ML20246K374
| ML20246K374 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/06/1989 |
| From: | Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Larson C NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20246K377 | List: |
| References | |
| NUDOCS 8905180044 | |
| Download: ML20246K374 (2) | |
See also: IR 05000282/1989014
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Docket No. 50-282
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Doc'ket No. 50-306
. Northern States Pnwer Company
ATTN: Mr. C. E. Larson
Vice President, Nuclear
Generation
414 Nicollet Mall
Minneapolis, MN 55401
Gentlemen:
'This refers to the routine safety inspection conducted by Mr. F. A. Maura of
this office on April 17-21, and 27,-1989, of activities dealing with the
containment integrated leak rate test, and containment penetration leak rate
testing at 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. E. Watz1 at the conclusion of the inspection.
The enciosed 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, as specified in the enclosed Notice. The violation is
the resolution of a previously identified Unresolved Item identified in
Inspection Report No. 50-282/83016. A written response is rer,uired. Two
additional violations regarding lack of drawing control and incorrect valve
status positicn indication were identified for which immediate corrective
actions were implemented.
Since these were violations that would be
categorized as Severity Level V and appropriate corrective actions were
initiated prior to the end of the inspection, no Notice of Violation is
being issued in accordance with the criteria of 10 CFR Part 2, Appendix C,
Section V.A.
We also request that you respond to the Open Item identified in Paragraph 6.b.
(maintaining penetration test pressure at P , or P , during local leak rate
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testing) of the attached Inspection Report
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of
this letter, the enclosures, and your response to this letter will be placed
in the NRC Public Document Room.
The responses directed by this letter and the accompanying Notice are not
subject to the clearance procedures of the Office of Management and Budget
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as required by the Paperwork Reduction Act of 1980, PL 96-511.
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8905180044 890506
DR
ADOCK CSOO
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- Ncrthern States Power Company
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. We will gladly discuss any questions you have concerning this inspection.
Sincerely,
OR!ClijAL S! cried BY CE?IER C. C"~"~
G. C. Wright, Chief
Operations Branch
Enclosures:
1.
2.
Inspection Reports
No. 50-282/89014(DRS);
No. 50-306/89015(DRS)
cc w/ enclosures:
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
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