IR 05000244/1992006
| ML17262A853 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/11/1992 |
| From: | Gray E, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17262A852 | List: |
| References | |
| 50-244-92-06, 50-244-92-6, NUDOCS 9205190084 | |
| Download: ML17262A853 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
2 p N
.
51124 /42-56 Docket No.
2L244 License Nos.
~DPR-I Licensee:
R h ster a & Electri dpdadk R
he er New York l4 rai n Facility Name:
R E irma Nuclear P wer Pl nt
6 6:~NY 2
6
d N.: ~l-1
Inspector; R. A. McBrearty, eactor Engineer, Engineering Branch, Materials Section, Division of Reactor Safety date
\\
r Approved by:
C E. H. Gray, Chief, Ma erials Section, Engineering Branch, Division of Reactor Safety date In tion Summar d: 6 dd I
d d dd
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6*4
program, the steam generator tube eddy current examination program and associated activities.
The inspection was conducted to ascertain whether the programs conformed to applicable requirements and whether the activities were performed in a way that confirms the plant's acceptability to return to operation.
R~eutt; The iicensee's ISI program and its steam generator tube inspection program are approved by the NRC, and are being implemented in a way that will confirm the plant's acceptability to safely return to operation.
Examination personnel are certified to the appropriate level of competence and additionally, eddy current data analysts are required by the licensee to successfully complete a site specific training and qualification program.
92051'F0084 920511 PDR ADOCK 05000244
a
1.0 Inservice Inspection (ISI) Program (Inspection Procedure 73051)
A nuclear generating facility depends on numerous systems,and components for the safe operation and shutdown of the facility; To assure that those systems and components will operate when required, the NRC requires that an ISI program be established.
Specific inspection
'equirements regarding method and frequency are contained in the ASME Boiler and Pressure Uessel Code,Section XI.
The R. E. Ginna facility is in its third 10-year inspection interval, which comm'enced, on January 1, 1990, and is scheduled to end on December 31, 1999.
The refueling outage now in progress is the last scheduled outage of the interval's first period.
The applicable code for the interval is the 1986 edition of the ASME Code,Section XI. The licensee's submittal to the NRC for approval included the 10-year program and related requests for relief from code requirements
'hich are considered by the licensee to be impractical. Program status is tracked by the licensee using a computer-based tracking system.
Conclusion The NRC approved ISI program is tracked by the licensee using a system that is capable of identifying up-to-date program status.
2.0
'nservice Inspection Activities (Inspection Procedure 73753)
Inservice inspection activities at Ginna are performed by licensee and contractor personnel using licensee procedures under the direction of the licensee.
The ultrasonic examination of the main steam header Tee to Pipe Weld G-2, including data acquisition, was observed to ascertain that the examination was properly performed in accordance with applicable requirements and procedures.
Proper performance of the examination is necessary to permit the acquisition of accurate data that willprovide the means for,the licensee to assess the capability of the plant to safely return to service.
The examination was performed by contractor personnel using the AMDATAIntraspect 98 automated ultrasonic examination system, and the data were evaluated by a licensee analyst.
The process resulted in information that was sufficient to assess the quality of the subject weld. The data analyst manually obtained supplemental thickness measurements of the appropriate portions, of the weld to assist in plottin'g the location of recorded reflectors.
The plotting was performed using the Raytrace version 2.0 computerized system for plotting ultrasonic reflectors.
All pertinent information, data and analysis, was included in the final package to permit reviewers to reproduce the examination and for comparison of the results with data from future inservice inspections.
Qualification/certification records oflicensee and contractor nondestructive examination personnel who participated in the performance of ISI at the plant were selected for inspection to ascertain
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that those personnel were properly qualified to perform their assigned responsibilities.
Records of AMDATAand Southwest Research Institute (SWRI) personnel were included in the selected records.
The certification records were determined to be in accordance with the applicable requirements of SNT-TC-1A, the governing document, and they confirmed that examination personnel were properly qualified and certified to the level of competency appropriate for carrying out their assigned duties.
Inservice inspection nondestructive examination related (NDE) results that are not clearly acceptable are tracked via the nonconformance report (NCR) system.
A log of issued NCRs is maintained by the ISI group which, at the time of this inspection, contained few entries, all of recent vintage, none of which were completely processed.
Three of those NCRs were selected for review to ascertain that'they were entered into the system and that the nonconforming condition was clearly identified.
The following were selected for review:
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NCR No.92-127, documenting liquid penetrarit indications on line 6D-AC-601 support lugs
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'NCR No.92-130, documenting liquid penetrant linear indications on IWAlug associated
. with SIU-85
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NCR No.92-147, documenting a bent hanger rod on component FWU-02 on 14" feedwater line, system 14A-FW-900-1A The bent hanger rod was considered to be a service related defect and resulted in the licensee expanding the inspection sample of feedwater system supports.
The inspection sample expansion resulted in the inspection of 100% of the spring can supports on 14" FW loop "A" inside containment and 40% of those supports on the "B" loop. No additional defects were identified..
The original defect was found on the "A" loop.
The NCRs were ascertained to be in the tracking system, and were prioritized regarding the timeliness of closeout.
A list of open NCRs is published on a daily basis and, among other attributes, the list identifies at which stage of plant startup specific NCRs must be closed.
Conclusion Ultrasonic examinations and data analysis were performed by qualified personnel, and provided information which confir'med that the subject weld was acceptable for contained service.
Examination results were complete and capable of being used for comparison to future'inservice inspection results.
Nonconforming results are clearly documented and tracked.
Controls are in place to identify unclosed nonconforming items,and permit management to make decisions regarding open NCRs and plant startu v
p 3.0 Steam Generator Tube Eddy Current Examination (IP'73753)
The Ginna facility is a Westinghouse two-loop pressurized. water reactor with Series
recirculating steam generators.
Each generator contains 3,260 millannealed Inconel 600 U-bend tubes seal welded into a 22" thick tubesheet.
From the hot function testing in November 1969, until November 1974, the plant operated with phosphate secondary side water chemistry.
In, November 1974, the plant converted to AllVolatile Treatment (AVT)chemistry control which is maintained at the present time.
The steam generator tube eddy current examination plan for the third 10-year inspection interval incorporates the requirements of the current revision of Appendix B, "Ginna Station Inservice Inspection Program for the 1990-2000 Interval," of the Ginna Quality Assurance Manual, as required by the facility Technical Specification 4.2.1.
Additionally, provisions of NRC Regulatory Guide 1.83, Revision 1, and recommendations of the Electric Power Research Institute PWR Steam Generator Inspection guidelines are included in the plan.
There are 2,748 unrepaired tubes in the "A" steam generator and 1,998 unrepaired tubes in the
"B" steam generator which were examined in the tube sheet crevice area using a motorized rotating pancake coil (MRPC).probe from the hot leg side.
The MRPC probe was used, additionally, for the examination of the expansion area of Combustion Engineering (CE) sleeves, Babcock and Wilcox (B&W) Company plugs, the u-bend of rows 1 and 2, and the appropriate portions of selected tubes in each generator.
Allof the MRPC examinations were performed from the hot leg and/or cold.leg side as defined by the April 1992 Outage Inspection program.
The examination in each generator of CE and B&Wsleeves was performed from the hot leg side using a bobbin coil probe, and a large number of selected tubes in each steam generator were inspected full length using a bobbin coil probe from the hot leg and cold leg as appropriate.
The rupture of a Westinghouse explosively plugged tube in the "B" steam generator resulted in the eddy current examination of all tubes in the generator bounding tubes that are plugged with Westinghouse explosive plugs.
Those tubes were examined from the hot leg side to the first hot leg support plate, and included approximately 100 "B" generator tubes and more than 400 tubes in the "A" generator.,
The steam generator tube status pr'ior to the outage was as follows:
Number of Number of R~
~bl I ~d tlAII ttBtl 187 323 325 939
J
The eddy current examinations performed during the ongoing outage identified 228 tubes in the
"A" generator and 181 "B".generator tubes that require repair.
The licensee plans to perform the repairs by installing sleeves in as many of the tubes as is possible and plugging the remaining tubes.
At the conclusion of this inspection, the licensee had not yet identified the specific tubes requiring a particular type of repair.
Data analysis was performed by a primary and a secondary analyst, each having equal authority.
A, resolution person/team has the responsibility for resolving discrepancies between the primary and secondary analysis results. A listofdiscrepancies is provided by data management personnel to the resolution persons/team.
The resolution team may consist of two analysts (such as the primary and secondary analysts),.or a single analyst (not the primary or secondary analyst), such as a third Level IIor Level IIIanalyst or the eddy current supervisor.
Any changes to override calls that would require corrective action must be done with the concurrence of a second Level II or Level IIIanalyst.
Any indications which can't be resolved by the resolution team shall be brought to the attention of the licensee's Level IIIfor disposition.
Personnel performing data analysis shall be qualified in accordance with the requirements of the licensee's procedure QMEIS 909, "Qualification of Nondestructive Examination Personnel" or an equivalent qualified and approved supplier's program. 'Data analysts must be qualified to a minimum of Level II, and shall have received specific training for the evaluation of 'data from non-ferromagnetic tubing.
Additionally, successful completion of site specific proficiency examinations is required of all personnel prior to their analyzing any data from the planned program.
Personnel qualification/certification records of individuals responsible for the acquisition and analysis of eddy currentdata at Girina confirmed that each individual was certified to the appropriate level of competency as mandated by the licensee's program.
Conclusion
- The steam generator tube eddy current, examination program is effective for detecting conditions that degrade steam generator operation.
The licensee's intent to maintain its steam generators in'a safe condition is evidenced by the training and qualification program to which examination personnel are subjected prior to acquiring or analyzing eddy current data at Ginna.
Further evidence of that intent is exhibited by the scope of the examinations performed during the April 1992 outage, and the extensive use of the motorized rotating pancake coil probe to enhance its ability to find degrading conditions.
4.0.
Exit Meeting The inspector met with licensee representatives (denoted in Attachment 1) at the conclusion of the inspection on April 17, 1992.
The scope and findings of the inspection were summarize '
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Per n
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ATl'ACHMENT1 R
h tr El tri i n
~G. Geicken, Supervisor, Material Engineering
~F. Klepacki, Inservice Inspection Engineering
- P. Lewis, Engineering Assistant, NDE, Materials Engineering and Inspection Services
- R. Marchionda, Superintendent, Support Services W. McCoy, Department Manager, Quality Performance
- M. Saporito, Manager, Materials Engineering and Inspection Services K. Wachter, Senior Engineering Assistant U.. Nuclear Re ul t mmi sion
- T. Moslak, Senior Resident Inspector Asterisk denotes those present at the exit meetin I
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