IR 05000306/1978021
| ML19284A464 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/09/1979 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19284A461 | List: |
| References | |
| 50-306-78-21, NUDOCS 7903060508 | |
| Download: ML19284A464 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND Ehf0RCEME"T
REGION III
Report No. 50-306/78-21 Docke t No. 50-306 License No. DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 35401 Facility Name: Prairie Island Nuclear Generating Plant Inspection At: Prairie Island, Site Unit 2 Red Wing, Minnesota Inspection Conducted: Novembe-r 28, 29, December 5, ana 6, 1978 llll..o.
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Inspector: f,K. D. Ward
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Approved By: D. H. Danielson,' Chief r !'f !7 7 Engineering Support Section 2 Ins _pec t ion Summary Inspe_ction on November 28, 29, December 5 and 6, 1978 (Report No.
50-306/78-21)
Areas Jaspected: QA/QC programs implementing procedures, observa-tion of inservice inspection (ISI) work activities, review and evaluate data and nondestructive examination (NDE) data and reports.
This inspection involved 26 onsite inspection hours by one NRC inspector.
Results: Of the three areas inspected, no apparent items of noncom-pliance were identified in two areas; one apparent item of noncom-pliance was identified in one area - (deficiency - f ilure to follow procedure).
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DETAILS Persons Contacted Northern States Power Company (NSP)
- F.
P. Tierney, Plant Manager
- E. Watzl, Plant Sc,erintendent, Engineering and Ra,liation
- D.
B. Hansen, Engineer
- A.
A. Humstad, Staff Engineer Hartford Steam Boiler Engineering and Insurance Company C. Landstrom, Authorized Nuclear Inservice Inspector (ASII)
Lambert, MacGill, Thomas, Inc. (LMT)
J. E. Hill, Field Supervisar The inspector also contacted and interviewed other licensee and con-tractor employees.
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findiqis (Closed) Unresolved Item (306/77-25-01):
Calibrated channel.
The Reactor Vessel UT Procedure No. ISI-152, Revision 5 was revised with instructions relative to the site failure of a previously calibrated channel (pulser amplifiers, etc.).
(Closed) Unresolved Item (306/77-25-02):
Certification of training.
The W mechanical and electronic technicians responsible for the site maintenance of the W automated inspection tool, had certifications of this training available at the site.
(Closed) Unresolved Item (306/77-25-03): Visual inspection. The visual inspection procedure No. NSP-VT-1, Revision I was revised and is now clear in the area of personnel qualification.
(Closed) Unresolved Item (306/77-25-04): Tightness of all bolting.
The visual inspection procedure No. SNP-VT-1, Revision 0 was revised in the area of tightness of bolting stating how the bolting shall be manually verified.
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Functional or Program Areas Inspected 1.
Inservice Inspection-General Information a.
The first inspection interval for Prairie Island, Unit 2, commenced on December 21, 1974, with the start of com-mercial operation, and ends on December 21, 1984.
The dates for the first three periods that occur during the first inspection interval are listed below:
Period 1 - December 21, 1974 to April 21, 1978 Period 2 - April 21, 1978 to August 21, 1981 Period 3 - August 21, 1981 to December 21, 1984 There were two refueling outages during the first period and three are planned in each of the remaining two periods this is the final outage of the second period.
b.
Lambert, MacGill. Thomas, Inc. developed and performed the inservice inspection program in accordance with ASME Section XI, 1974 Edition, Summer 1975 Addenda.
2.
Review of Programs 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 as specified by the Prairie Island Technical Specifications Technical Specification 4.2-4 and other NRR requirements are in accordan'e with ASME Section XI, 1974 Edition, Summer 1975 Addenda.
It was determined that the program adequately addresses the scope of work to be accomplished during this outage.
The LMT Operating and Quality Assurance Manual, Revision 10, March 9, 1978, was reviewed and found that procedure No. QA-6, Revision 6, " Qualification and Certification of NDE Personnel,"
March 6, 1978, did not state that for NDE Level III, personnel, a composite grade of 90% is required to pass the test.
This is an item of noncompliance identified in Appendix A.
NSP and LMT assured the inspector that the procedure would be revised stating the composite grade of 90%.
(306/78-21-01)
Except as noted, no items of noncompliance or deviations were identified.
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3.
Review of Procedures The folicwing LMT procedures that are applicable to this activity were reviewed.
NSP-VT-1, Revision 1, March 27,
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Visual Examination, No.
a.
1978.
Visual Examination of Assembled Hanger Assemblies, No.
b.
NSP-VT-2, Revision 1, September 18, 1978.
Liquid Penetrant Examination, No. NSP-PT-1, Revision 1, c.
September 8, 1977.
Magnetic Particle Examination Yoke Method No. NSP-MT-1, d.
Revision 1, September 8, 1977.
No. NSP-UT-1, Ultrasonic Examination of Pipe Welds, c.
Revision 0, Fbrch 18,1977.
Automatic Data Recording, No. NSP-UT-2, Revision 0, f.
March 18, 1977.
Ultrasonic Examination of Ferritic Vessels with Wall Thickness 2.5" and greater, No. NSP-UT-3, Revision 0, g.
March 18, 1977.
Ultrasonic Examination of Studs and Bolts No. NSP-UT-4, h.
Revision 0, March 18, 1977.
No items of noncompliance or deviations were identified within the areas reviewed.
Observation of Work and Work Activities 4.
inspector observed and had discussions with LMT per-a.
The These observations included sonnel during the NDE.
calibrations, preparation of the weld, performance of the examination and the documentation, Ultrasonic (UT) examinatior was observed being performed b.
on the reactor vessel, safety injection low head loop A welds, main steam relief header welds and the steam generator tube sheet to head welds.
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There was magnetic particle examination (MT) performed on
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c.
reactor vessel studs, liquid penetrant examination performed on socket welds, welded hangers, lugs, plate and pressurizer surge line safeend reducers. There were also visual exami-nations (VT) performed on various welds, bolts, studs and hangers.
No items of noncompliance or deviations were identified within the areas reviewed.
5.
Data Review and Evaluations Review of the data reports demonstrated that the Prairie Island QA/QC and technical requirements were met.
The required infor-mation was available for UT, PT, MT, and VT.
No items of noncompliance or deviations were identified in the documents reviewed.
6.
Material and Equipment Certification The inspector examined and verified the adequacy of calibration and certification, documents relative to the following items.
a.
UT Couplant - LMT - Gel Batch No. 8782.
b.
Magnaflux materials - Penetrant, Batch No. 7A004
- Developer, Batch No. 6K069
- Cleaner, Batch No. 6K024 c.
Nortec 130D, 131D, and Sonic FTS MKl.
d.
UT recorders, Sanborn 320, and Gulton TR-722J.
Magnaflux, Yoke, Parker Probe Y-6.
e.
f.
UT Calibration blocks.
Various UT transducers, Aerotech, Automation, Industry, g.
Harrisonic, etc.
No items of noncompliance or deviations were identified.
7.
NDE Personnel Qualifications The inspector reviewed the following LMT qualifications in accordance with SNT-TC-1.,1975 Edition.
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s Level Method Name UT-PT-MT-ET-RT III T. G. 'ambert
UT-PT-MT-ET J. E. nill II UT-PT W. J. Murray II UT-ET K. M. King Il PT V. R. March I
UT V. R. March I
UT B. K. Graham II UT S. M. Carroll the inspector In reviewing the above personnel qualifications, found that B. K. Graham and V. R. March did not have their NDE experience documented and was performing UT as of November 29, identified This is an item of noncompliance as 1978 on site.
in Appendix A.
(306/78-21-01)
Except as noted, no items of non compliance or deviations were identified.
Exit Interview The inspector met with site representatives (denoted in the Persons the conclusion of the inspection and summarized the Contacted) at The licensee acknowledged the scope and findings of the inspection.
information.
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