ML20134H216
| ML20134H216 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/28/1997 |
| From: | Caldwell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Watzl E NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20134H217 | List: |
| References | |
| NUDOCS 9702110209 | |
| Download: ML20134H216 (2) | |
See also: IR 05000282/1996016
Text
fuhUN
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a.
l
.
January 28, 1997
Mr. E. Watzl. Vice President
Nuclear Generation
.
Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
l
SUBJECT:
NRC INSPECTION REPORT NO. 50-282/96016, 50-306/96016
. Dear Mr. Watzl:-
i
On January 7.1997, the NRC completed an inspection at your Prairie Island
'
Nuclear Generating Plant.
The enclosed report presents the results of that
inspection.
l
.
During the 7-week period covered by this inspection, your conduct of
activities at the Prairie Island facilities was generally acceptable.
However, a concern with operator performance during surveillance activities
was identified in the three most recent resident inspector reports.
During
this report period an additional operator error during surveillance activities
- was identified.
Your staff also identified a case where operators had
performed an incorrect surveillance test.
Both of these errors were due to
i
inadequate self-checking by licensed operators.
In addition. the NRC
'
identified that many of your surveillance 3rocedures were not written in the
format specified by your writer's guide.
de are concerned that this could
lead to additional errors during performance.
An inadvertent boron dilution of the reactor coolant system occurred during
recovery from a maintenance activity due to an incorrectly specified valve
position.
While operators detected the dilution in a timely manner, the
incorrect valve position had not been identified by two licensed operators
during their reviews of the documentation prior to returning the letdown
purification system to service. This was another example of inadequate self-
checking similar to the surveillance errors discussed above.
We understand that corrective actions for the errors discussed above have been
initiated in response to the cited violation in our last report and recent
,
Licensee Event Reports. Therefore we elected to provide you a reasonable time
for corrective action implementation before re-citing similar events involving
,
operator errors, and the issues discussed above were considered non-cited
violations.
However, we remain concerned with weaknesses in operator
performance and will closely monitor the effectiveness of those actions.
1
9702110209 970128
ADOCK 05000282
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E. Watz1
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"
.
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
(PDR).
Sincerely.
/s/ J. A. Grobe for
J. L. Caldwell
Director
Division of Reactor Projects
Docket Nos.
50-282. 50-306
License Nos:
Enclosure:
Inspection Report 50-282/96016. 50-308/96016
cc w/ encl:
Plant Manager. Prairie Island
John W. Ferman, Ph.D.,
,
Nuclear Engineer. MPCA
State Liaison Officer. State
of Minnesota
j
State Liaison Officer. State
of Wisconsin
'
Tribal Council
Prairie Island Dakota Community
Distribution:
Docket File w/ encl
DRP w/ encl
PUBLIC IE-01 w/ encl
RIII PRR w/ encl
OC/LFDCB w/ enc 1
Prairie Island PM. NRR w/ encl
SRI Prairie Island w/ encl
CAA1 w/ encl (E-mail)
Monticello w/ enc 1
A. B. Beach, w/ encl
H. B. Clayton, w/ enc 1
W. L. Axelson, w/ encl
DOCUMENT NAME:
R:\\INSPRPTS\\ POWERS \\PRAI\\PRA96016.DRP
eive a copy of this document, indicate in the box "C" = Copy without attach /enci "E" = Copy with attach /enci
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OFFICE
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NAME
JacobsdnN Ntaldwell'-h
DATE
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OFFICIAL RECORD COPY