IR 05000269/1979013
| ML19249A777 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/06/1979 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249A773 | List: |
| References | |
| 50-269-79-13, 50-270-79-13, 50-287-79-14, NUDOCS 7908240311 | |
| Download: ML19249A777 (8) | |
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NUCLEAR REGULATORY COMMISSION
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Report Nos. 50-269/79-13, 50-270/79-13 and 50-287/79-14 Licensee: Duke Power Company 422 S. Church Street Charlotte, North Carolina 28242 Facility Name: Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, 50-270, and 50-287 License Nos. DPR-38, DPR-47, and DPR-55 Inspection at Oconee, peneca South. Carolina
Inspector:
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N. Economo EFte Signed 7[
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A. R. Herdt, RC&ES Branch j p e Signed SUMMARY Inspection on May 29 - June 1 and June 5-6, 1979.
Areas Inspected:
This routine unannounced inspection involved 43 inspector-hours onsite in the areas of Emergency feedwater and high pressure injection modification - welding, NDE and record review Units 1, 2, and 3.
Unit 3 fourth outage ISI inspection, review ISI records.
Results:
Of the three areas inspected, no apparent items of noncompliance or deviation were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- J. M. Davis, Superintendent :f Maintenance
- R. J. Brackett, Station Senior QA Engineer
- J. J. McCool, QA Surveillance Supervisor
- A. Wilkie, Mechanical Maintenance Support Engineer
- D. M. Thompson, Mechanical Maintenance Engineer Other Organizations Babcock and Wilcox Contruction Company (B&W)
H. Stoppelmann, ISI Coordinator
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NRC Resident Inspector F. Jape
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on June 1 cc.d 6 with those persons indicated in Paragraph 1 above. The inspector identified the areas inspected which included welding, hTE and record review for the emergency feedwater and high pressure injection modifications on Units 1, 2, and 3 review of Unit 3 fourth fuel outage ISI inspection data.
The licensee concurred with the inspection findings.
3.
Licensee Action on Previous Inspection Findings Actions on previous findings were not examined on this inspection.
4.
Unresolved Items Unresolved items are matters about which more informaticn is required to determine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are discussed in pa igraph 6 and 7.
5.
Eddy Current Examination of Once Through Steam Generator (OTSG) Tubing (Unit 3)
ISI activities during this outage (4th) included the eddy current (EC)
examination of tubes in both
"A" and "B" OTSGs.
Tubes selected for EC
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-2-included (1) a 100% inspection of tubes in the " lane region" (2) approxi-mately 75 tubes of special interest e.g., tubes with previously identified ID/0D indications and " dings" (3) random selection tubes in the tube bundle.
Items (2) and (3) constituted a 3 percent sample. Tube examination extended from the 15th tube support plate to the upper tube support. In all, 465 tubes were examined in OTSG "A" and 470 in OTSG "B".
B&W procedure ISI-401 R/7 which references R.G. 1.83 R/1 July, 1975 was used to perform the examination.
Both OTSGs were examined between May 5 and 7, 1979. The inspector reviewed the above mentioned EC procedure, test results, calibra-tion sheets, calibration standard quality records, personnel qualifications.
Examination results were discussed with the licensee who stated that both OTSGs required tubes to be plugged and stablized - one (1) in "A" and two (2) in "B".
6.
Inservice Inspection Data Review and Evaluation (Unit 3)
This work effort was relat ed to the fourth refueling outage which began on/or about April 27, 1979 and was still in progress at the time of this inspection. Nondestructive examinations /ISI activities were conducted by B&W under contract with DPC. The controlling document is B&W's 1979 ISI Manual for Unit 3.
This manual and related ISI procedures had been approved by B&W's Level III examiner and DPC's cognizant QA representative on April 30, 1979.
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 requirements.
Components / Parts scheduled for ISI during this outage include the reactor vessel, pressurizer, once through steam generators (A&B), nozzles pressure boundary piping, various Class 2 parts and components and hangers.
The inspector selected NDE records of pressurizer and reactor vessel nozzles, 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 examina-tion, programatic deviations, disposition of findings and identification of NDE material e.g.
UT couplant.
Records selected for this review were as follows:
a.
Reactor Vessel Component Weld Area /Part Inspect Method Fig. Bl.3.1 Circle Seam Vessel Flange UT/ARIS Fig. Bl.3.2 Circle Seam-Vessel to Flange UT/ARIS Fig. Bl.4.7 X-Axis 3B Outlet Nozzle Weld UT/ARIS and Knuckle Area
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-3-Fig. Bl.48 Z-Axis, 3A Outlet Nozzle Weld UT/ARIS-and Knuckle Area Fig. Bl.8.1 Closure head Studs UT/MT Bl.8.2
- Fig. Bl.13.1 Closure Head Surface Bl.13.2 Clad Patches PT/VIS Fig. Bl.15 Reactor Vessel Visual Internal Surfaces b.
Pressurizer Fig. B2.2.6 Presr. Upper Level Sensing Noz.
UT B2.2.7 Y-Z and Z-Waxes Fig. B2.1.1 Htr. Bundle Shell Arc. Seam UT Fig. B2.212 Pres. Relief Nozzle Z-W Axis UT c.
Steam Generator "B" Fig. B3.2.4 Outlet Noz. to Head 3B, W Axis UT Fig.
B3.2.5 Outlet Noz. to Head 3B, Y Axis UT d.
Piping Fig. C2.1.9 R. B. Emergency Sump UT C2.1.17 Pipe - 14" UT Fig. C2.1.40 Cooler B, Discharge to Valve UT C2.1.41 Pipe to 45 Ell, 10" UT Fig. C2.1.52 Borated Vater Supply UT and C2.1.53 to HPI Pump 6" UT Fig. C2.1.58 Main Steam, Ell to pipe R i'
26" x 0.88" Fig. C2.1.63 Pipe to Valve 24" x 0.97" RT Fig. C2.1.68 Pipe to Ell, 12.75" x 0.56" RT In addition, NDE recoida of the reactor vessel circular seam (vessel to flange weld figure Bl.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) documen-tation, evaluation and disposition of findings were consistent with code requirements, (4) the examination provided for full coverage of q
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-4-the area of interest. Also. ISI records of pipe welds were reviewed to ascertain whether calibration were complete and legible, examina-tions and data evaluation were performed by qualified personnel and evaluations were consistent with procedural and code requirements.
Within these areas the inspector noted the following:
- (1) Fig. C2.1.66, Pipe to Ell 12.75" x.56" to 75" Penetrameter holes (sensitivity)
in stations 1-2, 2-3 and 3-4 were not clearly visible - Paragraph 8.1, Procedure ISI-300 Rev. 3 (2) Fig. C2.1.63 Pipe to Valve 24" x 1.00" Penetrameter selection (thick-ness) for this material thickness did not appear to be consistent with procedural requirements -
Paragraph 8.4.3, Procedure ISI-300 Rev 8 (3) Fig. C2.1.58 E)i to Pipe 26" x.88" Penetrameter selec. ion (thick-ness) for this material thickness did not appear to be consistent with procedural requirements -
Paragraph 8.4.3, Procedure ISI-300 Rev. 8 These concerns were discussed in detail with the licensee who agreed to review these and other radiographs taken as part of the ISI effort and report later. This was identified as unresolved item 287/79-14-01 pending further review of the licensee's findings.
7.
Emergency Feedwater and High Pressure Inspection Systems Modification (Units 1, 2, and 3)
Work on the modification of the emergency feedwater lines (FW) and high pressure injection HPI system vas in progress at the time of this inspec-tion.
Authorization for this activity was documented on Nuclear Station Modification Process Records numbers 1275 and 1080 respectively.
Field activities (welding, NDE, QC inspection) are controlled thru Oconee Station Directives and related QA/QC procedures. A sample of these, selected on a random basis for review ine'.ude:
a.
Oconee Nuclear Station, Welding Program Oconee Nuclear Station Direc-tive, (0NSD) 3.6.1 (M) revision 4/24/79.
b.
QCL-1 Rev. 9, Inspction of Field Pipe and Welds c.
QCD-1 Rev.
3, Housekeeping During the operating phase of Nuclear Stations
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QCH-1 Rev. 5, Visual Workmanship Standards for Welds.
QCK-1 Rev.10, Control of Nonconforming Items e.
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QCK-2 Rev. 5, Work Stoppage
- NDE-B Rev.1, Training Qualification and Certification of NDE personnel.
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NDE-10 Rev.
O. Radiography.
In that the modification involves several pipe classifications, A through F, the referencing codes listed were as follows: fabrication and acceptance requirements ASME Section III; ANSI Power Piping B31.1 and Nuclear Power Piping 31.7; welder performance and weld procedure qualificctions ASME Section IX; Presservice inspection (baseline) ASME Section XI.
Witi:in these are is the inspector noted the following:
Paragraph 7.2.5 of ONSD 3.6.1(M) states in part that, "weldiag material n.
shall be issued to individuals in quantities.
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stated that the word " individuals" infers that anyone could withdraw weld rod wherea; under the controlled f rabrication concept only authorized individua's (e.g., qualified welders) may withdraw weld material. The licensee agreed to look into this matter and make the necessary proce-identified as inspector followup item dural adjustments.
This was number 79-13-02.
b.
Paragraph 9.2.1 of ONSD 3.6.1(M) which applies to preheat and interpass for temperature control, does not specifically address the requirement maintenance of preheat during periods of interrupted welding on heavy secticos of carbou steel or other alloy materials. Also it does not specify the frequency of preheat checks on welds reouiring several shiftc to compl te and, the checking of interpass temperature during the course of weld f abrication. The inspector discussed this subject with the cognizant license representative who agreed to review the document.nd take approprate action to address these matters. This was identified as unresolved item 79-13-01.
(1) Work Observation - Welding The inspector reviewed weld process specifications for shielded metal arc (SMA) L-30') and gas Tungsten arc (GTA) L-200 along with applicable field welJ data sheets for technical content and code compliance. Random'.y selected samples of field welds in process and completed were inspected for fitup, bead appearance, interpass
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cleaning, reinforcement use of appropriate weld procedure.
Drawings, weld sketches, weld rod issue slips and weld fabrica-tion records were reviewed.
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Welds selected for tt sork effort were as follows:
Weld No.
Size In Inches ISO / System Unit No.
In-Process FW-2 6" x.43" ISO-107/7A
FW-11 8" x sch. 40" ISO-132/7A
- FW-38 2" x.218" ISO-191/7A
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FW-4 12" x.375" ISO-134/7A
W-8 12" x.375" ISO-134/7A
FW-9 12" x.375" ISO-134/7A
Completed 44-8C 6"
ISO-44
FW-3,-8, 12" ISO-134/Dwg.
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-9,-10 0-1400RF FW-10 6"
ISO-132/7A
96-4A 6"
ISO-96/3A
96-4B 6"
ISO-96/3A
96-18 3/8" ISO-96/3A
96-20 3/8" ISO-96/3A
b.
Review of Quality Records Quality records of randomly selected components were reviewed to ascertain whether they were complete, accurate and retrievable.
Records reviewed included code data reports, certificates of confor-mance vendor QA certifications, fabrication records, receipt inspec-tion reports material certificatn as and NDE reports.
The items selected for this work effort re as follows:
Valves:
8," Class "C" Gate Valves S/Ns D63703 and D63739 3/4," Kerotest Globe Valves S/Ns YC16-8 and V0-5 2," Plug Valve S/N 89605 Flanges:
6" Class B, Ht #74-P, SA105 Pipe Material: 4" Sch. 160, HL Nos., M3145, M2267, M3067, P. O. E-47486-73 Spool Piece:
8"/6," S/N 0-2400-RF-S15, ISO-132, Systems 07A Weld Consumables:
Type Ht. No.
Size P. O. No.
E70S-2 65210 1/8" E39667-75 308 G5317 1/ 8
C50907 In addition the inspector reviewed the performance qualificatica records of certain welders involved in the fabrication of field-welds discussed above.
inspected no items of noncompliance or deviations Within the areas were identified.
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Randomly selected radiographs of welds from the emergency feedwater (EFW) and high pressure injection (HPI) systems, were selected for review, these were as follows:
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HPI Cross Over Line 2,3 and 10 121 R/2 4" x.531" 51A 2A 1.0 R/3 4" x.531" 51A
118 R/0 4" x.531" 51A 14 and 15 117 R/0 4" x.531" 51A HIP Cross Over Line 12 and 10 120 R/0 4" x.531" 51A
112 6" x.432" 03A
- EFW 9A and 9B 87 R/8 6" x.432" 03A 4A and 4B 96 R/7 6" x.432" 03A
- Welds indicated under this system were visually inspected, and sup-porting fabrication QC records were reviewed.
Within the areas in-spected no items of noncompliance or deviations were identified.
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