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Forwards Enforcement Conference Insp Repts 50-282/89-19 & 50-306/89-19 on 890608.Violations Discussed
	ML20246E387
Person / Time
Site:	Prairie Island
Issue date:	07/06/1989
From:	Miller H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Larson C; NORTHERN STATES POWER CO.
Shared Package
ML20246E390	List: IR 05000282/1989019; ML20246E387;
References
	EA-89-135, NUDOCS 8907120217
	Download: ML20246E387 (3)
	v • d • e

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: Docket No. 50-282
Docket No. 50-306
EA 89-135
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Northern States Power Company
ATTN: Mr. C. E. Larson
Vice President,-Nuclear
Generation
414 Nicollet Mall
Minneapolis, MN 55401
Gentlemen:
This confirms'our plans as discussed between Mr. Bruce Burgess of this office
and Mr. K. Beadell of your staff on June 29, 1989, to conduct an Enforcement
Conference at 10:00 a.m. on Thursday, July 13, 1989, at the Region III Office
in Glen'Ellyn, Illinois. The purpose of.the Enforcement Conference is to
discuss the apparent violations concerning inadequate dedication of. commercial-
grade material installed in safety related applications.
This letter also refers.to the meeting held on June 8, 1989, at the Region III
Office between Mr. K. M. Beadell and others of your staff and Mr. W. L. Axelson.
and members of this office in regard to the activities you had taken to resolve
the use of several components which were purchased as commercial grade and
subsequently installed in safety related applications at your Prairie Island
Nuclear Power Plant. This meeting was held as a result of the findings
identified in the Vendor Branch Inspection Report Nos. 50-282/88200,
50-306/88200.
The enclosed copy of our report of.this meeting identifies those matters
discussed during the meeting.
At the Enforcement Conference, you should be prepared to discuss the
following topics:
1. What controls have been established to ensure that components installed
in safety related applications conform with the requirements of Appendix B
to 10 CFR Part 50, whether purchased as safety related or commercial grade.
2. What actions you have taken to ensure that the components purchased as
commercial grade and identified on pages 4-6 of the above Vendor Branch
Inspection Report conform with the requirements of 10 CFR Part 50,
Appendix B, for utilization in safety related applications. You should
also be prepared to discuss when these actions were taken, and the final
determinations made for those items which were still " indeterminate" at

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                         the time of our June 8, 1989, meeting.
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           Northern States Power Company               2                   'JUL    61989
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           3.     For the equipment which was determined to have been unsuitable or                           I
                  indeterminate as of our June 8, 1989, meeting (items b, c, d, f, g, h, i,                   I
                  and j as described on pages 4-6 of the Vendor Branch Inspection Report),
                  what would have been the effect on the associated system's safety functions
                  if the component should fail during required use.
           In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of                         1
           this letter and the enclosures will be placed in the NRC Public Document Room.                     l
           We will gladly discuss any questions you have concerning this meeting.                            I
                                                      Sincerely,                                             i
                                                                                                             I
                                                                                    L        '
                                                      ORIGlDL SIGC US "
                                                      Hubert J. Miller, Director
                                                      Division of Reactor Safety
           Enclosure: Meeting Reports                                                                         l
              No. 50-282/89019(DRS);
                                                                                                              ]
              No. 50-306/89019(DRS)                                                                           1
           cc w/ enclosure:
           E. L. Watzl, Plant Manager
           DCD/DCB (RIDS)
           Licensing Fee Management Branch
           Resident Inspector, RIII Prairie
              Island
           Resident Inspector, RIII Monticello
           John W. Ferman, Ph.D.,
              Nuclear Engineer, MPCA
           State Liaison Officer, State
              of Minnesota
           W. Brach, VIB, NRR
           U. Potapovs, VIB, NRR
           R. McIntyre, VIB, NRR

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                                                                                            ~ NOTICE OF SIGNIFICANT LICENSEE MEETING
                          Name cf Licensce: Northern States. Power Company
                         ;Name.cf Facility: Prairie Island Nuclear Generating Plant
                                                                                         ~
                          Docket No: 50-282; 50-306

j ;Date and Timeiof Meeting: Thursday, July 13, 1989 at 10:00 P.M. (CST)

                        . Location of Meeting:
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                                                                                               U.S. Nuclear Regulatory Commission    .
                                                                                               Region III Office
                                                                                               799 Roosevelt Road
                                                                                               Glen Ellyn, Illinios 60137
                          Purpose of Meeting:
                                   '
                                                                                               Enforcement Conference to discuss the apparent
                                                                                               violations concerning inadequate dedication of
                                                                                                                                                                     ,

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                                                                                               commercial grade _ material installed in safety related
                                                                                              applications.
                         R'III Attendees:
                       cA.)B. Davis,l Regional Administrator
                       E. J. Miller, Director, Division of Reactor Safety
                       -M. J. Phillips, Chief, Operational Programs Section
                       'Others'as designated by Region III
                                                                                                                                                       sMEP-n.sep
                                                                                                                                           ~
                         Licensee Attendees:                                                                       "
                        ,L. Eliason, General Manager Nuclear Plants
                         E. Watzl',. Plant Manager, Prairie Island.
                         D. Hendele. General Superintendent, Plant Engineering.and Radiation Protection
                         D.-Beadell,' Superintendent. Technical Engineering'
                         Others as designated by the Licensee
                         NOTE:                                         Attendance at this meeting.by NRC personnel should be made known !:s
                                                                      .B. L. Burgess via telephone call (FTS 388-5698) by COB July 10, 7389,
                         Dis'tribution:
                         J. M. Taylor, Deputy Executive Director for Nuclear Reactor Regulation,
                           Regional Operations, and Research
                         F. J. Miraglia, Associate Director for Inspection and Technical Assessment
                                       ..
                         B.;K. Grimes, Director, Division of Reactor Inspection and Safeguards, NRR
                         J. G. Partlow, Associate Director for Projects, NRR
                      - G. M. Holahan, Acting Director, Division of Reactor Projects III/IV/V, NRR
                        M..J. Virgilio, Acting Assistant Director for Regions III and V NRR
                                                                                                          ~
                        J. W. Clifford, RIII Coordinator, ED0-
                        G. C. Wright, Chief, Operations Branch, DRS, RIII
                        R. W. Cooper, Chief Engineering Branch, DRS4 RIII
                        L. R._Greger, Chief, Reactor Programs Branch, DRSS, RIII
                        B. S..Mallett, Chief, Nuclear Materials Safety Branch, DRSS, RIII
                        L. Yandell, Acting Director, Directorate III-1, NRR
                      .D. Dilanni, Licensing Project Manager, NRR

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ML20246E387

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