IR 05000269/1978036
| ML15223A361 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/21/1978 |
| From: | Conlon T, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15223A359 | List: |
| References | |
| 50-269-78-36, 50-270-78-34, NUDOCS 7901100340 | |
| Download: ML15223A361 (8) | |
Text
REG&
.UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.:
50-269/78-36, 50-270/78-34 and 50-287/78-36 Docket Nos.:
50-269, 50-270 and 50-287 License Nos.:
DPR-38, DPR-47 and DPR-55 Categories:
C, C, and C Licensee:
Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee Nuclear Station, Units 1, 2 and 3 Inspection at:
Oconee, Seneca, South Carolina Inspection conducted: December 6-8, 1978 Inspector: N. Economos Reviewed by:
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T. E. Conlon, Chief
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Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary Inspection on December 6-8, 1978 (Report Nos. 50-269/78-36, 50-270/78-34 and 50-287/78-36)
Areas Inspected:
Corrective action on unresolved items 269/78-21-01, and 269/270/287/77-17-Ul; Unit 2 third outage ISI inspection records, NDE of stagnent water lines records (IE Circular 76-06).
The inspection involved 15 inspector-hours on site by one NRC inspecto Results:
Of the three areas inspected no apparent items of noncompliance were identifie ~
~~o
RII Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 I-1 DETAILS I Prepared by-A'
IZ4 1I17 N. Economos, Metallurgical Engineet Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection:
December 6-8, 1978 Reviewed b jy
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T. E. Conlon, Chief Da e Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Persons Contacted Duke Power Company (DPC)
- J. E. Smith, Station Manager
- R. M. Koehler, Superintendent of Technical Services
- A. J. Hogge, QA Specialist P. V. Fant, Assistant QA Engineer P. Waltman, Station ISI Coordinator B. Farmer, Level II NDE Babcock and Wilcox Construction Company (B&W)
G. Dunkel, ISI Coordinator In addition to the above, other craft and inspection personnel were interviewe *Denotes those present at the exit intervie.
Licensee Action on Previously Identified Inspection Findings (Closed) Unresolved Item (77-17-Ul):
ISI Calibration Block Evaluation. The licensee provided the inspector B&W's calibra tion block comparison data from tests conducted on calibration blocks #40301 and 40340. The inspector reviewed the data and B&W's correspondence on this matter. The new blocks are consistent with applicable code requirement (Closed) Unresolved Item (269/78-21-01):
Radiographic Examina tion of Feedwater Welds. The reshot of weld 41E was reviewed and found to be free of rejectable indication RII Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 1-2 Unresolved'Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviation Unresolved items disclosed during the inspection are discussed in Paragraph.
Independent Inspection Effort NDE of Stagnent Water Lines -
Circular 76-06 (Unit 2)
Records of nondestructive examinations performed on stagnent water lines between June 28 -
July 20, 1977 were reviewe The lines examined included portions of the core flood A and B loops, decay heat removal, low pressure injection (LPI), high pressure injection (HPI), reactor building spray (RBS) 2A and 2B, reactor building spray. The results of this examination is summarized belo System Welds Reportable Inter-Disposition Examined Indications pretation Core Flood Line-A
4
Accep Line-B
3
Accep Decay Heat Removal
5
Accep LPI Discharge
1
Accep RBS Line-2A
Line-2B
1
Accep The inspection provided for visual and volumetric (UT) examina tions performed by B&W. The UT examination was performed using procedure ISI-120 Revision 4. The areas of interest were scanned with straight beam and 450 shear wave transducer Records reviewed included calibration sheets, material certifi cations (couplant), personnel qualifications, data sheets, instrument and transducer certifications. An in depth record review was performed for weld W51, size 14"Ox1.25" thick in the core flood "B" lin Within the areas inspected, no items of noncompliance or deviations were identifie RII Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 1-3 Closure Head Stud Replacement - Unit 2 Replacement of closure head stud number 4 became necessary when the stud failed to respond to normal detensioning procedure The work was performed under nuclear station work request N, 7/26/78. Stud detensioning and removal was performed in accordance with procedure MP/0/A/1150/03 which gave detail instructions and provided for a sign-off at the completion of each step of the operatio The new stud, S/N 25-209-64-A540, was made of A540-65, grade 23, material produced from Crucible Steel Company heat number 15962 The inspector reviewed material quality records, receipt inspection records and warehouse release to the field. B&W (UT & MT) inspected the stud and found it acceptable for the applicatio Within the areas inspected no items of noncompliance or devia tions were identifie.
Eddy Current Examination of Once Through Steam Generator (OTSG) Tubing (Unit 2)
ISI activities during this outage included the eddy current (EC)
examination of tubes in both "A" and "B" OTSGs. The tubes selected for EC included (1) a 100% inspection of tubes in the "lane region",
(2) 6% inspection of the remaining number of tubes in the bundle with emphasis on the peripheral region of the generator and, (3) an additional list of approximately 75 tubes of specific interes The latter included tubes that previously exhibited dings and/or ID, OD indication B&W's procedure ISI-401 Rev. 8 was used to perform the examinatio Examination results were recorded on magnetic tape, strip chart and on Form-60 The inspector reviewed data of EC inspection on the following tubes:
OTSG Row (From) Tube Row (To) Tube Inspect. Date
"A"
1
8 11/15/78
11
9 11/15/78
12
12 11/15/78
15
16 11/16/78
RII Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 1-4 OTSG Row (From) Tube Row (To) Tube Inspect. Date
"B"
22
-
11/16/78
8
-
11/16/78
37
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11/16/78 In addition to reviewing this record sample, the inspector discussed examination results with the licensee and contractor. Both stated that no rejectable indications (tubes requiring plugging) were found during this outage. Within the areas inspected no items of noncompliance or deviations were identifie.
Inservice Inspection Data Review and Evaluation (Unit 2)
This work effort was related to the third (3) refueling outage which took place between October 26 and December 5, 197 Nondestructive examinations/ISI activities were conducted by B&W under contract with DPC. The controlling document is B&W's 1978 ISI Manual for Unit 2. This manual and related ISI procedures had been approved by B&W's Level III examiner and DPC's cognizant QA representativ The manual contains the current ISI scope and the projected ISI program over the first ten (10) year interval.Section XI of the ASME Code 1974 Edition through the 1975 summer addenda controls NDE requirement Components/Parts scheduled for IS1 during this outage included the reactor vessel, pressurizer, steam generators (A&B), pressure boundary piping and, various Class 2 parts and component The inspector selected records of ISI examinations of the reactor vessel welds, pressure boundary pipe welds and pressure retaining bolting. These records were reviewed to ascertain whether they contained information on, or provided reference to; examination results, examination equipment data, calibration data sheets, evaluations of indications, extent of examination, programatic deviations, disposition of findings and identification of NDE material e.g. UT couplant. Records selected for this review were as follows: Reactor Vessel Component Weld Area/Part Inspect Method Fig. B1. Circle Seam Vessel to UT/Aris Flange ID #86-7
RII Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 1-5 Fig. B1. X-Axis Outlet Noz Weld UT/Aris
& Knuckle Area ID #19-A7 Fig. B1. Z-Axis Outlet Noz Weld UT/Aris
& Knuckle Area ID #19-A7 Fig. B1. Ligament Area ID #7 UT/Aris Pressure Boundary Piping, >2"O Component Weld Area/Part Inspect Method RC Hot Leg B Fig. B4.1.19 Noz to Pipe Z-Y Axis UT ID #7-12 Fig. B4.1.20 Noz to Pipe Z-Y Axis PT ID #7-12 Fig. B4.1.21 Noz to Pipe Z-W Axis UT ID #7-12 Fig. B4.1.22 Noz to Pipe Z-W Axis PT ID #7-12 Fig. B4.1.23 Noz to Pipe X-Asix UT ID #7-12 Fig. B4.1.24 Noz to Pipe X-Axis PT ID #7-12
- Fig. B4. Z-Axis Outlet Noz UT/Aris to Pipe ID #19-32 Bolts/Studs (1) Heater Bundle Studs, 2"0 Component Weld Area/Part Inspect Method Fig. B2. Studs UT Fig. B2. Studs MT
RH Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 1-6 (2) Steam Generator "A", Manway Bolts Component Weld Area/Part Inspect Method Fig. B3.1 Bolts VIS (3) Closure Head Stud Component Weld Area/Part Inspect Method S/N 25-209-64-A540 1 Stud UT & MT
- Seven indications were found in the nozzle base meta These were identified by the straight (00) beam examination and are located in the nozzle between 2 and 5 o'clock looking at the vesse The signal amplitude ranged between
to 90 of DAC. B&W characterized these as laminar type indications and evaluated them in accordance with ASME Section III NB-2532. B&W reported that these were acceptable indica tions and noted that they had very small length and virtually no widt In addition, NDE records of the reactor vessel circular seam (vessel to flange weld figure B1.3.1) was reviewed to ascertain; (1) whether the method, technique and extent of examination complied with programatic requirements, (2) examination data met acceptance criteria, (3) documentation, evaluation and disposition of findings were consistent with code requirements, (4) the examination provide for full coverage of the area of interest. Also ISI records of Let Down Cooler (pipe to elbow welds Figs. B4.5.81 and B4.5.82) were reviewed to ascertain whether calibration sheets were complete and legible, data evaluation was performed by qualified personnel, evaluations were consistent with procedural and code requirement Discussions with the licensee disclosed that calibration blocks 40301 and 40323 could not be located and appear to be los In addition the licensee stated that block 40336 was damaged during handling. It was anticipated that all three blocks would be replace All weld examinations requiring the above blocks for instrument calibration were deleted from the ISI schedule for this outage and will be done sometime late The licensee agreed to improve on the identification, storage and handling of these blocks in order to help preclude the recurrence of this problem since under different circumstances it could prevent the examination of specific welds needed to meet code requirements at that point in tim RII Rpt. Nos. 50-269/78-36, 50-270/78-34 and 50-287/76-36 1-7 The inspector stated this would be identified as an unresolved item until NRC has an opportunity to inspect the new blocks. This matter was assigned unresolved item number 270/78-34-0.
Exit Interview The inspector met with the licensee representatives, denoted in paragraph 1 at the conclusion of the inspection. The inspector identified the areas inspected which included, review of ISI records for the current outage; the NDE examination on certain lines to satisfy IE 76-06 Circular. The licensee acknowledge the inspection findings.