IR 05000440/1990021
| ML20024G040 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/18/1990 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G037 | List: |
| References | |
| 50-440-90-21, NUDOCS 9012270269 | |
| Download: ML20024G040 (4) | |
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i U._S. NUCLEAR REGULATORY COMMISSION
REGION III
-Report No. 50-440/90021(DRS)-
Docket No.
50-440-License No. NPF-58-Licensee: The Cleveland Electric Illuminating Company i
10 Center Road i
Perry, Ohio 44081
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Facility Name: - Perry Nuclear Power Plant, Unit 1 Inspection At:
Perry Site, Perry, OH Inspection Conducted: October 22-24 and December 12, 1990 Inspector: $) YL lh/EfN K. D.-Ward-Date Approved'By: od N d k d d h ~
/s/F//90-
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D. H. Danielson, Chief Date liaterials and Processes Section
Inspection Summary.
Inspection on October 22-24 and December 12,1990'(ReportNo.50-440/90021(0RS))
Arecs Inspected:
Routine, unannounced safety inspection of inservice
' inspection (ISI)activitiesincludingreviewofprograms(73051),(procedures (73052), observation of work activities (73753), and data review 73755).
.Results: No violations:or deviations were identified.
Based on the results of the inspection, the NRC inspector noted the follcwing.
-The licensee demonstrated the ability to properly implement the ISI
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program on Unit I in accordance with ASME Section XI and the licensee's program.
' The licensee had an adequate ISI staff that was well trained and competent.
-Management involvement was evident.
9012270269 901219 PDR ADOCK 05000440.
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DETAILS
1.
Persons Contacted Cleveland Electric Illuminating Company (CEI)/Centerior Service Company (CSC)
- W. Dervay, ISI Supervisor
- H. Walls, Jr., Supervisor NDE, Corporate Level III
- R. Portmann, NDE Supervisor i
- C, Wirtz, 151 Coordinator
- R. Matthys, Mechanical QA Engineer
- C. Elberfeld, Operations Analyst UniversalTestingLaboratories,Inc.(UTL)
F. Stoll, Project Manager U. 5. Nuclear Regulatory Commission (NRC)
P. Hiland, Senior Resident Inspector G. O'Dwyer, Resident Inspector Hartford Steam Boiler Inspectors and Insurance Company (HSB)
W. Zimmerman, ANil The NRC inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the exit. interview on December 12, 1990.
2.
Inservice Inspection (ISI) Unit 1 a.
Review of Program (73051)
UTL and CEI personnel performed the ISI program in accordance with ASME Section XI, 1983 Edition, Summer 1983 Addenda.
There was sufficient organizational staff to ensure that acceptable ISI work was performed. The sampling inspection plan for addressing intergranular stress corrosion-cracking (IGSCC) concerns was in accordance with Generic letter (GL) 88-01. All 58 welds were inspected in accordance GL 88-01.
Fifty-six welds were found to be acceptable and two welds were found to have indications (details are in Paragraph
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2.c.(2)) of this report. -Where ASME requirements were determined to be impractical, specific relief from NRR was requested in writing.
The NRC inspector reviewed specific relief requests and related i
documentation.
The NRC inspector also reviewed CEI QA Audit No.
J PA 90-19, and surveillances of ISI activities conducted by
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qualified personnel to verify compliance with the ISI program.
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b.
Review of Procedures (70052)_
All applicable 151 procedures were approved by the Authorized Nuclear Inservice Inspector (ANil) and were reviewed by the NRC inspector.
The nondestructive ew>minations (flDE) were performed in accordance with ASME Section V, 1983 Edition, Summer 1983 Addenda, c.
Data Review and Evaluation (73755)
(1) The examination data was within the criteria as outlined in the applicable !!DE procedures and ASME Code requirements. The flRC inspector's review included examination of documents relating to HDE equipment, data, and evaluations.
(2) All sb. feedwater nozzle to safe end welds were ultrasonically examined (UT) during this outage. Unacceptable indications were detected in nozzles !14E and H4C. The indications are oriented in a circumferential direction and are located near the junction of the feedwater nozzle safe end and the Inconel 182 buttering. The N4E nozzle indication is 1.6" in length and 0.15" in depth, while the H4C nozzle indication is 2.9" in length and 0.15" in depth.
Since both flaws are the same depth and near the same location, CEI felt that justification for the larger flaw would serve as technical justification for both.
The UT indications were not identifiable as characteristic of IGSCC. The final flaw size was determined by the licensee to be acceptable in accordance with ASi1E Section XI, Tables IWB.3641-5 and 3641-6, for the full duration of the next operating nominal 18 month cycle. CEI plans to reultrasonically examine the two nozzles during the next refueling outage, and further engineering evaluation will be performed at that time, in accordance with Generic i.etter 88-01, CEI submitted to NRR their evaluations for continued service of the flawed feedwater nozzles. P R has the lead on this matter and during telecons, HRR stated that permission to start back up will be granted.
However, NRR informed CEI that they will be requesting further information for justification of crack growth values utilized in CEI calculations. Aho, NRR requested an evaluation of personnel exposures should NRR request the plant to shut down mid-cycle to re-size the flaws.
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ObservationofWorkActivities(73753)
The flRC inspector observed work activities in progress and had discussions with personnel during the observation of ISI activities. These observations included the following:
(1) UTL personnel performing liquid penetrant examinations on h;gh pressure core spray welds flo. 6 and 7.
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(z, Viewing by video, the visual examination performed by UTL and CEI:
P. ) Shroud head stud bolts; b
Source range monitor dry tubes; c
Core spray sparger; and d
RPV steam dryer.
'(3) UTL personnel performing ultrasonic exami. nations op high pressure core spray welds No. 20 and 21.
The NRC inspector reviewed the qualification and certifications of all inspection personnel on site to ensure conformance witi.
SNT-TC-1A. The personnel performing ultrasonic examinations on stainless steel welds susceptible to IGSCC were qualified at Electric Power Research Institute (EPRI).
No violations or deviations were identified.
3.
ExitInterview(30703)
The NRC inspector met with site representatives (denoted in Paragraph 1)
at the conclusion of the inspection on Decen6er 12,1990. The NRC inspector summarized the scope and findings of the inspection noted in this report. T!; NRC inspector also discussed the likely information content of the inspection report with regard to documents or processes reviewed by the NRC inspector during the inspection. The licensee did not identify any such documents / processes as proprietary, i
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