IR 05000334/1990024
| ML20029A184 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/11/1991 |
| From: | Gray E, Kaplan H, Patnaik P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20029A180 | List: |
| References | |
| 50-334-90-24, 50-412-90-24, NUDOCS 9102050021 | |
| Download: ML20029A184 (6) | |
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V. S. NUCLEAR REGULATORY COMMISSION
REGION I
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Report No.
50-334/90-24; 50-412/90-24 Docket No.
50-334; 50-412 License No. DRP-66, NPF-73 Licensee:
Duquesne Light Company
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Robinson PTaza Building No. 2
[Pittsburgh, Pennsylvania Suite W10, PT Route 60, 15205 Facility Name:
Beaver Vallev Power Station, Unitt 1 and_2
Inspection At:
Shippingpor_t, Pennsylvania Inspection Conducted: December 3 - December 6, 1990
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Inspectors:
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Prakash Patnaik, Reactor Engineer, MPS, EB, date DRS, Region I KuL&t
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Herbert J. raplan,' Senior Reactor Engineer.
I ~date MPS, EB, DRS, Region I
Approved by: [
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_E. Harold Gray, hief, Materials & Processes date Section, Engineering Branch, DRS, Region !
Inspection Summary: A routine unannounced inspection was performed from December 3 to D'ecember 6, 1990 (Report Nos. 50-334/90-24;50-412/90-24).
Areas Inspected: The areas covered were inservice inspection, steam generator eddy current examination, and water chemistry control.
Results: No violation or deviation was identified, l
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9102050021 910123 PDR ADOCK 05000334 O
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DETAILS 1.0 Persons Contact _ed Duquesne Light Company
- T. P. Noonan, General Manager, Nuclear Operations
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- N. R. Tonet.
Manager, Nuclear Safety
- $. C. Fenner, Manager, Quality Services
- W. Sikorski, Director 1.5.1.
- M. Parlick, Director, Quality Services
- M. Pergar, Director Quality Services, Inspection & Examiniation
- D. Orndorf, Director, Chemistry
- B. Sepelek, Licensing Engineer
- F. Lipchick, Senior Licensing Supervisor
- T. Heimei, NDE Specialist D. Grabsky, Senior Engineer United States Nuclear Regulato y_Commissio_n J. E. Beall, Senior Resident inspector P. Wilson, Resident Inspector
- Denotes those attending the Exit Meeting.
The inspectors also contacted other administrative end technical personnel during the inspection.
2.0 Introduction The Beaver Valley Power Station is a twin unit, three loop Westinghouse designed prt surized water reactor plant designed for a rated output of 2,060 MWt.
Unit No I was licensed for commercial operation on January 30, 1976 and Unit No. 2 was licensed for commercial operation on August 14, 1987. The steam generators are vertical shell and U-tube, Westinghouse Model 51.
Both units have adopted the 1983 Edition of the ASME boiler and Pressure vessel Code, section XI, including the Summer 1983 Addenda.
3.0 References / Requirements Technical Specification - Steam Generators paragraph 3.4.5 Final Safety Analysis Report - Steam Generators paragraph 4.2.2.4 PWR Seconaary Water Chemistry Guidelines - Electric Power Research Institute Special Report, EPRI NP-2704-SR ASME Boiler and Pressure vessel Code,Section XI,1983 Edition including Summer 1983 addenda, e
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3.0 Steam Generator _ Eddy Current Inspection - Unit No. 2 Scope The inspectors reviewed eddy current examination data from the second refueling outage of Unit No. 2.
The examination was performed during the third week of September, 1990 by Westinghouse.
Results of Prior Inspection During the inservice inspection in April,1989 (the first refueling outage of Unit No. 2) twenty percent of the total number of tubes in Steam Gener-ators (S/G) A and C of Unit No. 2 were examined by eddy current.
The inspection identified only one location with 31 percent wall-thinning in the free span between the seventh and eighth hot leg support plates of S/G A (tube Row 40, Column 27).
This is below the plugging limit.
However, tubes at Row 11, column 4 and Row 9, Column 33 in S/G C were each preventively plugged in accordance with IE Bulletin 88-02 " Rapidly Propagating Fatigue Cracks in Steam Generator Tubes."
Details of Review The inspectors reviewed the results of the 1990 inspection and discussed the results with cognizant personnel.
The examination covered twenty percent of the total number of tubes in "B" Steam Generator.
The licensee ter td a total of 691 tubes as per the following test plan:
658 tubes tested full length from hot leg tube end to cold leg tube
end, using a Bobbin coil probe.
62 of the above tubes in Rows 1 and 2 were tested in the U-bend
region using a Rotating pancake coil.
33 tubes tested in the straight portion from hot leg tube end to the
eighth support plate using a Bobbin coil probe.
The inspector concluded that the examination met the requirement of the Technical Specification. Although there was no rejectable indication found in the data, the licensee reported the presence of one indication which was 30 percent through wall.
Review of records indicated that all Steam Generators in Unit 2 had the tube sheet to tube expansion region shot peened and the U-bends in Rows 1 and 2 tubes stress relieved prior to service.
Three tubes in "B" Steam Generator were plugged prior to service.
There are twenty two plugged tubes in all three steam generators.
All plugged tubes used mechanical plugs with plug-in plug.
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4 Data Analysis The inspectors reviewed the licensee's Eddy Current Analysis Guidelines.
ISI-GL-004B, Rev. O, to determine that these guidelines were adequate for providing the data analyst with info mation to assure that all data was properly analyzed.
These guidelines orovided the analysts with sufficient information to provide continuity between organizations performing the analysis and to assure that differences were resolved in a conservative manner.
The Bobbin Coil data analysis was performed by two independent analysts from different contractors.
The Rotating Pancake Coil data were analyzed by the two different analysts from a single contractor.
The inspectors reviewed the certifications of five personnel engaged in the eddy current examination.
The certifications were found to meet the requirements of SNT -TC-IA.
The drawings and the material certifications on the eddy current calibra-tion standards E-360 and Z 6381 were reviewed and found to be within ECT procedure guidelines.
5.0 Inservice Inspection Portions of the inservice inspection program were reviewed to determine the licensee's compliance to ASME Boiler and Pressure Vessel Code Section XI, as required by the Technical Specification and other augmented inspections committed to by the licensee.
Details of Review The inspectors reviewed the inspection plan for Beaver Valley Unit No. 1 including the Reactor Coolant System isometric 8700-151-0999 D-2 app?icable to the second interval of the current ten year plan to assess code compliance.
The welds EW-1, 37 and 39 in the Pressurizer Surge line of Unit No I were selected for review.
The subject welds were examined in 1989 by liquid penetrant and ultrasonics to investigate possible cracking due to thermal stratification identified in NRC Bulletin 88-11.
The inspectors found that the weld EW-1 was not examined in accordance with ASME Section XI with regard to the code required volume. The licensee stated that the ultrasonic examination was not a requirement of NRC Bulletin 88-11 and was performed for information only. The licensee is planning to perform the ASME Code required examination during the second period of the second ten year interval.
The review of data on the remaining welds identified no other questionable items.
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The inspectors reviewed the Ultrasonic Examination Procedure UT-303 Rev. 8 applicable to the subject welds for compliance to ASME Code,Section V and found it to be acceptable.
The Inspectors next reviewed the inservice inspection records on Unit No. 1 Reactor Vessel Core belt line weld No. C-5 and did not find any reportable indications.
The inspectors reviewed the Certificate of Qualification of two UT NDE Technicians.
There were no discrepancies noted.
l 6.0 Water Chemistry Control Water chemistry data.were reviewed as part of.the steam generator and maintenance inspection.
The method of collecting and verifying the accuracy of-these data, was not included in the scope of this inspection.
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Details of Review The-inspector interviewed cognizant personnel and discussed the control of primary and secondary ' water chemistry in the plant systems. The results of
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the controls for secondary water chemistry were also reviewed for the current calendar year. The Chemistry Performance Itadex (CPI) based on-cation conductivity, sodium and oxygen is a weighted average of three principal corrosion causing impurity concentrations-divided by the EPRI upper specification limits.
During cycle 8 of Unit No.1, the yt ar-to-date CPI was 0.43 and during cycles 2 and 3 of Unit No. 2, the year-to-date CPI was 0.23.
The plant upper level limit is 0.50.
The unit No. 1 CPI is higher due to some condenser tube leakage, that is currently being identified for repair.
The control of pH in secondary water is governed by morpholine.
The licensee ~ attempts-to maintain a pH of 9.3 to-reduce erosion / corrosion, iron transport and sludge in the steam generators. -This practice has been successful on the basi.s that erosion / corrosion degradation has been limited to a few components, and virtually no sludge in the steam generators has been observed.
The licensee attempts to maintain a pH of 7 to 7.2 in the primary system during Mode I by controlling lithium in the reactor coolant system.
During cycle 8 of Unit No I and Cycle 3 of Unit No. 2, the lithium control in the reactor coolant system has been appropriate.
For the most part, the lithium level in the reactor coolant system has been between 1.9.to 2.2 ppm which is within the industry guideline.
The licensee's training program-for chemistry personnel was reviewed and found to be satisfactory.
Chemistry Personnel Training is on schedule and completion _is expected by the end of the year.
The inspectors reviewed an inhouse audit-report by the licensee's Quality Assurance Unit, on plant chemistry.
The report identified one finding and one observation which were resolved in a timely manner by the licensee.
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Management Meetings Licensee management was informed of t ' scope and purpose of the inspection at the entrance meeting on Decemoer 3, 1990.
The findings of the inspection were discussed with licensee representatives during the course of the inspection and presented to licensee management at the Exit Meeting on December 6,1990 (see paragraph I for attendees).
At no time during the inspection was written material provided to the license by the inspectors, The licensee did not indicate that proprietary information was involved within the scope of this inspection.
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