IR 05000285/1990022
| ML20042G238 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/02/1990 |
| From: | Barnes I, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20042G232 | List: |
| References | |
| 50-285-90-22, NUDOCS 9005110261 | |
| Download: ML20042G238 (5) | |
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e APPENDIX g
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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tiRC Inspection Report: 50-285/90-22 Operating License: DPR-40 Docket: 50-285 Licensee: OmahaPublicPowerDistrict(OPPD)
<f 444 South 16th Street Mall i
Omaha, Nebraska 68102-2247
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- Tacility Name: FortCalhounStation(FCS)
Inspection At: FCS, Blair, Nebraska 3 -
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Inspection Conducted: March 12-16 and April 9 12, 1990
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Inspector:
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W. M. McNeiTT, Reactor Inspector ~ Materials Date
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and Quality Programs Section, Division of
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. Reactor Safety
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,'T 1. Bat nes, ChieT, Materialt and' Quality Date-
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Programs Section, Division of Reactor Safety inspectionSummary inspection Conducted March 12-16_ and April 9-12. 1990 (Repod 50-285/90-22)
Areas in,spected: Rou' e, unannounced inspection of action token on previously identifiedinspectionfindings,inserviceinspection(ISI),andwelding activities.
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Results: - Observation of ISI work activities found that volumetric and surface examinations required by the ISI program plan were being satisfactorily performed by appropriately. certified contractor personnel.
Limited inspection
of~in-process welding showed appropriate conformance with welding procedure specification requirements. The licensee was noted to be actively monitoring ISI performance and to be performing detailed surveillances of in-process velding activities, s
9005110261 900504 i
PDR ADOCK 05G00285
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DETAILS
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PERSONS CONTACTED,
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- R. L. Andrews, Quality and Environmental Aff airs Division Hanager t'
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f*C. N. Bloyd, Lead Special Service Engineer 4"
C. E. Dougther, Lead Special Service Engineer
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F. G. Buck, Systerns Engineer a
^ *D. W. Dale, Quality Control (QC) Supervisor
- S. K. Ganbhir, Production Engineering Division Manager
- J. K. Gasper, Training Manager (*W. G. Cates, Nuclear Operations Division Manager f *P. F. Hafner, Special Services Engineer
- C. K. Haung, Human Performance Evaluation System / Root Cause Analysis Supervisor
- R. L. Jawerski, Station Engineering Manager i
- J. D. Kecy, Systems Engineering Supervisor i
- L.T.Kuset,SafetyReviewGroup(SRG) Manager R. H. Lichtenstein, System Engineer
- R. C. Lippy, Special Services Engineer S. A. Lindquest, Licensing Engineer d*D. J. Matthews, Station Licensing Supervisor
- T. C. Matthews, Station Licensing Engineer
- T. J. McIvor Nuclear Projects Manager
- R. J. Mueller, Nuclu r Projects Supervisor
- R. L. Phelps, Design Engineering Manager gO-f*G. R. Peterson, FCS Manager
B. A. Reneaud, Chemistry Technicibn R..L. Ruhge QC Engineer
- G. P. Schwartz, Electronics, Instrument and Control Manager
,#*C. F. Simons, Station Licensing Engineer f*R. E. Short, Special Services Engineering Supervisor
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- D. L. Stice, Licensing Engineer j
S. A. Swearngin, SRG Engineer f*T. G. Therkildsen, Nuclear Licensing Supervisor
.f*J. W. Tills, FCS Assistant Manager Ebasco Inspection Services Inc.
A._B. Nagel, level 11 D. D. Peterson, level 1
D. P. Roeters, level II T. J. Spelde, level 1
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Hartford Steam Bo,iler Inspection and Insurance Company S.C.Presler,AuthorizedNuclearInterviceInspection(AN!!)
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- J. E. Gagliardo, Section Chief j
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'P. H. Harrell, Senior. Resident inspector
- D. R. Hunter, Reactor Inspector
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- C. J. Paulk, Reactor inspector
- P. C. Wagner, Reactor Inspector l
- Denotes those persons that attended the exit interview on March 16, 1990.
(Denotes those persons that attended the exit interview on April 17, 1990.
l The inspector also interviewed other licensee personnel during the inspection.
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ACTIO,N,0N PREVIOUSLY 1DENTIFIED INSPECTION FINDI,NGS (92701)
2.1 (Closed)OpenItemP85/8806-01:
ISI of reactor vessel head meridional
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A review of the licensee's 151 records for the reactor vessel found that one of
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the reactor vessel closure head meridional welds was inspected during the.1988 l
refueling outage.
A. total of 4 1/2 inches of meridional Weld HM-3 was i
inspacted, with the remainder of the'32-inch length being inaccessibic for
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inspection due;to the presence of a seismic shield and interference from the control rod drive housing welds. The closure head and. bottom head of the I
reactor vessel both contain six meridional welds. About 10 percent ~ of the top meridional welds and 20 percent of the bottom meridional welds are inspected:
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during axamination~of the associated circumferential welds. After review of'
the'above information with the Materials and Chemical Engineering Branch of the
Office of Nuclear Reactor Regulation, it was agreed that the scope of the FCS
ISI activities for these welds was sufficient to assure conformance with regulatory requirements.
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INSFRVICEINSPECTION(ISI)WORKAC,TIVITIES (73753)>
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L The objective of this inspection was to ascertain whether ISI examinations and
- repair / replacement activities are performed in accordance with Technical-
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Specifications (TS), the applicable American Society of Mechanical
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. Engineers (ASME) Code, and correspondence between NRC and the licensee concerning relief requests.
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3.1-ReviewofJS1ProgramandProcedures Ls The inspector reviewed TS, Amendecnt 122 dated June 2, 1989; the " Inservice s
Irispection Program Plan," Revision 4, dated July 1,1988; and the following
m procedures:
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FC-PR-1, " Liquid Penetrant Examinat'on," Revision 2, dated December 1,
1989.
FC-UT-2, " Ultrasonic Examination of Class 1 and 2 Vessel Welds Greater
Than 2 Inches," Revision 3, dated December 1, 1989.
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OPPD-410-004, " Procedure for !!ulti-frequency Eddy Current Examination of
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Honferromagnetic Steam Generator Tubing Using MIZ-18 Equipment,"
Revision 3, dated rebruary 28, 1990.
3.2 Witnessing of 151 Work Activities The inspector witnessed the performance of the following examinations:
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d Liquid penetrant examination (PT) of the four welds of Pipe 12-SRD-20 to
plates on Isometric A-42 and Pipe Weld 2.5-PRL-2/11 on Isometric A-20.
Ultrasonic examination-(UT) of Circumferential Weld PR2-SC-5-403 and
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Longitudinal Welds PRZ-SC-5-403 A and D on Isometric A-03.
It was noted by the inspector that examination personnel appropriately complied with the examination, calibration, and documentation requirements of the approved procedure:,. The use of the correct UT calibration blocks was verified by the inspector. The inspector also checked the personnel certifications to
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verify that personnel _wcre appropriately qualifiet'. for the examinations serformed. The equipment used (pT materials UT search units UT scopes 3 and-JT gels) was found to be appropriately certified and the instruments calibrated
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It was additionally noted by the inspector that the 151 contractor's performance was monitored by a qualified member of the licensee's
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OC staff. The monitoring of contractor performance had been a coment in an earlier NRC Inspection Report 50 285/88-29.
The inspector also reviewed records of 151 examinations performed during this outage, including those
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applicable to the eddy, current examinations of steam generator tubing. No problems or discrepancies were noted during this review. The results of-inspection of repair / replacement welding activities are documented in paragraph 4 of this report.
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3.3 Licensee Actions in Recard to NRC Information Notice 90,04,
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A review was performed of the licensee's analysis of NRC Information No+,1ce 90-04, which pertained to cracking of the upper shell to transition cone
girth weld of steam generators. To date, this problem has been observed at
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domestic plants only in Westinghouse steam generators, whereas, FCS has
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CombustionEngineering(CE)steamgenerators. The licensee had previously reviewed information on this subject contained in NRC Information Notices 82-37 and 85-65. As in the past, the licensee concluded that FCS did not have this problem. - A review of the chemistry history found no problems with respect to control.of oxygen, chlorides, or copper. The feedwater sparger is below the water: level and therefore is not a source of thermal cycling. The closure weld on the CE steam generators is about half way down the lower shell, it was
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noted that the licensee intends to perform a visual exaraination during this outage of one of the subject girth welds and an auxiliary feedwater nozzle.
This visual exernination will also ascertain whether any corrosion pitting is present on the inside surfaces of the steam generator, ar.d is being performed in preparation for perforr.ance of the UT discussed in the notice.
No violations or deviations were identified in this area of the inspection.
4.; WEl. DING (55050aniSS100)
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The current FCS program for control of safety-related welding activities was previously inspected in flRC Inspection 50-285/90-16. The absence of in-process
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welding activities at the time of that irspection precluded verification of the cornpliance of personnel with the requirements of welding procedure-
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specifications. During this inspection, the inspector reviewed Maintenance Work Orders 864512, 894453, 894023, and 894525, which were repair / replacement activities perforraed by the licensee under Section XI of the ASME Code, in addition, the inspector witr,essed the gas tungsten arc welding of replacement backwashing pipe on Maintenance Work Order 864512. The welding activity was found ta be performed in accordance with the weiding procedure specification requirements for emperage, voltage, welding speed, gas flow, filler material, base meterial, and type of electrode used.
It was additionally noted that the licenste's QA staff had performed a detailed surveillance of this welding
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No violations or deviations were identified in this area of the inspection.
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GIT,jiEETING IT Exit meetings were held on liarch 16 and April 12, 1990, with those individuals denoted in paragraph 1 of this report. At this me.cting, the scope of the inspection and the findings were summerbed. The licensee did not identify as proprietary any of the information provided to, or reviewed by, the inspector.
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