IR 05000270/1978014
| ML19317D379 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/09/1978 |
| From: | Conlon T, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317D356 | List: |
| References | |
| 50-270-78-14, 50-287-78-14, NUDOCS 7911270587 | |
| Download: ML19317D379 (6) | |
Text
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Report Nos.:
50-270/78-14 and 50-287/78-14 Docket Nos.:
50-270 and 50-287 License Nos.:
C and C Licensee:
Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee Nuclear Station, Units 2 and 3 Inspection at:
Seneca, South Carolina Inspection conducted:
June 26-29, 1978 Inspector:
Nick Economos r
Reviewed by:
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T. E. Conlon, Chief Date En/ineering Support Section No. 2
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I Reactor Construction and Engineering Support Branch
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Inspection Sumary Inspection on June 26-29 (Report Nos. 50-270/78-14 and 50-287/78-14)
Areas Inspected:
Corrective action on previously identified infraction number 270/78-06-01; ISI activity in Unit 3; nuclear station modification, (NSM) number 246.
The inspection involved 29 inspector-hours on site by one NRC inspector. There were no Part 21 or 50.55(e)' items included in this inspection.
Results:
Of the three areas inspected, no apparent items of noncompliance
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were identified in two areas; one apparent item of noncompliance (infraction -
paragraph 4) was identified in one area.
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RII Rpt. Nos. 50-270/78-14 I-1 and 50-287/78-14 CC)' M.
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DETAILS I Prepare by:
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N., Econo'mos, Metallurgical Engineer Date
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Engineering Support Section No. 2
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Reactor Construction and Engineering
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Support Branch
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Dates of Inspection: June 6-29, 1978 Reviewed
T. E. Conlon, Chief Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted
a.
Duke Power Company (DPC)
- J. E. Smith, Station Manager
- J. Barbour, QA Operations Divisions Manager
- D. Norton, QA Engineer, Charlotte
- R. J. Brackett, Operations QA Engineer
- R. T. Bond, Station Technical Services Engineer b.
Cy Jrganization
i Babcock and Wilcox Construction Company (B&W)
D. R. Welch, Coordinator P. D. Berstein, Level II, UT Examiner P. Pitz, Level II, Radiography In addition to the above, other craft and inspection personnel were interviewed.
- Denotes those present at the exit interview.
2.
Licensee Action on Previously Identified Inspection Findings (Closed) Noncompliance Item (270/78-06-01): Failure to meet minimum ISI requirements (Units 2 and 3).
The licensee has completed the
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review of the ISI plan and has identified the categories where -ISI inspection requirements were not fully implemented.
A schedule has-been established which provides for the implementation of these inspections during future outages.
Also, the licensee has taken
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RII Rpt. Nos. 50-270/78-14 I-2 and 50-287/78-14 appropriate steps which provides for revies of subsequent ISI plcns to assure that component examinations meet minimum code requirements.
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This item is closed.
3.
Unresolved Items No new unresolved items were identified on this inspection.
4.
Independent Inspection Effort Replace Low Pressure Injection Discharge Valve, NSM-246 (Unit 3)
The licensee is replacing existing low pressure injection (LPI)
discharge values with 811 flow control Fisher Vee-Ball valves. This action was required when it was discovered that the internal guide pins of the existing valves were failing because of flow induced cavitation.
DPC's engineering has reviewed the thermal, gravity and seismic analyses results.
The modified system will be hydro tested to meet construction code, USAS B31.7, code requirements.
Weld fabrication and testing was done to meet AStiE Section XI requirements.
The inspector reviewed various quality control documents including process records ON-0246 R1, R1A and Part C December 21, 1977 implementation approval, design summary, vendor QA certifications f~e Q ues with serial number (S/N)
6489111 through 6489114; certificates of compliance; design receipt reports and QA acceptance.
The manuf acturer's certifications indicated these valves sere manufactured
in accordance with DPC specificatien ENS /12005.06-3 and AStiE Section III; welding was governed by Sectan IX of the abov t code while NDE
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personnel were qualified per ASNT Recommended Practice SNT-TC-1A.
In addition, the inspector rniewed related DPC is" metric drawings, radiographs for new welds50-11B, -12A, -13A, -14A, a:d inspected these welds as well as those on either side of valve 3LP-14.. At Lnis time, the inspector noted that a substantial quantity of 3DS stainless steel base wire veld electrodes, of various lengths, were scattered on the floor in the area where the modification had taken place.
This condition was brought to the attention of appropriata licensee personnel who agreed that the condition was in violation of Station Directive 3.6.1(M) which requires that, "all mater.a1 be consumed in the weld process or returned to the issue statica".
This findings represents a violation to Criterion V of Appendix 3 to 10 CFR 50, as implemented by commitments set forth in the DPC Topical Report Duke-1-A Section 17 paragraph 17.1.5.
This was ideutified as an infraction and assigned number (78-14-01).
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RII Rpt. Nos. 50-270/78-14 I-3 and 50-287/78-14 5.
1978 Refueling Outage Inservice Inspection - Unit 3 a.
Observation of Work and Work Activities Nondestructive examinations / activities during this outage are being conducted by B&W under contract with DPC. The controlling document is E&W's 1978 ISI Manual Rev. 7, June 5,1978. This had been approved by B&W's Level III examiner and DPC's cognizant QA representative. It lists examination schedules for class 1 and 2 components for this and subsequent outages during the first ten year interval.Section XI of the ASME Code 1974 Edition through summer 1975 addenda, controls NDE examination requirements.
Class 1 and 2 components earmarked for this ISI examination were:
reactor pressure vessel and head; pressurizer; steam generator and tubes; reactor coolant piping, pumps and valves; coolers.
Within these areas the inspector witnessed the examination of the following items.
Figure Weld / Component Comments C.2.1.73 Mainsteam Clear Loop B, 9-19 C.2.1.48 LP Cooler "A" Clear Head Flange Nuts C.I.2.2 LP Cooler "A" Clear Inlet Nozzle C.5.22 Sipport Attachment Clear C.2.1.48 8" LP Discharge Two Indication C.2.1.48.1 8" LP Injection Five Indications
<DAC For these welds the inspector verified procedure implementation, personnel qualifications and familiarity with inspection methods,-
administrative controls, inte rpretation and documentation of findings.
b.
Data Review and Evaluation Records of completed nondestructive examinations were selected and reviewed to ascertain whether:
the method (s), technique and extent of the examination complied with the ISI plan and l
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RII Rpt. Nos. 50-270/78-14 I-4 and 50-287/78-14 applicable NDE procedures; findings were properly recorded and evaluated by qualified personnel; programmatic deviations were recorded as required; personnel, instruments, calibration blocks and NDE materials (penetrants, couplants) were designated and qualifications / certifications on file. Records selected for this review were as follows:
Figure Component / Weld Comments C.2.1.30 10" L.P. discharge Clear C.2.1.35 10" L.P. discharge Clear
- C.2.1.40 10" Pipe to Valve Two Inds. 160 &
200% DAC, Geometry
- C.2.1.40.1 Reducer to Valve One indication 45,
100% DAC
- C.2.1.40.2 Valve to Reducer Two Inds., <DAC
- C.2.1.40.3 10" Reducer to TEE Clear
- C.2.1.40.4 Tee to Pipe Clear
- C.2.1.4.7.7 Tee to Pipe Clear
- These are new welds associated with the aforementioned modi-fication NSM-246 and the NDE performed at this time was regarded as the preservice (baseline) examination.
C.2.1.6 12" decay beat suction One Indication 110%
B.2.1.8 Pressurizer-shell long.
Clear B.3.5.2
"A" Studs Clear C.2.1.88 Header to Cap 14" Clear
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C 2.1.10C 16-55
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C.2.1.93 Main Feedwater S/G "B" C.2.1.104 Emergency Feedwater,
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The inspector reviewed quality certifications and/or calibrations for calibration blocks No. 40327, 40329, 40324 and 40304; transducer serial numbers (S/N) 32157, 32377, 32172, 32372; UT instruments S/N 12038, 12039 and couplant batch number 62009. The liquid penetrant materials were certified to applicable ASTM standards.
The item selected to verify compliance with IWC-2400 inspection schedule requirements for this inspection interval and outage was main steam lines A and B.
This was performed by reviewing ISI isometries ISI-209 and 15I-210 and the ISI plan.
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RII Rpt. Nos. 50-270/78-14 I-5 and 50-287/78-14 c.
ISI Technical Specification (TS) Commitments i
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In addition to code required ISI examination, the licensee has agreed by commitment in the TS to perform certain inspections at specified time intervals. These refer to the following items:
Pa ra graph Item Examination Frequency 4.25 Main Internal Visual of Welded Bolt Refueling Bolts Locking Caps Outage 4.2.8 Bore and Key-In-Place Volumetric Approximately way of RC Examination 3-yr. In-Pump Flywheel te rval These examinations were conducted during the October 10, 1977 fuel outage.
4.2.12 Vent Valves Exercise Valves and East Refueling inspect Outage Appendix 4A Outlet Nozzle Volumetric 3 1/3 yrs.
Item 2 after initial operation The inspector reviewed the records of inspection for these ittms in order to verify that the ccomitments were met as required.
Within the areas inspected, no items of noncompliance or deviations were identified.
6.
Exit Interview The inspector met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on June 29, 1978.
The inspector identified the areas inspected and advised the licensee that one noncompliance was identified.
The licensee acknowledged the inspection findings.
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