ML20198D548: Difference between revisions
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{{#Wiki_filter:, | {{#Wiki_filter:, | ||
.. | |||
_ | |||
- | |||
$ | - | ||
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#ptp Ettoq% | |||
UNITED STATES | |||
NUCLEAR REGULATORY COMMISSION | |||
$ | |||
o | |||
REGloN lil | |||
M | |||
j | |||
801 WARRENvlLLE ROAD | |||
" | " | ||
* | |||
LISLE, ILLINOIS 60532-4351 | |||
'+, *****,o | |||
' | |||
December 7, 1998 | |||
.. | |||
. | |||
Mr. D. R. Gipson | |||
Senior Vice President | |||
Nuclear Generation | |||
The Detroit Edison Company | |||
6400 North Dixie Highway | |||
Newport, MI 48166 | |||
, | |||
SUBJECT: | |||
FERMI INSPECTION REPORT 50-341/98015(DRP) | |||
Dear Mr. Gipson: | |||
On November 9,1998, the NRC completed an inspection at your Fermi 2 reactor facility. The | |||
enclosed report presents the results of that inspection. During the 7-week period covered by | |||
this inspection period, your conduct of activities was generally characterized by | |||
safety-conscious operations, sound engineering, and good maintenance practices. | |||
During the inspection, a number of personnel errors occurred during the refueling outage. | |||
Consequently, the station error free clock was reset 11 times during the outage due to - | |||
personnel errors. An example of a personnel error resulted in the issuance of a non-cited | |||
violation for the failure to follow an operating procedure and the deenergizing of an engineored | |||
safety features bus. The inspection also identified a concern regarding the failure to correctly | |||
schedule a surveillance test on the primary containment radiation monitoring system. Your | |||
identification of a failure to perform the surveillance test within the surveillance interval was | |||
determined to be a non-cited violation of the Technical Specifications for the failure to adhere to | |||
the Offsite Dose Calculation Manual requirements. Finally, concerns were identified regarding | |||
the quality of the ma'atenance procedures for the high pressure turbine control valves. | |||
Although these are nasafety-related pieces of equipment, insufficient torque applied to | |||
. portions of the valve linkage resulted in unanticipated cycling of the valve internals during valve | |||
manipulation. The valve cycling caused significant fluctuations in reactor power level and | |||
caused operators to insert manual scrams on two occasions. These concerns indicate that | |||
continued attention is needed to reduce personnel errors and to control maintenance activities. | |||
\\ | |||
T | |||
9812230118 981207 | |||
PDR | |||
ADOCK 05000341 | |||
G | |||
PDR | |||
. | |||
. | |||
. | |||
D.'. Gipson | |||
-2- | |||
~ | |||
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, the | |||
enclosure, and your response will be placed in the NRC Public Document Room. | |||
* | |||
Sincerely, | |||
/s/ C. Phillips for | |||
Anton Vogel, Chief | |||
Reactor Projects Branch 6 | |||
Docket No.: 50-341 | |||
License No.: NPF-43 | |||
Enclosure: | |||
Inspection Report 50-341/98015(DRP) | |||
cc w/ encl: | |||
N. Peterson, Director, Nuclear Licensing | |||
P. Marquardt, Corporate Legal Department | |||
R. Gaston, Compliance Supervisor | |||
R. Whale, Michigan Public Service Commission | |||
Michigan Department of Environmental Quality | |||
Monroe County, Emergency Management Division | |||
Emergency Management Division, Ml Department | |||
of State Police | |||
' | |||
Document Name: G:\\FERM\\FER98015.DRP | |||
r - . | |||
um - - w e.co m - .r.co | |||
1, | - .v.ma. | ||
OFFICE | |||
Rlli | |||
l | |||
Rlli - | |||
l | |||
Rlll | |||
l | |||
l | |||
NAME | |||
Phillips/ml /4 | |||
Burgess Il | |||
Vegel tff | |||
DATE | |||
12/1/98 | |||
'V | |||
12/1/98 | |||
12M/98 I | |||
'' | |||
OFFICIAL RECORD COPY | |||
1, | |||
, | |||
__ | |||
_ _ _ _ . . | |||
' | ' | ||
- | |||
1 | |||
. | |||
, - . | |||
D. Gipson | |||
-2- | |||
, | |||
Distribution: | |||
CAC (E Mail) | |||
RPC (E-Mail) | |||
Project Mgr., NRR w/enci | |||
J. Caldwell, Rill w/enci | |||
. | |||
C. Pederson, Ril' w/enci | |||
B. Clayton, Rill w/ encl | |||
SRI Fermi w/enct | |||
DRP w/ encl | |||
TSS w/enci | |||
DRS (2) w/enci | |||
Rlli PRR w/enct | |||
PUBLIC IE-01 w/enci | |||
Docket File w/ encl | |||
GREENS | |||
LEO (E-Mail) | |||
DOCDESK (E-Mail) | |||
210102 | |||
' | |||
.. | |||
. | |||
- _ - _ - - - - - - - - | |||
A | |||
}} | }} | ||
Latest revision as of 12:37, 10 December 2024
| ML20198D548 | |
| Person / Time | |
|---|---|
| Site: | Fermi |
| Issue date: | 12/07/1998 |
| From: | Anton Vegel NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gipson D DETROIT EDISON CO. |
| Shared Package | |
| ML20198D551 | List: |
| References | |
| 50-341-98-15, NUDOCS 9812230118 | |
| Download: ML20198D548 (3) | |
See also: IR 05000341/1998015
Text
,
..
_
-
-
_
_ . ~.- - .-
.
- ptp Ettoq%
UNITED STATES
NUCLEAR REGULATORY COMMISSION
$
o
REGloN lil
M
j
801 WARRENvlLLE ROAD
"
LISLE, ILLINOIS 60532-4351
'+, *****,o
'
December 7, 1998
..
.
Mr. D. R. Gipson
Senior Vice President
Nuclear Generation
The Detroit Edison Company
6400 North Dixie Highway
Newport, MI 48166
,
SUBJECT:
FERMI INSPECTION REPORT 50-341/98015(DRP)
Dear Mr. Gipson:
On November 9,1998, the NRC completed an inspection at your Fermi 2 reactor facility. The
enclosed report presents the results of that inspection. During the 7-week period covered by
this inspection period, your conduct of activities was generally characterized by
safety-conscious operations, sound engineering, and good maintenance practices.
During the inspection, a number of personnel errors occurred during the refueling outage.
Consequently, the station error free clock was reset 11 times during the outage due to -
personnel errors. An example of a personnel error resulted in the issuance of a non-cited
violation for the failure to follow an operating procedure and the deenergizing of an engineored
safety features bus. The inspection also identified a concern regarding the failure to correctly
schedule a surveillance test on the primary containment radiation monitoring system. Your
identification of a failure to perform the surveillance test within the surveillance interval was
determined to be a non-cited violation of the Technical Specifications for the failure to adhere to
the Offsite Dose Calculation Manual requirements. Finally, concerns were identified regarding
the quality of the ma'atenance procedures for the high pressure turbine control valves.
Although these are nasafety-related pieces of equipment, insufficient torque applied to
. portions of the valve linkage resulted in unanticipated cycling of the valve internals during valve
manipulation. The valve cycling caused significant fluctuations in reactor power level and
caused operators to insert manual scrams on two occasions. These concerns indicate that
continued attention is needed to reduce personnel errors and to control maintenance activities.
\\
T
9812230118 981207
ADOCK 05000341
G
.
.
.
D.'. Gipson
-2-
~
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, the
enclosure, and your response will be placed in the NRC Public Document Room.
Sincerely,
/s/ C. Phillips for
Anton Vogel, Chief
Reactor Projects Branch 6
Docket No.: 50-341
License No.: NPF-43
Enclosure:
Inspection Report 50-341/98015(DRP)
cc w/ encl:
N. Peterson, Director, Nuclear Licensing
P. Marquardt, Corporate Legal Department
R. Gaston, Compliance Supervisor
R. Whale, Michigan Public Service Commission
Michigan Department of Environmental Quality
Monroe County, Emergency Management Division
Emergency Management Division, Ml Department
of State Police
'
Document Name: G:\\FERM\\FER98015.DRP
r - .
um - - w e.co m - .r.co
- .v.ma.
OFFICE
Rlli
l
Rlli -
l
Rlll
l
l
NAME
Phillips/ml /4
Burgess Il
Vegel tff
DATE
12/1/98
'V
12/1/98
12M/98 I
OFFICIAL RECORD COPY
1,
,
__
_ _ _ _ . .
'
-
1
.
, - .
D. Gipson
-2-
,
Distribution:
CAC (E Mail)
RPC (E-Mail)
Project Mgr., NRR w/enci
J. Caldwell, Rill w/enci
.
C. Pederson, Ril' w/enci
B. Clayton, Rill w/ encl
SRI Fermi w/enct
DRP w/ encl
TSS w/enci
DRS (2) w/enci
Rlli PRR w/enct
PUBLIC IE-01 w/enci
Docket File w/ encl
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
210102
'
..
.
- _ - _ - - - - - - - -
A