IR 05000266/1992011
| ML20198D703 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/14/1992 |
| From: | Jeffrey Jacobson, Schapker J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20198D697 | List: |
| References | |
| 50-266-92-11, NUDOCS 9205210120 | |
| Download: ML20198D703 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-266/92011(DRS)
Docket No. 50-266 License No. DPR-24 Licensee:
Wisconsin Electric Power Company 231 West Michigan - P379 Milwaukee, WI 53201 Facility Name:
Point Beach Nuclear Plant - Unit 1 Inspection At:
Two Rivers, WI 54241 Inspection Conducted:
April 14-16 and May 5-7, 1992
/
i Inspector:
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Date Approved By:
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. M. C ac son, Chief Date l
4ateric and Processes Section Inspection Summary i
i Insoection on April 14-16 and May 5-7, 1992 (Recort_Fo.
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50-266/92011(DRS))
Areas Inspected:
Routine unannounced inspection of inservice inspection-(ISI) activities including review of program (73051),
procedures (73052), observation of work activities (73753), data-review and evaluation (73755), and inspection of modification to the cafety injection system (SI) (37700).
.Results:
Of the areas inspected, no violations or deviations were identified.
During the course of the inspection, the following were noted:
Based on the areas reviewed, the_ licensee app?ars to have an effective ISI program.
The licensee contractu for some ISI services and performs ISI activities to ASME Section XI requirements, utilizing state of the art ISI equipment and procedures.
- This was the second outage, first period, of the third ten
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year. plan.
The 1986 ASME Section XI Code is the applicable Code requirement.
However, the licensee does not have a documented repair and replacement program as required by IWA-4130 of the 1986. Code.
The licensee has submitted a relief request to the Office of Nuclear Reactor Regulation (NRR) requesting an extension to comply with this-requirement of the Code.
9205210120 920515
"DR ADOCK 05000266
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Inspection Summary
The Unit 1 steam generators were replaced in 1984.
I.fter
eight operating cycles, eight steam generator tubes have
.been plugged.
The licensee's operational and maintenance program and new steam generator design has been successful in reducing.the degradation of steam generator tubes.
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DETAILS 1.
Persons Contacted Wisconsin Electric Power Company (WEPCo)
- J.
Reisenbliethler, Superintendent of Operations
- J.
Becka, Manager, Regulatory Services
- G.
Sherwood, ISI Engineer Supervisor
- K.
Crowley, ISI Engineer Supervisor
- C.
Prothero, ISI Engineer Supervisor
- F.
Fleutje, Regulatory Administrativ,e Specialist J. Michaelson, Quality Assurance Supervisor Hartford Steam Boiler Enaineerina and Insurance Company (HSB)
,
J.
Gault, ANII U.
S. Nuclear ReaulatoIV Commission (NRC)
- J.
Gadzala, Resident Inspector
- Denotes those attending the exit meeting on May 7, 1992.
Othar licensee and contractor personnel were contacted during the course of this inspection.
2.
Licensee Action on Previous Inspection Findinas (92701)
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(Open) Unresolved Item (266/ 91009-01(DRS) ; 301/91009-01(DRS)):
The licensee's repair and replacement program does not comply to ASME Section XI 1986 Edition, which requires a formally.4ocumented program which meets the requirements described in IWX 4000 and IWX 7000.
The licensee submitted a letter to NRC concerning this deviation on March 26, 1991.
The NRC is currently reviewing the Third and the stated deviation, and will inform the Ten Year P
- t licensee of the results of this review.
The licensee's current repair and replacement program complies with the ASME Code Section XI, 1977 Edition, Summer 1979 Addenda, L
which was the previous code commitment.
The licensee is
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currently preparing a program which complies with the 1986 Code requiremec and has committed'to implement it by February 28, 1993.
This will remain an unresolved item pending NRC review of the updated repair and replacement program.
3.
Inservice Inspection Review of Plan (73051)
a.
.The NRC inspector reviewed the third ten-year Inservice Inspection (ISI) Plan for the first period, second outage.
The ISI Plan conforms to the requirements of
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the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code,Section XI, 1986 Edition.
Relief requests in accordance with 10 CFR 50. 55a (G) ( 5) (IV) had been applied for by the licensee.
NRC~ review of ISI examinations that the licensee was unable to perform is currently in progress.
The services of an Authorized Nuclear Inservice Inspector (ANII) were procured and t ISI procedures and personnel certifications have been reviewed by the ANII.
The licensee contracted EBASCO Services, Inc. and Professional Welding Associates to assist the WEPCo Quality Assurance Department in performing the ISI.
Westinghouse Electric Company (W) was contracted to perform eddy current examination (ET) of steam generator tubing.
b.
ISI Documentation Review (73755)
The NRC inspector reviewed documents relating to the following:
NDE procedures utilized for ISI.
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NDE personnel certifications in accordance with
,
SNT-TC-1A.
NDE equipment calibration and examination reports.
- Ultrasonic instruments, calibration blocks,
transducers, and ultrasonic examination couplant certifications.
Liquid penetrant material certifications.
- ET examination reports.
- ET-data analysis guidelines.
- No violations or deviations were identified.
c.
Observation of Work Activities (73753)
The NRC inspector obse >;** the following work activities in progress:
ET examination of steam genc.'ator (SG) tubes.
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Ultrasonic examination (UT) of feedwater piping
and safety injection (SI) piping welds; UT calibration setup for reactor coolant loop piping velds.
-Magnetic particle exataination of main steam welds.
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Liquid-pet t examination of SI piping welds.
- Radiography
- Visual examination of reactor vessel upper weld
internals and fitup examination of SI piping welds.
Work activities were performed-in accordance with approved procedures, utilizing calibrated NDE equipment, and certitled personnel.
Detection and
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ovaluat.icn of flaws detected by NDE procedures were
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completed in accordance with ASME Code and regulatory requirements.
No violations or deviations were identified.
4.
Eddy Current Examination of Unit 1 Steam Generator Tuhgg (73753, 73755)
a.
General The licensee employed H to perform ET of the steam generator- (SG) tubes as required by the Point Beach Technical Specifications (TS).
H utilized the MIZ digital multifrequency acquisition and analyzer system
.to conduct-the examinations.
Inspection of the SG tubes included:
Full-length inspection of 591 "A" SG tubes and 592
"B" SG tubes (random).
Hot. leg to tube support plate number one:
"A"
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SG - 62. tubes;
"B" SG - 90 tubes (SG tubesheet
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periphery).
Hot leg
"U" bends:
"A" SG 54 tubes and
"B" SG 54
tubes (Rows 1, 2, and 3).
Inspection-of the
"A" SG tubes detected five manufacturing burnish marks (MBMs) in the hot leg and two in the cold leg.
Three multiple manufacturing burnish marks were found in the hot leg and one in the cold leg.
One tubesheet anomaly and one.20-29%
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indication in the anti-vibration bar (AVB) region was detected.
No defective tubes were found.
The
"B" SG tube inspection detected three MBMs in the hot leg and one in the cold leg.
One 20-29% indication
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was found in the AVB region with no defective tubes detected, b.
Insnection The NRC inspector observed the ET of the SG tubes in progress, verified calibration / certification of ET equipment and calibration standards, and reviewed the examiners / analyst qualification certifications.
The NRC inspector also reviewed the ET Data Analyst Guidelines for the Unit 1 SGs and observed the analyst's evaluations of indications in progress.
The licensee's ET program and tube degradation preventive maintenance program appear to be conservative in assuring the safe operation of the SGs for Unit 1.
No violations or deviations were identified.
l S.
Fabrication and Installation of Safety Iniection Full Flow Test Line for Unit 1 (37700)
The NRC inspector observed fabrication and installation of portions of the safety injection full flow test line.
The NRC inspector observed fitup of piping prior to welding of two joints, reviewed welding procedures and observed welding in progress.
Independent review of radiographs for ten weld joints and observation of three preservice examinations (UT)
of piping weld joints was performed by the NRC inspector.
Through observations of fitup, welding, and radiographs, the NRC inspector concluded that the licensee's procedures were adequate and implemented by qualified personnel.
The NDE contractor performing the weld radiography, demonstrated good work practices and produced quality radiographs.
No violations or deviations were identified.
7.
Erosion / Corrosion (E/C) Monitorina Activities (73052, 73753, 737551 The licensee's erosion / corrosion program was developed and initiated by the licensee's engineering staff in response to industry and safety concerns.
The current E/C program appears to be conservatively implemented and based on good engineering principles.
The licensee is currently revising
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the program to adopt the EPRI Chec NDE program.
Further training of the responsible engineering staff on use of the EPRI Chec/Checmate programs is planned in the near future.
The licensee's current program has been successful in identifying E/C in components and corrective nieasures have been taken to repair or replace these components.
The licensee's action to adopt the EPRI programs is a conservative action to assure that E/C in components and piping is identified and corrected.
No violations or deviations were identified.
8.
Unresolved Items Unresolved items are matters about which more information is required in order'to ar.certain whether they are acceptable items, open items, deviations, or violations.
An unresolved item disclosed during this inspection is discussed in Paragraph 2.
8.
Exit Meeting The_NRC inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on May 7, 1992.
The inspector summarized the purpose and findings of the inspection.
The licensee representatives acknowledged this information.
The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed during the inspection.
The licensee representatives did not identify any such documents or processes as proprietary, i
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