IR 05000409/1978013
| ML20062G184 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/16/1978 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20062G171 | List: |
| References | |
| 50-409-78-13, NUDOCS 7812270078 | |
| Download: ML20062G184 (5) | |
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U.S. NUCLEAR REGL*LATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-409/78-13 Docket No. 50-409 License No. DPR-45
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Licensee: Dairyl'und Power Cooperative 2615 East Avenue - South La Crosse, WI 54601 Facility Name: La Crosse Boiling Water Reactor Inspection At: La Crosse Boiling Water Reactor Site, Genoa, WI
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Inspection Conducted: October 23 and 24, 1978 Mlhwat. b Inspector:
K. D. Ward
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Approved By:
D. H. Danielson, Chief
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Engineering Support Section 2 Inspection Summary Inspection on October 23 and 24,1978 (Report No. 50-409/78-13)
Areas Inspected: Inservice inspection (ISI) QA/QC programs, implementing procedures, data review and evaluation. The inspection involved a total of 11 onsite inspection hours by one NRC inspector.
I Results: No items of concompliance or deviations were identified.
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DETAILS Persons Contacted Dairyland Power Cooperative J. Parkyn, Assistant Superintendent
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- Denotes those pr'esent at the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (50-409/77-10, paragraph 1.a) - Inservice inspec-tion program. The licensee's response, dated July 13, 1977, was evaluated and the implementation of the corrective action was examined. Region III requested headquarters assistance in obtaining an NRR position relative to the Code, ASMI Section XI, 1971 Edition with no Addenda and the LACBWR Technical Specification, Table 5.3-1.
The Assistant Director, Technical Programs, Division of Reactor Operations Inspection.
IE response., dated October 31, 1977, was reviewed and the implementation of the specified corrective action was examined at the site. Results of the examination showed that the Dairyland Power Cooperative is in the process of completing the amendment to their technical specifications with an updated ISI program, including valve and pump testing. This will be co=pleted six months prior to the next 40-month period which begins November 1, 1979 per 50.55a(g).
(Closed) Unresolved Item (50-409/77-10, paragraph 1.b) - Inservice inspection reports. The Authorized Inspector was present during the inservice inspection reviewing ISI reports. The QA Supervisor performed an audit and reviewed all the reports. Also, measures have been estab-lished to have all ISI reports reviewed by the licensee or the Authorized Inspector.
Functional or Program Areas Inspected 1.
Inservice Inspection - General Information C uthwest Research Institute (SWRI) developed and performed the inservice inspection program in accordance with ASME Section XI, 1974 Edition, Sum =er 1975 Addenda.
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Review of Program The inspector established through review and discussion with the licensee representatives that the program requirements for inservice inspection of the reactor' pressure vessel piping weldments and associated systems were in accordance with ASME Section XI, 1974 Edition, Summer 1975 Addenda.
It was determined that the program adequately addresses the scope of work to be accomplishda during this outage.
The SWRI Nuclear Quality Assurance Program Manual No. 96 provided the implementation of QA/QC measures responsive to NRC requirements.
No items of noncompliance or deviations were identified within the areas reviewed.
3.
Review of Procedures The following procedures that are applicable to this activity were reviewed, Special Process Control No. NQAP 11-1, Revision 1, March 1977, a.
NDE Personnel Certification, Written Practice in Accordance With SNT-TC-1A, 1975 Edition.
b.
Weld Joint Identification Marking on Nuclear Power Plant Piping, No. 1X-FE-103-1 February 1977.
Measuring and Recording Search Unit Location and Maximura Signal c.
Amplitude Data During Ultrasonic Weld Examination, No. 1X-FE-104-1, August 1976.
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Onsite NDT Records Control No. X-FE-101-0, March 1976.
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Control of Nuclear Inspection Equipment, No. XIII-AG-101-0, June 1977.
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Liquid Penetrant Examination Color Contrast Method, No.
SWRI-NDT-200-1, Revision 42, July 1978.
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Test and Inspection Equipment Control, No. NQAP,10-1, Revision 1, March 1977.
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Control of Critical Services, Items and Equipment, No. NQAP, 12-1, Revision 1, March 1977.
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Manual Ultrasonic Examination of Pressure Piping Welds, No.
SVRI-NDT-600-3, Revision 46, June 1978.
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Manual Ultrasonic Examination of Pressure Vessel Welds, No.
SWRI-NDT-600-15, Revision 37,.'aly 1978.
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Manual Ultrasonic Examination of LACBWR Nozzle Inside Radius Sections From Vessel Base Material, No. SWRI-NDT-800-59 Revision 0, October 1978.
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Visual Examination'b'Y Nuclear Reactor Co=ponents by Direct or
Remote Viewing, No. SWRI-NDT-900-1, Revision 42, July 1978.
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Audits, NQAP, 15-1, Revision 1, March 1977.
No items of noncompliance or deviations were identified within the procedures reviewed.
4.
Data Review and Evaluations Review of the data files for the following systems demonstrated that the QA/QC and technical requirements were met.
The specified information was available for ultrasonic (UT), liquid penetrant (PT), and visual (VT) examinations performed.
a.
Reactor Pressure Vessel weldments b.
Main Steam c.
Upper Liquid Les21 Penetrant Piping e.
Experimental Access Penetration at 45 Piping No items of noncompliance or deviations were identified in the data reviewed.
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Material and Equipment
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The inspector examined and verified the adequacy of the ultrasonic calibration standards, preparation of weldments and certification documents relative to the following items.
a.
Ultrasonic Couplant - batch No. TB-12137-2 b.
Liquid Penetrant Materials - batch No. 7H113 Penetrant.
No. 7H140 Developer, and No. 7J070 Cleaner-4-
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Various calibration blocks and transducers
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No items of noncompliance or deviations were identified above.
6.
NDE Personnel Qualifications The inspector reviewed the following Southwest Research Institute Personnel qualffications in accordance with SNT-TC-1A.
Name Nethod Level Yr. Code L.Vilka VT-PT II
L. Villa MT I
L. Villa UT II
L. Villa ET I
S. Todd VT I LTD
S. Todd UT-MT-PT I
M. Littfin PT-MT I
M. Littfin VT-RT I LTD
M. Littfin UT II
J. Lehman PT-VT-UT-MT I LTD
G. Hendrix VT-UT-MT-PT II
M. Ehnstrom UT-PT-MT I
M. Ehnstrom VT I LTD
No items of noncompliance or deviations were identified above.
Exit Interview The inspector met with Mr. Towsley, the site representative at the con-clusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report.
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