ML20058F290
| ML20058F290 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/02/1993 |
| From: | Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Antony D NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20058F293 | List: |
| References | |
| GL-89-10, NUDOCS 9312080062 | |
| Download: ML20058F290 (2) | |
See also: IR 05000282/1993012
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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799 ROOSEVELT ROAD
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GLEN ELLYN. ILLINOIS 60137-5927
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DEC C
1993
Docket No. 50-282
Docket No. 50-306
Northern States Power Company
ATIN: Mr. D. D. Antony
Vice President, Nuclear
Generation
414 Nicollet Mall
Minneapolis, MN 55401
Dear Mr. Antony:
This letter refers to the Generic Letter 89-10 motor operated valve inspection
conducted by Ms. C. A. Gainty and others of this office on September 27 through
November 15, 1993. The inspection included a review of activities authorized for
your Prairie Island Nuclear Generating Station.
At the conclusion of the
inspection, the findings were discussed with those members of your staff
identified in the enclosed report.
The enclosed copy of our inspection report identifies areas examined during the
inspection. These areas consisted primarily of a review of the implementation
of the Prairie Island Motor Operated Valve Program established in response to
Within this area, the inspection consisted of a
selective examination of procedures and representative records, observations, and
interviews with personnel.
Based on the results of this inspection, certain of your activities appeared to
be in violation of NRC requirements, as specified in the enclosed Notice of
Violation (Notice). You are required to respond to this letter and should follow
the instructions specified in the enclosed Notice when preparing your response.
In your response, you should document the specific actions taken and any -
additional actions you plan to prevent recurrence. After reviewing your response
to this Notice, including your proposed corrective actions and the results of
future inspections, the NRC will determine whether further NRC enforcement action
is necessary to ensure compliance with NRC regulatory requirements.
Considerable progress was noted in your GL 89-10 program; however, weaknesses
were identified in the areas of test control and technical evaluation (Sections
2.2.2, 2.3, and 2.4.2) .
Management attention in these areas is essential to
ensure program effectiveness.
Concerns were also 4dentified with your analysis to determine which MOVs were
considered susceptible to pressure locking. For example, your analysis concluded
that the sump B valves were not susceptible; however, we presented two scenarios
by which we feel pressure locking is possible.
This item is considered an
inspection followup item and is discussed in Section 2.7.2 of the enclosed
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inspection report. You have indicated your intention to evaluate the scenarios
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and take appropriate action.
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93120B0062 931202
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ADOCK 05000282
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DEC 2
1993
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Northern States Power Company
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You are requested to respond and address each of the inspection followup items
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identified within 60 days of your receipt of this inspection report. Include in
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your response: (1) the schedule and details for any planned corrective actions
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regarding motor brakes, Limitorque's Part 21 report on elevated temperature
effects, and pressure locking; and (2) your assessment of the potential for
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pressure locking for the MOVs identified.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this
letter, its enclosures, and your response to this letter will be placed in the
NRC Public Document Room.
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The responses directed by this letter and the accompanying Notice are not subject
to the clearance procedures of the Office of Management and Budget as required
by the Paperwork Reduction Act of 1980, PL 96-511.
We will gladly discuss any questions you have concerning this inspection.
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Sincerely,
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/ G. C. Wright, Chief
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Engineering Branch
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Enclosures:
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2.
Inspection Reports
No. 50-282/93012(DRS);
No. 50-306/93012(DRS)
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3. Prairie Island Gate and
Globe Valve Data
cc w/ enclosures:
E. L. Watzl, Site Manager,
Prairie Island Site
M. Wadley, Plant Manager
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Resident Inspector, RIII
Prairie Island
Resident Inspector, RIII
Monticello
John _W. Ferman, Ph.D.,
Nuclear Engineer, MPCA
State Liai~on Officer, MN
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Prairie Island LPM, NRR
T. Scarbrough, NRR
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P. Eapen, RI
F. Jape, RII
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T. Westerman, RIV
P. Narbut, RV
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M. Holbrook, INEL.
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