERTIFICATIONS 0
14.0 CALIBRATION SHEETS 0
15.0 REFERENCE DOCUMENTS
REV. 1
DATE: 7-6-81
PAGE: 11-1
11.0 AUGMENTED INSPECTION DATA
11.1 AUGMENTED LEAK TEST (TAB "E")
Ten piping systems were examined by visual examination
(LO.3.1, LO.3.2, LO.3.3, LO.3.4, LO.3.5, LO.3.8, LO.3.9,
LO.3.10, LO.3.12, and LO.3.13). Of these, only 4 had conditions
which were reported via the evaluation reports as noted below:
LO.3.5 ER #599-0443-011 LO.3.9 ER #599-0443-007, LO.3.10 ER #599-0443-010 LO.3.13 ER #599-0443-097
The utility representative documented that the conditions are
acceptable as is and this is noted on the evaluation reports which
are located in Section 15.0, Reference Documents.
REV. 1
DATE: 7-6-81
PAGE: 11-2
11.2 STEAM GENERATOR TUBES (TABS "F" & "G")
The inconel tubing (Figure XO.1.1 and X0.1.2) of the 2A & 2B
steam generators was examined per NRC Regulatory Guide 1.83 using
eddy current techniques. This is described in M. J. Gallagher's
letter to file dated March 6, 1981, in Section 15.0 of this report.
As a result of-this examination, it was found that 4 of the
tubes in steam generator "A" had indications equal to or exceeding
20% of the wall thickness. Approximately ten percent of the tubes
were examined in the "A" generator, the data for which is presented
following Tabs "F". No tubes exceeded the 40% plugging limit.
Steam generator "B" had 24 tubes with indications equal to or
greater than 20% of the wall thickness. Four of these (150-14, 4-4,
58-2, and 62-113) had indications exceeding the 40% plugging limit
and had to be taken out of service. Approximately 21% of the tubes
were examined in."B" generator, the data for which is presented
following tab "G". No other tubes exceeded the plugging limit.
REV. 1
DATE:7-6-81
PAGE: 11-3
11.3 REACTOR COOLANT PUMP MOTOR FLYWHEEL (TAB "H")
Ultrasonic examinations of the bore and keyway areas for each
of the four reactor coolant pump motor flywheels (Figures XO.2.1,
XO.2.3, XO.2.5, and XO.2.7) were performed. No recordable
indications were observed during these examinations.
11.4 CLASS 1 LEAK TEST (TAB "J")
The Class i leak test (figure.XO.3.1) as identified in Section
4.0 of the Inservice Inspection Manual was performed in accordance
with the requirements. of IWA & IWB-5000 of the Section XI Code. No
recordable indications were observed during the visual examination
except for minor leaks as noted on Figure XO.3.1.
REV. 1
DATE: 7-6-81
PAGE: 15-1
15.0 REFERENCE DOCUMENTS
This section contains the letters, documents, nonconforming
items reports, and evaluation reports which pertain to various
technical considerations referenced throughout this report.
15.1 LETTERS AND DOCUMENTS (TAB "Q")
Item Letter/Documents Date
1. D. E. Guilbert, to Distribution "C" 12-16-81
Subject: Authorization for approval of Eddy Current FCA's.
2. T. F. McDermott to H.W. Stoppelmann 12-17-80
Subject: NCR's 80-1 thru 80-8
a 3. T. F. McDermott to Randy Klein 1-19-81
Subject: Justification for Deviations. from Code Requirements
4. T. E. Smith to File 1-21-81 Subject: Percentage of NDE
performed on Class 2 bolting.
Attachment Included; A) Letter from A. J. Hogge dated
8-7-.80.
5. Report of Inspection, L. M. Elliot 1-22-81
QA.
Attachments Included: A) Personnel Qualifications B) Equipment C) Equipment D) Consumable Materials E) Calibration Blocks and Data
REV. 1
DATE:7-6-81
PAGE: 15-2
15.1 LETTERS AND DOCUMENTS (TAB "Q") CONT'D
Item Letter/Documents Date
6. Letter from'J. Crowe, (DPC, QA) 1-26-81
Subject: Receipt of Radiographs
7. T. E. Smith to C. B. Cheezem 3-3-81
Subject: Response to NRC's Unresolved Item on Oconee-3 1980 Outage.
8. M. J. Gallagher to File 3-6-81
Subject: Steam Generator Eddy Revised Page2 Current Examination for on 7-6-81 Oconee 3.
9. T. E. Smith to C. B. Cheezem 3-6-81
Subject: Oconee .3 Welded Lug Field Check
10. P. L. Pitz to File 3-7-81 Subject: Mag Particle Examination
of Welds Scheduled for RT After Grinding
REV. 1
DATE: 7-6-81
PAGE: 15-3
15.2 LETTNONCONFORMING ITEM REPORT (TAB "R")
Item Serial Number Attachments
1. 80-1 N/A
2. 80-2 PQ, Data Sheet
3. 80-3 N/A
4. 80-4 N/A
5. 80-5 N/A
6. 80-6 N/A
7. 80-7 N/A
8. 80-8 N/A
9. 80-9 Letter from M.G. Hacker dated 1-20-81
10. 80-10 N/A
11. 80-11 N/A
12. 80-12 N/A
13.. 80-13 Letter from M.G. Hacker dated 1-20-81
14. 80-14 N/A
15. 80-15 N/A
16. 0-475 N/A
17. 0-485 1
18. 0-488 N/A
19. 0-494 1
20. 0-507 1
21. 0-510 1
22. 0-519 N/A
23. 536 N/A
24. WR-50933 N/A
25. WR-66568 N/A
REV. 1
DATE: 7-6-81
PAGE: 15-4
15.3 EVALUATION REPORTS (TAB "W")
Item Figure Number Report Number
1. N/A 599-0443-001
2. N/A 599-0443-002
3. N/A 599-0443-003
4. N/A 599-0443-004
5. N/A 599-0443-005
6. N/A 599-0443-006
7. LO.3.9 599-0443-007
8. N/A 599-0443-008
9. C2.6.8 599-0443-009
10. LO.3.10 599-0443-010
11. LO.3.5 599-0443-011
12. N/A 599-0443-012
13. N/A 599-0443-013
- 14. N/A 599-0443-014
15. N/A 599-0443-015
16. N/A 599-0443-016
17. N/A 599-0443-017
. 18. N/A 599-0443-018
19. N/A 599-0443-019
20. N/A 599-0443-020
21. N/A 599-0443-021
22. N/A 599-0443-022
23. N/A 599-0443-023
24. N/A 599-0443-024
25. N/A 599-0443-025
26. N/A 599-0443-026 27. N/A 599-0443-027
28. C2.6.52 599-0443-028 29. C2.6.61.8 599-0443-029
30. C2.6.64 599-0443-030 31. C2.6.65.2 599-0443-031
32. C2.6.65.8 599-0443-032
33. C2.6.68 599-0443-033
34. B4.7.5 599-0443-034
35. B6.9.6 599-0443-035
36. B4.1.56 599-0443-036
37. C2.1.66 599-0443-037
38. C2.1.69 599-0443-038
39. C1.2.1 599-0443-039
40. N/A 599-0443-040
41. N/A 599-0443-041
REV. 1
DATE: 7-6-81
PAGE: 15-5
Item Figure Number Report Number
42. N/A 599-0443-042 43. N/A 599-0443-043
. 44. C1.4.12 599-0443-044 45. N/A 599-0443-045 46. N/A 599-0443-046 47. N/A 599-0443-047 48. N/A 599-0443-048 49. N/A 599-0443-049 50. N/A 599-0443-050 51. N/A 599-0443-051 52. N/A 599-0443-05,2 53. N/A 599-0443-053 54. N/A 599-0443-054 55. N/A 599-0443-055 56. N/A 599-0443-056 57. N/A 599-0443-057 58. N/A 599-0443-058 59. N/A 599-0443-059 60. N/A 599-0443-060 61. N/A 599-0443-061 62.. N/A 599-0443-062 63. N/A 599-0443-063 64. N/A 599-0443-064 65. N/A 599-0443-065 66. N/A 599-0443-066 67. N/A 599-0443-067 68. N/A 599-0443-068 69. N/A 599-0443-069 70. N/A 599-0443-070 71. N/A 599-0443-071 72. N/A 599-0443-072 73. N/A 599-0443-073 74. N/A 599-0443-074 75. N/A 599-0443-075 76. N/A 599-0443 -076 77. N/A 599-0443-077 78. N/A 599-0443-078 79. N/A 599-0443-079 80. N/A 599-0443-080 81. N/A 599-0443-081 82. N/A 599-0443-082 83. N/A 599-0443-083 84. N/A 599-0443-084 85. N/A 599-0443-085 86. N/A 599-0443-086
REV. 1
DATE: 7-6-81
PAGE: 15-6
Item Figure Number Report Number
87. N/A 599-0443-087
88. N/A 599-0443-088
89. N/A 599-0443-089
90. N/A 599-0443-090
91. N/A 599-0443-091
92. N/A 599-0443-092
93. N/A 599-0443-093
94. N/A 599-0443-094
95. N/A 599-0443-095
96. LO.3.13 599-0443-096
97. N/A 599-0443-097
98. N/A 599-0443-098
99. N/A 599-0443-099
100. N/A 599-0443-100
101. LO.3.2 599-0443-101
102. LO.3.8 599-0443-102
r- - -INDICATION DESIGN(ATIONS__
(1) 0. D.LONG. CRA W (6) LTS-2 H O.D. WEA* HKIXG (16) UTS C2 < (2) DING 7) LTS-B 121 PLUGGED Il UTS C3
o D '1 (3) CHAITTER (8) MISC. (13 REM4OVED i1) O.D. INDICATION F-i 1 LOO-PS ~ 9 SPECIAL TUBES IO 14 STABILIZED 19) I.D.LONG.CRACK
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Page 2
A total of 10% of the "A" generator tubes and 21% of the "B" generator tubes was examined. The results of these exams are documented below.
RESULTS:
There are four (4) tubes in steam generator "A" which contain defects equal to or greater than 20% of the wall thickness. A listing of these tubes and their status is given below.
Tube Locatioh & Type of Defect Depth
77-6 15th OD 22% 63-130 12th OD 30% 77-123 l1th OD 22% 75-118 14th OD 25%
There are 24 tubes in steam generator "B" which contain defects equal to or greater than 20% of the wall thickness.
Tube Location & Type of Defect Depth
75-3 15th OD 20% 75-5 15th OD 20-30% 75-6 15th OD 20-30% 75-9 15th OD 25% 75-10 15th OD 20-25% 77-22 15th OD 20% 78-6 15th OD 25% 78-3 15th OD 28% 104-93 LTS-1 OD 20% 52-45 13th OD 20% 83-71 8-9th OD 20-25% 37-5 14th OD 25% 133-35 2-3rd OD 30% 124-38 14-15th OD 35%
*4-4 14th OD 44% 137-68 2-3rd OD 35%
*150-14 10th OD 52% 99-105 14-15th OD 36%
*58-2 14th OD 50% *62-113 14th OD 52% 100-11 14th OD 30-40% 53-124 14th OD 20-30% 54-125 14th OD 20-25% 57-125 14th OD 20-30%