ML20135E339
| ML20135E339 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/27/1997 |
| From: | Caldwell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Patulski S WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20135E342 | List: |
| References | |
| NUDOCS 9703060440 | |
| Download: ML20135E339 (4) | |
See also: IR 05000266/1996019
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February 27, 1997
Mr. S. A. Patuiski, Bite Vice President
Point Beach Nuclear Plant
6610 Nuclear Road
Two Rivers, Wisconsin 54241
SUBJECT:
POINT BEACH NRC INSPECTION REPORT NO. 50-266/96019,
50-301/96019, 72-005/96019 AND NOTICE OF VIOLATION
Dear Mr. Patuiski:
On January 27,1997, the NRC completed an inspection at your Point Beach 1 and 2
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reactor facilities. The enclosed report presents the results of that inspection.
During the six week period covered by this inspection, we noted improved material
preservation of equipment in the primary auxiliary building and better questioning attitude
and identification of deficiencies by engineering personnel. However, we also identified
three violations of NRC requirements.
For Violation 1.A, although you identified the auxiliary operator's failure to correctly
position the residual heat removal (RHR) valve and you conducted an extensive
investigation of the event, the corrective actions for the auxiliary feedwater system valve
mispositioning that was the subject of recent esca!ated enforcement should have
prevented this RHR valve mispositioning.
Regarding Violation 1.B, we acknowledge that your condition reporting system has
significantly improved in the past several months, but the two examples where condition
reports should have been written but were not highlight the need for continued
management emphasis on this important problem identification program.
Violations 2 and 3 were of concern as examples of inadequacies in enst. ring that
equipment and systems are tested at their required frequency including technical
specification required surveillances
These violations are cited in the enc!; od Notice of Violation, and the circumstances
surrounding the violations are described in detailin the enclosed report. Please note that
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, please address what
you will be doing to ensure that corrective actions taken for the RHR valve mispositioning
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and the two failures to write a condition report will be more effective than actions taken
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for previous valve configuration control and condition reporting system problems. The
NRC will use your response, in part, to determine whether further enforcement action is
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necessary to ensure compliance with regulatory requirements.
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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,
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the enclosures, and your response to the letter will be placed in the NRC Public Document
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Room (PDR).
Sincerely,
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/s/ John A. Grobe for
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James L. Caldwell, Director
Division of Reacto. Projects
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Docket Nor..: 50-266, 50-301,72-005
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Enclosures-
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2. Inspection Report No. 50-266/96019(DRP);
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50-301/96019(DRP): 72-005/96019(DRP)
cc w/ encl:
R. R. Grigg, President and Chiai
Operating Officer, WEPCO
A. J. Cayia, Plant Manager
Virgil Kanable, Chief,
Boiler Section
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Cheryl L. Parrino, Chairman
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Wisconsin Public Service
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Commission
State Liaison Officer
Docket File w/ encl
SRI Point Beach w/enci
PUBLIC IE-01 w/ encl
OC/LFDCB w/ encl
A. B. Beach, w/enci
Rll! Enf. Coordinator, w/ encl
W. L. Axelson, w/enct
CAA1 w/enci (E-mail)
Project Manager, NRR, w/ encl
DRP, w/enci
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Rill PRR w/enci
DRS (3) w/ encl
TSS w/ encl
Document: R:\\lnspr pts \\ powers \\poin\\ptb96019.drp
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Tc receive a copy of this document, Indicate in the box "C" = Copy without attach /enci
"E" = Copy with attachtenci "N" = No copy
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February 27, 1997
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Mr. S. A. Patuiski, Site Vice President
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Point Beach Nuclear Plant
6610 Nuclear Road
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Two Rivers, Wisconsin 54241
SUBJECT:
POINT BEACH NRC INSPECTION REPORT NO. 50-266/96019,
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50-301/96019,72-005/96019 AND NOTICE OF VIOLATION
1
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Dear Mr. Patulski:
l
On January 27,1997, the NRC completed an inspection at your Point Beach 1 and 2
reactor facilities. The enclosed report presents the results of that inspection.
!
l
During the six-week period covered by this inspection, we noted improved material
i
preservation of equipment in the primary auxiliary building and better questioning attitude
i
and identification of deficiencies by engineering personnel. However, we also identified
three violations of NRC requirements.
For Violation 1.A, although you identified the auxiliary operator's failure to correctly
position the residual heat removal (RHR) valve and you conducted an extensive
investigation of the event, the corrective actions for the auxiliary feedwater system valve
mispositioning that was the subject of recent escalated enforcement should have
prevented this RHR valve mispositioning.
,
Regarding Violation 1.B, we acknowledge that your condition reporting system has
significantly improved in the past several months, but the two examples where condition
reports should have been written but were not highlight the need for continued
i
management emphasis on this important problem identification program.
Violations 2 and 3 were of concern as examples of inadequacies in ensuring that
equipment and systems are tested at their required frequency including technical
l
specification required surveillances.
I
l
These violations are cited in the enclosed Notice of Violation, and the circumstances
surrounding the violations are uescribed in detail in the enclosed report. Please note that
you ars required to respond to this letter and should follow the instructions specified in the
enclosed Notice when preparing your response, in your response, please address what
you will be doing to ensure that corrective actions taken for the RHR valve mispositioning
and the two failures to write a condition report will be more effective than actions taken
for previous valve configuration control and condition reporting system problems. The
NRC will use your response, in part, to determine whether further enforcement action is
necessary to ensure compliance with regulatory requirements.
.
.
S. A. Patuiski
-2-
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter,
the enclosures, and your response to the letter will be placed in the NRC Public Document
Room (PDR).
Sincerely,
\\
.
ames L. Caldwell, Director
1
) Division of Reactor Projects
I
Docket Nos.: 50-266, 50-301,72-005
. Enclosures:
2. Inspection Report No. 50-266/96019(DRP);
s
50-301/96019(DRP) 72-005/96019(DRP)
cc w/ encl:
R. R. Grigg, President and Chief
Operating Officer, WEPCO
A. J. Cayia, Plant Manager
Virgil Kanable, Chief,
{
Boiler Section
Cheryl L. Parrino, Chairman
Wisconsin Public Service
l
Commission
State Liaison Officer
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