IR 05000155/1990021
| ML20024F843 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/19/1990 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024F841 | List: |
| References | |
| 50-155-90-21, NUDOCS 9012270034 | |
| Download: ML20024F843 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 111 Report No.:
50-155/90021(DRS)
Docket No.:
50-155 License No.: OPR-6 Licensee: Consumers Power Company 1945 West Parnall Road Jackson, MI 49201 Facility Name:
Big Rock Point Nuclear Plant Inspection At:
Big Rock Point Site, Charlevoix, MI 49720 Inspection Conducted: October 9-17 and December 10, 1990 Inspector: k,[ MM
///J/' fC K. D. Ward Da te (October 9-11, 15-17, and December 10, 1990)
llRC Region i NDE Mobile Team (October 9-16,1990)
Approved By:
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D. H. Danielson, Chief Date Materials & Processes Section Inspection Summary inspection on October 9-17 and December 10, 1990 (Report No. 50-155/90021(DRS))
Areas Inspected:
Routine unannounced safety inspection of inservice inspection (ISI) activities including review of programs (73501), procedures (73052), observation of work activities (73753), data review (73755), and NRC independent ultrasonic examination of selected welds on the main recirculation system and the reactor clean up systen (57080).
Results: No violations or deviations were identified.
Based on the resultc of the inspection, the NRC inspector noted the following:
The implementation of 151 follcwed the requirements of ASME Section XI and the licensee's program.
The licensee's staffing of the ISI group was adequate, and the personnel
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were very knowledgeable and conscientious.
The NRC nondestructive examination laboratory personnel found two small indications in weld #24-MRSD-121-1 that were later found to be nonrelevant indications by EPRI qualified individuals from ItQS.
9012270034 901220 PDR ADOCK 05000155 G
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DETAILS 1.
Persons Contacted Consumers Power Company (CPCo)
- W. Beckman, Plant Manager
- G. Withrow, Engineering Superintendent
- M. Acker, ISI Coordinator
- D 11oeggenberg, Engineering Supervisor
- R. Alexander, Technical Engineer
- L. Monshor, QA Superintendent J. Beer, Health Physics Supervisor U. S. Nuclear Regulatory Commission (NRC)
E. Plettner, Senior Resident Inspector D. Jones, Senior Resident inspector (Acting)
T. licLellan, NRR
- R. McBrearty, Reactor Engineer, Region 1 R. Harris,ilDE Technician, Region 1 D. Wiggins,11DE Technician, NRC Contractor M. Itingus, NDE Technician, ilRC Contractor Factory Mutual Engineering R. Alsbry, ANIl The NRC inspector also contacted and interviewed other licensee and contractor employees.
In addition to the NRC inspector, denotes those present at the NRC llobile NDE Team exit interview conducted October 16, 1990.
- Denotes those present at the exit interview conducted December 10, 1990.
2.
InserviceInspection(ISI).
a.
General During the period of October 9-16, 1990, a flRC independent measurements inspection was conducted using the llRC mobile nondestructive examinations (llDE) laboratory.
The NRC IIDE laboratory was dispatched to the site at the request of the NRR staff. Under the requirements of NUREG-0313, Revision 2, and Generic Letter 88-01, a number o1 stainless steel (SS) welds which had not been required to be ultrasonically examined in the past, are now required to be examined.
Because of the lack of ultrasonic examination (UT) data, the NRR staff had concerns regarding the condition of the SS piping systems.
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b.
UltrasonicExamination(57080)
Eight safety-relateu ASliE Class 1 stainless steel pipe weldments
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were ultrasonically e_xamined using_ a Sonic Itark I ultrasonic flaw detector in accordance with NRC Procedure NDE-23, Revision 0, the licensee's procedure, 22.A.35-6009, Revision 3(Ultrasonic i
Examination of Austenitic Piping and Branch Connection Welds for IGSCC),andassociatedultrasonictestdata.
Instrument calibration (linear verification) was performed using NRC Procedure NDE-2,
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Revision 1.
A distance amplitude correction curve (DAC) was constructed using the licensee's calibration standards BRP-38,
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BRP-34, BRP-19, BRP-9, and BRP-35. The instrument settings and search units (transducers) were matched as closely as possible to those indicated by the licensee's available ultrasonic data reports. The following is a list of specific weldments examined.
Weld Identification Component Material Size
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5-MRS-131-5 Pipe / Elbow SS/316 5 inch 5-MRS-131-6 Elbow / Pipe SS/316-5 inch 4-MRS-141-4 Pipe / Elbow SS/316-4 inch 4 -MRS-141 -5 --
Elbow / Pipe SS/316 4 inch
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17-MRS-111-7 Red./ Elbow 316/240-Il 17 inch 24-MRS-121-1
.Tec/ Reducer 240-M/316 24 inch.
3-RCS-101-8 Pipe / Elbow SS/304 3 inch 3-RCS-108-9 Pipe / Elbow
.SS/304 3 inch-The examination included the use of 1.0 MHZ, 45 shear wave, the Delta technique, and the WSY-70 transducer, which is recommended by the EPRI NDE-Center for verification of the presence of flaws and
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-for sizing of. flaws. The two instances where case stainless steel was encountered were the elbow side of weld 17-MRS-111-7 and the tee side of weld 24-MRS-121-1.:-Those welds were examined only from the-
- reducer side.due-to the as-cast surface of the tee and the elbow which did not permit adequate coupling of.the ultmsci.ic transducer.- No attempt was made to improve the surTaces by grinding -
_because of'ALARA considerations, and the concern that mitimum wall thickness would be violated by the grinding ope)atio;.
Results-Main recirculation system weld 24-MRS-121-1 was examined using a 1.0-MHz~ 1" diameter transducer generating a shear wave with'a 45'
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angle.- Indications of two (2) reflectors were identified, 40% of DDAC, 21" long at the 270' location and 50% DAC, 4"-long located 3"
.CCW from top dead' center of the reducer.. The examination was
_ performed from the: reducer side only as discussed above.
In addition to the 45' examination, supplemental examinations of the area of
' indications were performed using the Delta technique and the.
30-70-70 mode conversion technique using a WSY-70 transducer which is recommended by the EPRI NDE Center as a method for discriminating among geometric and non-geometric reflectors. The ID creeping wave-generated by the WSY-70 transducer does not readily res1ond to geometric reflectors. The reflectors were confirmed by eac1 of the supplemental ultrasonic examination methods.
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Radiographs of the weld were not available for review to aid in evaluating the ultrasonic examination results. At the time of plant
construction (1950-1960 era) radiographs were required to be retained I
for a period of only ten years. The remaining welds were found to be accepte sle.
c.
Review of Program (73051)
i CPCo, Energy Supply Technical Services personnel and liQS (three welds) performed the ISI in accordance with ASME Section XI, 1977 Edition, Sumer 1978 Addenda. The staff size was sufficient to
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ensure that the ISI work was adequately _ performed. The NRC inspector
reviewed.CPCo QA Audit tQT-90-01, and surveillance of ISI activities conducted by qualified personnel to verify compliance with the ISI program.
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Review of Procedures All applicable ISI procedures were approved by the authorized nuclear' insurance inspector (ANil) and were reviewed by the NRC inspector. _The ISI procedures were found to be in accordance with ASilE Section V,1977 Edition, Sumer 1978 Addenda.
e.
Data Review and Evaluation (73755)
The e'xamination data'was within the criteria as outlined in the applicable NDE procedures and ASi1E Code requirement. The NRC inspector's review included examination of documents relative to l
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llDE equipment, data, and evaluations.
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Observation of Work Activities (73753)
'The llRC inspector observed flRC NDE lab personnel performing ultrasonic examinations on various calibration blocks and pipe welds.
The NRC inspector reviewed the qualifications and certifications of all inspection' )ersonnel on site performing ISI to ensure conformance wit 1.SNT-TC-1A.
tio. violations or deviations were identified.
3.
Exit Interview (30703)
'At.the RegionLI exit, the Region 1 personnel requested that CPCo hire a HDE EPRI-trained, qualified and certified individual in detection and sizing for IGSCC defects. The EPRI qualified _ individual was-to UT the weld, and CPCo was to report the results to Region I and llRR prior to.-
startup indicating if the two indications were IGSCC or some other type it,01 cations.- CPCo contracted EPRI qualified individuals ~from MQS-Inspection, l_nc.,-to UT the weld. The MQS individuals found that the two small indications were acceptable slag in the weld i" from the inside wall.
CPCo requested itQS personnel to UT two additional 5" welds for IGSCC; they were found to be acceptabic. Region I and NRR agreed with the results, and no additional welds were UT'd.
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The t!RC inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on December 10, 1990. The NRC inspector summarized the scope and findinos of the inspection noted in this report.
The NRC inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietary.
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