ML20154J970
| ML20154J970 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/09/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20154J974 | List: |
| References | |
| 50-282-98-16, 50-306-98-16, NUDOCS 9810160061 | |
| Download: ML20154J970 (3) | |
See also: IR 05000282/1998016
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October 9, 1998
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Mr. M. Wadley -
President, Nuclear Generation
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Northem States Power Company
414 Nicollet Mall
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Minneapolis, MN 55401
SUBJECT:
NRC FIRE PROTECTION FUNCTIONAL INSPECTION (FPFI)
REPORTS 50-282/98016(DRS); 50-306/98016(DRS)
Dear Mr. Wadley:
On August 28,1998, the NRC completed an inspection at your Prairie Island Nuclear
Generating Plant. The enclosed report presents the results of that inspection.
Areas examined during the inspection included the fire protection program and the results of
your recently performed Appendix R self-assessment. Within these areas, the inspection
consisted of a selective examination of procedures and representative records, observations,
and interviews with personnel.
The inspectors concluded that your fire protection self-assessment project contained acceptable
administrative controls to identify, track, and resolve issues; to review, identify, and control
commitments; and to ensure configuration management controls were appropriate. No cited
violations of NRC requirements were identified at this time. However, we were concerned that
your self-assessment actMties did not identify the significant safe shutdown deficiencies
subsequently identified by the NRC inspection team.
During this inspection period, three apparent violations of NRC requirements were identified by
the inspectors which are being considered for escalated enforcement action in accordance with
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the " General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement
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Policy), NUREG-1600. These apparent violations pertain to: 1) the failure to identify and protect
safe shutdown equipment which could be susceptible to fire damage; 2) the failure to maintain
fire wrapping for safe shutdown equipment identified by NRC approved exemptions as being
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required to assure safe shutdown in the event of a postulated fire in Fire Areas 32 and 58/73;
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and 3) the susceptibility of valves to fire-induced mechanical damage as described in
Information Notice 92-18. Although your preliminary reviews of these issues were documented
in Licensee Event Reports 1-98-10,1-98-12,1-98-14, and 1-98-15, we understand that these
issues are still being evaluated by your staff for safety significance. Accordingly, no Notice of
Violation is presently being issued for these inspection findings. In addition, please be advised
that the number and characterization of apparent violations described in the enclosed inspection
report may change as a result of further NRC review of your completed analyses of safety
significance. You will be advised, by separate correspondence, of the results of our
deliberations on this matter.
9810160061 981009
ADOCK 05000282
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M.Wadly
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During this inspection, we also identified that the fire-resistive performance of the Kaowool fire
barrier system used extensively at Prairie Island to protect safe shutdown equipment was
indeterminate. We understand that your staff has implemented and will maintain appropriate
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compensatory actions until this issue is resolved. We request that you respond within 30 days
of the date of this letter describing your project plan for addressing this issue.
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in accordance with 10 CFR 2.790 of the NRC's " Rules and Practice," a copy of this letter and its
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enclosure will be placed in the NRC Public Document Room.
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We will gladly discuss any questions you have conceming this inspection.
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Sincerely,
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John A. Grobe, Director
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Division of Reactor Safety
Docket Nos.: 50-282; 50-306
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Enclosure:
Inspection Reports 50-282/98016(DRS); 50-306/98016(DRS)
cc w/ encl:
Plant Manager, Prairie Island
State Liaison Officer, State of Minnesota
' State Liaison Officer, State of Wisconsin
Tribal Council, Prairie Island Dakota Community
Distnbution:
CAC (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/enci
J. Caldwell, Rlli w/enci
C. Pederson, Rlll w/enci
B. Clayton, Rlli w/enci
SRI Prairie Island w/ encl
DRP w/enci
TSS w/enci
DRS (2) w/enci
Rill PRR w/enci
PUBLIC IE-01 w/ enc!
Docket File w/enci
GREENS
LEO (E-Mail)
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DOCDESK (E-Mail)
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DOCUMENT NAME: G:DRS\\pra98016.wpd
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NAME
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Kunowski n AL Claytoed(M Grobe
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DATE
10/6/98-
10/4/98
10/(/98
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10/ /98
OFFICIAL RECORD COPY
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During this inspection, we also identified that the fire-resistive perform,ance of the Kaowool fire
barrier system used extensively at Prairie Island to protect safe shutdown equipment was
indeterminate. We understand that your staff has implemented and will maintain appropriate
compensatory actions until this issue is resolved. We request that you respond within 30 days
of the date of this letter describing your project plan for addressing this issue.
In accordance with 10 CFR 2.790 of the NRC's " Rules and Practice," a copy of this letter and its
enclosure will be placed in the NRC Public Document Room.
We will gladly discuss any questions you have conceming this inspection.
Sincerely,
original /s/ J. A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket Nos.: 50-282;50-306
Enclosure:
Inspection Reports 50-282/98016(DRS); 50-306/98016(DRS)
cc w/ encl:
Plant Manager, Prairie Island
State Liaison Officer, State of Minnesota
State Liaison Officer, State of Wisconsin
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Tribal Council, Prairie Island Dakota Community
Distribution:
CAC (E-Mail)
RPC (E-Mail)
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Project Mgr., NRR w/enct
1
J. Caldwell, Rill w/enci
C. Pederson, Rill w/enci
B. Clayton, Rlll w/enci
SRI Prairie Island w/encI
DRP w/ encl
TSS w/enci
DRS (2) w/ encl
Rlli PRR w/ encl
PUBLIC IE-01 w/ encl
Docket File w/enci
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
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DOCUMENT NAME: G:DRS\\pra98016.wpd
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OFFICE
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NAME
Butler:sd 4
Gardner #
Kunowski
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Clayton 4
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DATE
10/ /98
10/ /98
10/ /98
10/ /98
10/ f/98
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OFFICIAL RECORD COPY
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