ML20058F236
| ML20058F236 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/29/1993 |
| From: | Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Antony D NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20058F240 | List: |
| References | |
| NUDOCS 9312080040 | |
| Download: ML20058F236 (3) | |
See also: IR 05000282/1993019
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' Docket No. 50-282
Docket No. 50-306
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Northern States Power Company
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Mr. D. D. Antony
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Vice President, Nuclear
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414 Nicollet Mall
Minneapolis, MN 55401
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Dear Mr. Antony:
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This refers to the routine safety inspection conducted by Messrs. M. Dapas,
R. Bywater, C. Orsini, and W. Stearns of this office from September 14 through
November 8,1993, of activities at the Prairie Island Nuclear Generating
Plant, Units 1 and 2, authorized by NRC Operating Licenses No. DPR-42 and
No. DPR-60, and to the discussion of our findings with Mr. M. D. Wadley and
other members of your staff at the conclusion of the inspection.
The enclosed copy of our inspection report identifies areas examined during
the inspection.
Within these areas, the inspection consisted of a selective
examination of procedures and representative records, observations, and
interviews with personnel.
During this inspection, certain of your activities appeared to be in violation
of NRC requirements.
Specifically, you inadvertently entered a condition of
minimum defense-in-depth during the Unit 2 outage with respect to the critical
safety function of containment closure associated with your shutdown safety
assessment program.
You had several barriers in place which should have
prevented this condition.
In addition, you did not implement an adequate
design control process for the modification of steam exclusion area
boundaries; an issue which we discussed in our last inspection report.
We
continued our review of your corrective actions for steam exclusion design
control deficiencies, and considered your reconstruction of design basis
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information and evaluation of the impact of current modifications on steam
exclusion area boundaries, to be strengths. As described in the enclosed
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' inspection report, the identified violations are not being cited because the
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criteria specified in Section Vll.B.2 of the " General Statement of Policy and
Procedure for NRC Enforcement Actions," (Enforcement Policy,10 CFR Part 2,
Appendix C), were satisfied.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of
this letter and its enclosures will be placed in the NRC Public Document Room.
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
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Bruce Jorgensen, Acting Chief
Reactor Projects Branch 2
Enclosures:
Inspection Reports
No. 50-282/93019;
No. 50-306/93019(DRP)
cc w/ enclosure:
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E. L. Watzl, Site Manager,
Prairie Island Site
M. Wadley, Plant Manager
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Resident Inspector, RIII Prairie
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Resident Inspector, Rlli Monticello
John W. Ferman, Ph.D.,
Nuclear Engineer, MPCA
State Liaison Officer, State
of Minnesota
State Liaison Officer, State
of Wisconsin
Prairie Island, LPM, NRR
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We will gladly discuss any questions you have concerning this inspection.
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Bruce Jorg ns.n Acting Chief
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Enclosures:
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No. 50-282/93019;
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No. 50-306/93019(DRP)
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E. L. Watzl, Site Manager,
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Prairie Island Site
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M. Wadley, Plant Manager
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Resident Inspector, Rill Prairie
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Resident Inspector, RIII Monticello
John W. Ferman, Ph.D.,
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Nuclear Engineer, MPCA
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State Liaison Officer, State
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State liaison Officer, State
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