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=Text=
=Text=
{{#Wiki_filter:_ . . . _ _ .-  _    ._ _      >    __                              __
{{#Wiki_filter:_... _
l $ ?an=                                                                                   Davis-Besse Nuclear Power Station j     yn                                                                                               5501 North State Route 2
l $ ?an=
\                         m                                                                        Oak Harbor. Ohio 43449-9760
Davis-Besse Nuclear Power Station j
    ,    November 13,1998.
yn 5501 North State Route 2
\\
Oak Harbor. Ohio 43449-9760 m
November 13,1998.
CCN: P-6-98-10 i
CCN: P-6-98-10 i
Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Ladies and Gentlemen:
Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Ladies and Gentlemen:
Monthly Operating Report, October 1998 Davis-Besse Nuclear Power Station Unit 1 Enclosed is a copy of the Monthly Operating Report for the Davis-Besse Nuclear Power Station for the month of Oeober 1998.
Monthly Operating Report, October 1998 Davis-Besse Nuclear Power Station Unit 1 Enclosed is a copy of the Monthly Operating Report for the Davis-Besse Nuclear Power Station for the month of Oeober 1998.
If you have any questions, please contact E. C. Matranga at (419) 321-8369.
If you have any questions, please contact E. C. Matranga at (419) 321-8369.
l l        Very truly yours,
l Very truly yours,
        ~ju   s H. Lash                                                                                                           l Plant Manager Davis-Besse Nuclear Power Station ECM/ljk                                                                                                                   l Enclosure p       cc:     . J. L. Caldwell NRC Region III Acting Administrator A. G. Hansen NRC Project Manager                                                                                 ,
~ju s H. Lash Plant Manager Davis-Besse Nuclear Power Station ECM/ljk l
j                S. J. Campbell NRC Senior Resident Inspector                                               /
Enclosure p
lh                    l 9811170269 981031 iM PDR R        ADOCK 05000345" PDRC e
cc:
. J. L. Caldwell NRC Region III Acting Administrator A. G. Hansen NRC Project Manager j
S. J. Campbell lh l
NRC Senior Resident Inspector
/
9811170269 981031 iM PDR ADOCK 05000345" R
PDRCe


  , .. r .
.. r.
OPERATING DATA REPORT DOCKET NO.                         50-0346 UNIT NAME                         Davis-Besse Unit 1 DATE                   November 9.1998 COMPLETED BY                             E. C. Matranaa TELEPHONE                         419-321-8369 REPORTING PERIOD                         October.1998 YEAR IQ MONTH     DATE     CUMULATIVE 1 Design Electrical Rating (MWe-Net).                                     906 The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.
OPERATING DATA REPORT DOCKET NO.
2 Maximum Dependable Capacity (MWe-Net).                                   873               I The gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal i
50-0346 UNIT NAME Davis-Besse Unit 1 DATE November 9.1998 COMPLETED BY E. C. Matranaa TELEPHONE 419-321-8369 REPORTING PERIOD October.1998 YEAR IQ MONTH DATE CUMULATIVE 1 Design Electrical Rating (MWe-Net).
station service loads.                                                                     I 3 Number of Hours the Reactor Was Cntical.                   624.6   5,827.7   120,259.9 The total number of hours during the gross hours of the reporting period that the reactor was critical.
906 The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.
4 Number of Hours the Generator Was On Line.                 605.0   5,719.9   117,807.7 (Also called Service Hours). The total number of hours during the gross hours of the reporting period that the unit operated with breakers closed to the station bus.
2 Maximum Dependable Capacity (MWe-Net).
873 The gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal station service loads.
3 Number of Hours the Reactor Was Cntical.
624.6 5,827.7 120,259.9 The total number of hours during the gross hours of the reporting period that the reactor was critical.
4 Number of Hours the Generator Was On Line.
605.0 5,719.9 117,807.7 (Also called Service Hours). The total number of hours during the gross hours of the reporting period that the unit operated with breakers closed to the station bus.
The sum of the hours the generator was on line plus the total outage hours should equal the gross hours in the reporting period.
The sum of the hours the generator was on line plus the total outage hours should equal the gross hours in the reporting period.
5 Unit Reserve Shutdown Hours.                                 0.0       0.0       5,532.0 The total number of hours during the gross                                                 ;
5 Unit Reserve Shutdown Hours.
hours of the reporting period ths; the l
0.0 0.0 5,532.0 The total number of hours during the gross hours of the reporting period ths; the unit was removed from service for economic or similar reasons but was available for i
unit was removed from service for economic                                                 1 or similar reasons but was available for                                                   i operation.
operation.
6 Net Electrical Energy (MWH).                             524,776 4,835,429   95,061,986 The gross electrical output of the unit measured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in mega-watt hours. Negative quantities should not be used.
6 Net Electrical Energy (MWH).
1
524,776 4,835,429 95,061,986 The gross electrical output of the unit measured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in mega-watt hours. Negative quantities should not be used.
 
* a UNIT SHUTDOWNS
a UNIT SHUTDOWNS                                                                                                                                                                                     ^
^
DOCKET NO.'                 50-346   k UNIT NAME Davis-Besse #1             -
DOCKET NO.'
DATE_ November 9,1998 COMPLETED BY E. C. Mau^ ese REPORTING PERIOD: October.1998                                                                                                                                                                                                                                                                 TELEPHONE (419) 32't-8369 NO.     DATE                           TYPE                   DURATION             REASON (1) METHOD OF -                                                                                                                                   CAUSE/ CORRECTIVE ACTIONS F: FORCED .                     (HOURS)                                                               SHUTTING                                                                                                                                                                         ,
50-346 k
S: SCHEDULED                                                                                           DOWN (2)                                                                                                                           COMMENTS 1998-11   10/14/98                         F                                                         A                                                                             2                                                 Inadequate human interface design caused the loss of the essential 4160 bus. Improved guidance and additional barriers added. Failed rupture disk caused the CCW leak. A 146.9                                                                                                                                                           modification was initiated for additional overpressure protection.
UNIT NAME Davis-Besse #1 DATE_ November 9,1998 COMPLETED BY E. C. Mau^ ese REPORTING PERIOD: October.1998 TELEPHONE (419) 32't-8369 NO.
1998-12   10/18/98                         F                                                           F                                                                           3                                                 Improper procedure sequence. Procedure was changed.
DATE TYPE DURATION REASON (1)
METHOD OF -
CAUSE/ CORRECTIVE ACTIONS F: FORCED.
(HOURS)
SHUTTING S: SCHEDULED DOWN (2)
COMMENTS 1998-11 10/14/98 F
A 2
Inadequate human interface design caused the loss of the essential 4160 bus. Improved guidance and additional barriers added. Failed rupture disk caused the CCW leak. A 146.9 modification was initiated for additional overpressure protection.
1998-12 10/18/98 F
F 3
Improper procedure sequence. Procedure was changed.


==SUMMARY==
==SUMMARY==
Reactor power was maintained at approximately 100% full power for the majority of the month. On October 14,1998, at 1523 hours, the reactor was manually tripped from 87% full power due to a Component Cooling Water leak that occurred following a loss and re-energization of an essential 4160 volt electrical bus. Following completion of required maintenance, a reactor startup was commenced and criticality achieved October 18, 1998, at 1636 hours. An automatic reactor trip occured at 2152 hours due to mispositioning an Anticipatory Reactor Trip System (ARTS) switch during the startup. Following the completion of corrective action, the reactor was taken critical at 1904 hours on October 19,1998. The Main Generator was synchronized to the grid at 1131 hours on October 20, and 100% full power was achieved at 2030 hours on October 21.1996 (1) Reason:                                                                                         (2) Method:
Reactor power was maintained at approximately 100% full power for the majority of the month. On October 14,1998, at 1523 hours, the reactor was manually tripped from 87% full power due to a Component Cooling Water leak that occurred following a loss and re-energization of an essential 4160 volt electrical bus. Following completion of required maintenance, a reactor startup was commenced and criticality achieved October 18, 1998, at 1636 hours. An automatic reactor trip occured at 2152 hours due to mispositioning an Anticipatory Reactor Trip System (ARTS) switch during the startup. Following the completion of corrective action, the reactor was taken critical at 1904 hours on October 19,1998. The Main Generator was synchronized to the grid at 1131 hours on October 20, and 100% full power was achieved at 2030 hours on October 21.1996 (1) Reason:
A-Equipment Failure (Explain)                                                                               1-Manual '
(2) Method:
B-Maintenance or Test                                                                                       2-Manual Trip / Scram C-Refueling                                                                                                 3-Automatic Trip / Scram D-Regulatory Restriction                                                                                   4-Continuation E-Operator Training & License Examin                                                                       5-Other (Explain)
A-Equipment Failure (Explain) 1-Manual '
B-Maintenance or Test 2-Manual Trip / Scram C-Refueling 3-Automatic Trip / Scram D-Regulatory Restriction 4-Continuation E-Operator Training & License Examin 5-Other (Explain)
F-Administrative G-Operational Error (Explain)
F-Administrative G-Operational Error (Explain)
H-Other (Explain)
H-Other (Explain)
_  _      _ _ _ _ _ _          _ -- _-          _ -. - _ - - _ _ - . .-- _-__ - _ _ .                                                                                                                  - - - _ - - - . - _ _ _ _ _      _ _ _ ___          .___-___- --- --__ _              - - _ - _ .}}
.}}

Latest revision as of 19:20, 10 December 2024

Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With
ML20195D000
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 10/31/1998
From: Lash J, Matranga E
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN:P-6-98-10, NUDOCS 9811170269
Download: ML20195D000 (3)
v • d • e


Text

_... _

l $ ?an=

Davis-Besse Nuclear Power Station j

yn 5501 North State Route 2

\\

Oak Harbor. Ohio 43449-9760 m

November 13,1998.

CCN: P-6-98-10 i

Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Ladies and Gentlemen:

Monthly Operating Report, October 1998 Davis-Besse Nuclear Power Station Unit 1 Enclosed is a copy of the Monthly Operating Report for the Davis-Besse Nuclear Power Station for the month of Oeober 1998.

If you have any questions, please contact E. C. Matranga at (419) 321-8369.

l Very truly yours,

~ju s H. Lash Plant Manager Davis-Besse Nuclear Power Station ECM/ljk l

Enclosure p

cc:

. J. L. Caldwell NRC Region III Acting Administrator A. G. Hansen NRC Project Manager j

S. J. Campbell lh l

NRC Senior Resident Inspector

/

9811170269 981031 iM PDR ADOCK 05000345" R

PDRCe

.. r.

OPERATING DATA REPORT DOCKET NO.

50-0346 UNIT NAME Davis-Besse Unit 1 DATE November 9.1998 COMPLETED BY E. C. Matranaa TELEPHONE 419-321-8369 REPORTING PERIOD October.1998 YEAR IQ MONTH DATE CUMULATIVE 1 Design Electrical Rating (MWe-Net).

906 The nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.

2 Maximum Dependable Capacity (MWe-Net).

873 The gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions minus the normal station service loads.

3 Number of Hours the Reactor Was Cntical.

624.6 5,827.7 120,259.9 The total number of hours during the gross hours of the reporting period that the reactor was critical.

4 Number of Hours the Generator Was On Line.

605.0 5,719.9 117,807.7 (Also called Service Hours). The total number of hours during the gross hours of the reporting period that the unit operated with breakers closed to the station bus.

The sum of the hours the generator was on line plus the total outage hours should equal the gross hours in the reporting period.

5 Unit Reserve Shutdown Hours.

0.0 0.0 5,532.0 The total number of hours during the gross hours of the reporting period ths; the unit was removed from service for economic or similar reasons but was available for i

operation.

6 Net Electrical Energy (MWH).

524,776 4,835,429 95,061,986 The gross electrical output of the unit measured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in mega-watt hours. Negative quantities should not be used.

  • a UNIT SHUTDOWNS

^

DOCKET NO.'

50-346 k

UNIT NAME Davis-Besse #1 DATE_ November 9,1998 COMPLETED BY E. C. Mau^ ese REPORTING PERIOD: October.1998 TELEPHONE (419) 32't-8369 NO.

DATE TYPE DURATION REASON (1)

METHOD OF -

CAUSE/ CORRECTIVE ACTIONS F: FORCED.

(HOURS)

SHUTTING S: SCHEDULED DOWN (2)

COMMENTS 1998-11 10/14/98 F

A 2

Inadequate human interface design caused the loss of the essential 4160 bus. Improved guidance and additional barriers added. Failed rupture disk caused the CCW leak. A 146.9 modification was initiated for additional overpressure protection.

1998-12 10/18/98 F

F 3

Improper procedure sequence. Procedure was changed.

SUMMARY

Reactor power was maintained at approximately 100% full power for the majority of the month. On October 14,1998, at 1523 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.795015e-4 months <br />, the reactor was manually tripped from 87% full power due to a Component Cooling Water leak that occurred following a loss and re-energization of an essential 4160 volt electrical bus. Following completion of required maintenance, a reactor startup was commenced and criticality achieved October 18, 1998, at 1636 hours0.0189 days <br />0.454 hours <br />0.00271 weeks <br />6.22498e-4 months <br />. An automatic reactor trip occured at 2152 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.18836e-4 months <br /> due to mispositioning an Anticipatory Reactor Trip System (ARTS) switch during the startup. Following the completion of corrective action, the reactor was taken critical at 1904 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.24472e-4 months <br /> on October 19,1998. The Main Generator was synchronized to the grid at 1131 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.303455e-4 months <br /> on October 20, and 100% full power was achieved at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on October 21.1996 (1) Reason:

(2) Method:

A-Equipment Failure (Explain) 1-Manual '

B-Maintenance or Test 2-Manual Trip / Scram C-Refueling 3-Automatic Trip / Scram D-Regulatory Restriction 4-Continuation E-Operator Training & License Examin 5-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

.

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