ML20063L108: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:.           .          -                .        - . - -                    _      -        -                    ._
{{#Wiki_filter:.
I' a
I' a
      .co************************************************************r*************
.co************************************************************r*************
UNIT 1 OPERATING DATA REPORT oo*********************************************************r****************
UNIT 1 OPERATING DATA REPORT oo*********************************************************r****************
Docket No. 50-317 February 15,.1994                                             ~
Docket No. 50-317 February 15,.1994
Prepared by Frank Piazza Telephone: (410) 2 60-3 821                                   l OPERATING STATUS
~
: 1.       UNIT NAME                                           Calvert Cliffs Unit 1                                         ,.
Prepared by Frank Piazza Telephone: (410) 2 60-3 821 l
: 2.        REPORTING PERIOD                                     JANUARY 1994
OPERATING STATUS 1.
: 3.       LICENSED THERMAL POWER (MWT)                                           2700
UNIT NAME Calvert Cliffs Unit 1 2.
: 4.       NAMEPLATE RATING (GROSS MWe)                                             918
REPORTING PERIOD JANUARY 1994 3.
: 5.       DESIGN ELECTRICAL RATING (NET MWe)                                       845
LICENSED THERMAL POWER (MWT) 2700 4.
: 6. MAXIMUM DEPENDABLE CAP'Y (GROSS MWe)                                           860                                       ,
NAMEPLATE RATING (GROSS MWe) 918 5.
: 7. MAXIMUM DEPENDABLE CAP'Y (NET MWe)                                             830
DESIGN ELECTRICAL RATING (NET MWe) 845
: 8. CHANGE IN CAPACITY RATINGS                                                   NONE
: 6. MAXIMUM DEPENDABLE CAP'Y (GROSS MWe) 860 7.
: 9. POWER LEVEL TO WHICH RESTRICTED                                                 N/A
MAXIMUM DEPENDABLE CAP'Y (NET MWe) 830 8.
: 10. REASONS FOR RESTRICTIONS                                                       N/A Cumulative     "
CHANGE IN CAPACITY RATINGS NONE 9.
This month                   Year-to-Date to Date           l
POWER LEVEL TO WHICH RESTRICTED N/A
: 11. HOURS IN REPORTING PERIOD                                                       744                   744     164,245     ,
: 10. REASONS FOR RESTRICTIONS N/A Cumulative This month Year-to-Date to Date l
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                                       561.4                     561.4 117,530.4     ,
: 11. HOURS IN REPORTING PERIOD 744 744 164,245
: 13. REACTOR RESERVE SHUTDOWN HOURS                                                 0.0                   0.0   '3,019.4
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL 561.4 561.4 117,530.4
: 14. HOURS GENERATOR ON LINE                                                   561.4                     561.4 115,139.8
: 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0
: 15. UNIT RESERVE SHUTDOWN HOURS                                                     0.0                   0.0         0.0
'3,019.4
: 16. GROSS THERMAL ENERGY GENERATED (MWH)                             1,511,925                     1,511,925 291,826,744       ,
: 14. HOURS GENERATOR ON LINE 561.4 561.4 115,139.8
: 17. GROSS ELECTRICAL ENERGY GEN'TED(MWH)                                 507,645                     507,645 96,981,191
: 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 18. NET ELECTRICAL ENERGY GENERATED (MWH)                                 483,493                     483,493 92,287,775     l
: 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,511,925 1,511,925 291,826,744
: 19. UNIT SERVICE FACTOR                                                         75.5                     75.5       70.1-   ;
: 17. GROSS ELECTRICAL ENERGY GEN'TED(MWH) 507,645 507,645 96,981,191
: 20. UNIT AVAILABILITY FACTOR                                                     75.5                     75.5       70.1     j
: 18. NET ELECTRICAL ENERGY GENERATED (MWH) 483,493 483,493 92,287,775 l
    '21. UNIT CAPACITY FACTOR (USING MDC NET)                                         78.3                     78.3       68.1L   '
: 19. UNIT SERVICE FACTOR 75.5 75.5 70.1-
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                         76.9                     76.9       66.5-   ;
: 20. UNIT AVAILABILITY FACTOR 75.5 75.5 70.1 j
: 23. UNIT FORCED OUTAGE RATE                                                       24.5                     24.5       '8.8     '
'21.
UNIT CAPACITY FACTOR (USING MDC NET) 78.3 78.3 68.1L
: 22. UNIT CAPACITY FACTOR (USING DER NET) 76.9 76.9 66.5-
: 23. UNIT FORCED OUTAGE RATE 24.5 24.5
'8.8
: 24. SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION):
: 24. SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION):
Refueling, February 8, 1994, 90 Days                                                             .l
Refueling, February 8, 1994, 90 Days
: 25. IF SHUTDOWN AT END OF REPORT PERIOD,                                                                                       .
.l
ESTIMATED DATE OF START-UP:                                                                                   !
: 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:
February 2, 1994-                                                                                 ,
February 2, 1994-t i
t i
9403040004 940215 E
9403040004 940215 PDR E
PDR ADOCK 05000317 R
ADOCK 05000317         :
PDR l
R                  PDR       ;                                                                                ;
l


UNIT SIIUTDOWNS AND POWER REDUCllONS
UNIT SIIUTDOWNS AND POWER REDUCllONS DOCKET NO. 317 UNIT NAME Cahrrt Cliffs-U1
* DOCKET NO.             317                                       ~
~
UNIT NAME             Cahrrt Cliffs-U1 DATE           February 15.1994 i                                                                                                                                       COMPLETED BY               Frank Pia 77a                                   "
DATE February 15.1994 i
TELEPHONE               (4101 260-3821 REPORT MONTIl Jnnuary 1994 MEUIOD OF
COMPLETED BY Frank Pia 77a TELEPHONE (4101 260-3821 REPORT MONTIl Jnnuary 1994 MEUIOD OF SIlUTUNG LICENSEE CAUSE & CORRECnVE 3
.                                                                        SIlUTUNG   LICENSEE                                                 CAUSE & CORRECnVE 3
DURNRON DOWN EVENT SYS1 tim COMPONENT ACDONTO (IIOURS)
DURNRON                       DOWN         EVENT       SYS1 tim   COMPONENT                           ACDONTO NO.      DATE        TYPEI          (IIOURS)     REASON 2     REACIUR3   REPORT #         CODE 4         CODES                   PREVENT RECURRENCE INVT 94-01     940124           F           182.6         A             3       317/94-01         ED                       The Unit automatically shutdown on 1/24/94 at 0926 due to a loss of the 120 Vac Vital Panel 1YO2. The loss of the panel was due to the failure of the voltage regulator card in the 12 Vital Inverter                                     '
REASON 2 REACIUR3 REPORT #
which resulted in the loss of the 120 Vac Vital Panel and the Unit trip.
CODE 4 CODES PREVENT RECURRENCE NO.
Circuit cards were replaced and load tested both
DATE TYPEI 94-01 940124 F
,                                                                                                                              statically and dynamically. Due to the ongoing trouble shooting to determine the exact cause of the failure, an Unusual Event #3765 was declared and the Unit was cooled down and entered into Mode 5 at 2105 on 1/26N4.
182.6 A
3 317/94-01 ED INVT The Unit automatically shutdown on 1/24/94 at 0926 due to a loss of the 120 Vac Vital Panel 1YO2. The loss of the panel was due to the failure of the voltage regulator card in the 12 Vital Inverter which resulted in the loss of the 120 Vac Vital Panel and the Unit trip.
Circuit cards were replaced and load tested both statically and dynamically. Due to the ongoing trouble shooting to determine the exact cause of the failure, an Unusual Event #3765 was declared and the Unit was cooled down and entered into Mode 5 at 2105 on 1/26N4.
A Significant incident Finding Team was established to investigate the cause and to determine long term corrective resolutions.
A Significant incident Finding Team was established to investigate the cause and to determine long term corrective resolutions.
1 F: Forced                             2 Reason:                                                     3 Method:                         4 IEEE Standard 805-1984 S: Scheduled                           A - Equipment Failure                                         1 - Manual -
1 F: Forced 2 Reason:
B - Maintenance or Test                                       2 - Manual Scram.                                                                                 !
3 Method:
-;                                                C- Refueling                                                   3 - Automatic Scram.           5 IEEE Standard 803A-1983 D - Regulatory Restriction           _
4 IEEE Standard 805-1984 l
4 - Continued                                                                                      >
S: Scheduled A - Equipment Failure 1 - Manual -
E - Operator Training & License Examination                   5 - Reduced Load F- Administrative                                             9 - Other G - Operational Error H - Other
B - Maintenance or Test 2 - Manual Scram.
C-Refueling 3 - Automatic Scram.
5 IEEE Standard 803A-1983 4 - Continued D - Regulatory Restriction 5 - Reduced Load E - Operator Training & License Examination F-Administrative 9 - Other G - Operational Error H - Other


h
h
                                                                                                                      .a F
.a F
                              -AVERAGE DAILY UNIT POWER LEVEL oc**********************************************************************                                         ;
-AVERAGE DAILY UNIT POWER LEVEL oc**********************************************************************
                                                            -Docket No. 50-317 Calvert Cliffs Unit No. 1 February-15, 1994 Prepared by Frank Piazza                                   ',
-Docket No. 50-317 Calvert Cliffs Unit No. 1 February-15, 1994 Prepared by Frank Piazza Telephone: (410) 260-3821 JANUARY 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net)
Telephone: (410) 260-3821 JANUARY 1994 Average Daily Power Level                         Average Daily Power Level Day           (MWe-Net)                       Day             (MWe-Net)
Day (MWe-Net) 1 867 17 863 2
* 1                 867                             17         863 2                 867                             18         866 3                 868                             19         867 4                 868                             20         870                           i 5                 868                             21         870                           ;
867 18 866 3
6                  883                             22         870                           i 7                 886                             23         870 8                 868                             24         323 9                 867                             25           0 10                 854                             26           0                           !
868 19 867 4
11                 853                       '27                 0 i
868 20 870 i
12                 866                             28           0-13                 869                             29           0 14                 872                             30           0                           i l
5 868 21 870 6
15                 871                             31           0
883 22 870 i
                                                                                                                        ,t 16                 868                                                                         F 1
7 886 23 870 8
I I
868 24 323 9
                  ,  ,,                  .      .              .:.. - - _ .    -            -  _____.__--.__-.__c
867 25 0
10 854 26 0
11 853
'27 0
i 12 866 28 0-13 869 29 0
14 872 30 0
i l
15 871 31 0
16 868 F
1 I
I c


DOCKET NO. 50-317                                                                                                   i i
DOCKET NO. 50-317 i
CALVERT CLIFFS - UNIT 1 February 15,1994                                                                                                   l l
CALVERT CLIFFS - UNIT 1 i
I
February 15,1994 l


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE January 1994 He unit began the month at 100% reactor power (870 MWe).
OF OPERATING EXPERIENCE I
* On 1/24f>4 at 0926, the unit tripped due to a loss of the 120 Vac Vital Panel 1Y02. The loss of the Panel was due to the failure of the voltage regulator in the 12 Vital Inverter. A Significant Incident Finding Team was immediately formed to investigate the cause of the inverter failure and to -
January 1994 He unit began the month at 100% reactor power (870 MWe).
determine future corrective actions. Because the root cause for the inverter failure was not                       ;
On 1/24f>4 at 0926, the unit tripped due to a loss of the 120 Vac Vital Panel 1Y02. The loss of the Panel was due to the failure of the voltage regulator in the 12 Vital Inverter. A Significant Incident Finding Team was immediately formed to investigate the cause of the inverter failure and to -
determined in sufficient time, the unit commenced cooldown at 1050 on 1/26/94 as required by                       ;
determine future corrective actions. Because the root cause for the inverter failure was not determined in sufficient time, the unit commenced cooldown at 1050 on 1/26/94 as required by Technical Specifications and entered Mode 5 at 2105. The Inverter Voltage Regulator Board was -
Technical Specifications and entered Mode 5 at 2105. The Inverter Voltage Regulator Board was -                     .
subsequently found to be faulty and was replaced.
subsequently found to be faulty and was replaced.
The Unit ended the month shutdown in Mode 3 after starting a plant heat-up.
The Unit ended the month shutdown in Mode 3 after starting a plant heat-up.
l l
l l
1
1
                                                                                                                            )
)
l 1
1 I
I 1
1


I               January 6. 1994                                                                   ,
I January 6. 1994 NFM 94-004-l Page 2 of 4 1
            . NFM 94-004-                                                                       l Page 2 of 4                                                                       !
REFUELING INFORMATION REQUEST l
1 REFUELING INFORMATION REQUEST                           l 1
1 1.
: 1. Name of facility: Calvert Cliffs Nuclear Power.. Plant, Unit No.1.
Name of facility: Calvert Cliffs Nuclear Power.. Plant, Unit No.1.
: 2. Scheduled date for next refueling shutdown:   February 8, 1994.
2.
* i
Scheduled date for next refueling shutdown:
: 3. Scheduled date for restart following refueling:   May 9, 1994.
February 8, 1994.
: 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other-license amendment?
i 3.
Operation after refueling will require either " Core Operating Limits       1 Report" or will require a change to Technical Specification 3/4.2.2,.     i
Scheduled date for restart following refueling:
                      " Linear Heat Rate".                                                       !
May 9, 1994.
: 5. Scheduled date(s) for submitting proposed licensing action and supporting informatiori.
4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other-license amendment?
Operation after refueling will require either " Core Operating Limits 1
Report" or will require a change to Technical Specification 3/4.2.2,.
i
" Linear Heat Rate".
5.
Scheduled date(s) for submitting proposed licensing action and supporting informatiori.
Submitted September 1993 for Core Operating Limits Report.
Submitted September 1993 for Core Operating Limits Report.
.              6. Important licensing considerations associated with the refueling, None identified at this time.                                           .;
6.
7,   The number of fuel assemblies (a) in the core and (b) in the spent fuel     '
Important licensing considerations associated with the refueling, None identified at this time.
storage pool.
7, The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 217. (b) 1426. (Note 2) *                                     - t Spent fuel pools are common to Units 1 and 2.                               {
(a) 217.
: 8.   (a) The present licensed spent fuel pool storage ca3acity, and (b) the     ,
(b) 1426. (Note 2) *
size of any increase in licensed storage capacity tlat has been             :
- t Spent fuel pools are common to Units 1 and 2.
requested or is planned, in number of fuel assemblies.
{
(a) 4710. (NOTE 1)       (b) 0.
8.
i 9     The projected date of the last refueling that can be discharged to the   .;
(a) The present licensed spent fuel pool storage ca3acity, and (b) the size of any increase in licensed storage capacity tlat has been requested or is planned, in number of fuel assemblies.
Spent Fuel Pool assuming the present licensed capacity and maintaining -
(a) 4710. (NOTE 1)
space for one full core off-load.                                          .
(b) 0.
March 2014                                                         ,
i 9
* Entry has changed since last report.                                       -i NOTE 1: 4710 total licensed site storage capacity.                               ,
The projected date of the last refueling that can be discharged to the Spent Fuel Pool assuming the present licensed capacity and maintaining -
                      -(1830 pool + 2880 ISFSI)                                                   i NOTE 2:  72 Spent Fuel Assemblies in the ISFSI.                                 ;
space for one full core off-load.
I                                                                                                 1 L                                                                                                 !
March 2014 Entry has changed since last report.
- i NOTE 1: 4710 total licensed site storage capacity.
-(1830 pool + 2880 ISFSI) i 72 Spent Fuel Assemblies in the ISFSI.
NOTE 2:
I 1
L r


.~       -        -        -      ..  .  .                    -      . - . .          .    . - . -      ..-      - --
.~
W l
W l
l l
l l
Cd**************************************************************************
Cd**************************************************************************
UNIT 2 OPERATING DATA REPORT i        QQ**************************************************************************
UNIT 2 OPERATING DATA REPORT QQ**************************************************************************
l                                                               Docket No. 50-318 l                                                               February 15, 1994 Prepared by Frank Piazza Telephone : (410) 260-3821 OPERATING STATUS
i l
: 1. UNIT NAME                                       Calvert Cliffs Unit 2                                             -
Docket No. 50-318 l
: 2. REPORTING PERIOD                                   JANUARY 1994
February 15, 1994 Prepared by Frank Piazza Telephone : (410) 260-3821 OPERATING STATUS 1.
: 3. LICENSED THERMAL POWER (MWT)                                         2700                                             ,
UNIT NAME Calvert Cliffs Unit 2
: 4. NAMEPLATE RATING (GROSS MWe)                                         911
: 2. REPORTING PERIOD JANUARY 1994 3.
: 5. DESIGN ELECTRICAL RATING.(NET MWe)                                   845
LICENSED THERMAL POWER (MWT) 2700 4.
: 6. MAXIMUM DEPENDABLE CAP'Y (GROSS MWe)                                 860
NAMEPLATE RATING (GROSS MWe) 911
: 7. MAXIMUM DEPENDABLE CAP'Y (NET MWe)                                   830
: 5. DESIGN ELECTRICAL RATING.(NET MWe) 845 6.
: 8. CHANGE IN CAPACITY RATINGS                                           NONE
MAXIMUM DEPENDABLE CAP'Y (GROSS MWe) 860
{         9. POWER LEVEL TO WHICH RESTRICTED                                       N/A l_       10. REASONS FOR RESTRICTIONS                                               N/A Cumulative This month                 Year-to-Date                 to Date
: 7. MAXIMUM DEPENDABLE CAP'Y (NET MWe) 830 8.
: 11. HOURS IN REPORTING PERIOD                                             '744                       744         147,600
CHANGE IN CAPACITY RATINGS NONE
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                               571.2                       571.2       106,608.0-
{
: 13. REACTOR RESERVE SHUTDOWN HOURS                                         0.0                       0.0         1,296.6
9.
: 14. HOURS GENERATOR ON LINE                                           568.0                       568.0       105,091.6
POWER LEVEL TO WHICH RESTRICTED N/A l_
: 15. UNIT RESERVE SHUTDOWN HOURS                                           0.0                       0.0             0.0
: 10. REASONS FOR RESTRICTIONS N/A Cumulative This month Year-to-Date to Date
: 16. GROSS THERMAL ENERGY GENERATED (MWH)                     1,509,766                     1,509,766 268,375,309
: 11. HOURS IN REPORTING PERIOD
: 17. GROSS ELECTRICAL ENERGY GEN'TED(MWH)                             506,297                 506,297- 88,662,166         ,
'744 744 147,600
l
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL 571.2 571.2 106,608.0-
: 18. NET ELECTRICAL ENERGY GENERATED (MWH)                           483,609                 483,609 84,726,743
: 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1,296.6
: 19. UNIT SERVICE FACTOR                                                   76.3                       76.3           71.2
: 14. HOURS GENERATOR ON LINE 568.0 568.0 105,091.6
: 20. UNIT AVAILABILITY FACTOR                                             76.3                       76.3           71.2
: 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 21. UNIT CAPACITY FACTOR (USING MDC NET)                                 78.3                       78.3           69.6
: 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,509,766 1,509,766 268,375,309
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                 76.9                       76.9           67.9'
: 17. GROSS ELECTRICAL ENERGY GEN'TED(MWH) 506,297 506,297-88,662,166 l
: 23. UNIT FORCED OUTAGE RATE                                               23.7                       23.7             5.8
: 18. NET ELECTRICAL ENERGY GENERATED (MWH) 483,609 483,609 84,726,743
: 19. UNIT SERVICE FACTOR 76.3 76.3 71.2
: 20. UNIT AVAILABILITY FACTOR 76.3 76.3 71.2
: 21. UNIT CAPACITY FACTOR (USING MDC NET) 78.3 78.3 69.6
: 22. UNIT CAPACITY FACTOR (USING DER NET) 76.9 76.9 67.9'
: 23. UNIT FORCED OUTAGE RATE 23.7 23.7 5.8
: 24. SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION):
: 24. SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION):
N/A
N/A
Line 168: Line 200:
N/A
N/A


UNIT SIIUTDOWNS AND POWER REDUCTIONS                                                                       -
UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
DOCKET NO.           50-318 UNITNAME             Calwrt ClitTs-U2                     -
50-318 UNITNAME Calwrt ClitTs-U2 DATE February 15.1004 i
DATE         February 15.1004 i
COMPLETED BY Frank Piana TELEPHONE (410) 2NL3821 REPORTMONTil January 1994 METilOD OF SillTITING LICENSEE CAUSE & CORRECITVE DURATION DOWN EVENT SYSTEM COMPONENT ACITON TO (IIOURS)
COMPLETED BY               Frank Piana TELEPHONE             (410) 2NL3821 REPORTMONTil January 1994 METilOD OF SillTITING       LICENSEE                                             CAUSE & CORRECITVE DURATION                       DOWN             EVENT SYSTEM       COMPONENT                             ACITON TO No. DATE                            TYPEI                  (IIOURS)     REASON 2     REACIOR3         REPORT # CODE 4         CODES                     PREVENT RECURRENCE 94-01   940112                               F                   176.0         A                 3         3183 401         El       RLY       Unit automatically shutdown at 0552 on 1/12N4 when a protective relay for the 13KV Voltage Regulator which was being installed, but not yet operational, caused the supply breaker (# 252-2103) for the Senice Transformer (# U-4000-22) to open.
REASON 2 REACIOR3 REPORT #
CODE 4 CODES PREVENT RECURRENCE No.
DATE TYPEI 94-01 940112 F
176.0 A
3 3183 401 El RLY Unit automatically shutdown at 0552 on 1/12N4 when a protective relay for the 13KV Voltage Regulator which was being installed, but not yet operational, caused the supply breaker (# 252-2103) for the Senice Transformer (# U-4000-22) to open.
This resulted in the loss of the Senice Transformer and actuation of other safety features to trip the Unit.
This resulted in the loss of the Senice Transformer and actuation of other safety features to trip the Unit.
A ground in the associated 125 VDC control circuit interacted with the 125 VDC ground detection system producing a signal which actuated the protective relay and tripped the Unit.
A ground in the associated 125 VDC control circuit interacted with the 125 VDC ground detection system producing a signal which actuated the protective relay and tripped the Unit.
All leads for the new voltage regulator protective circuits for both Units were disconnected and the voltage regulator bypass switches were tagged in the shut position, removing the possibility of the circuitry tripping either Unit.
All leads for the new voltage regulator protective circuits for both Units were disconnected and the voltage regulator bypass switches were tagged in the shut position, removing the possibility of the circuitry tripping either Unit.
A Significant Incident Finding Team was established to investigate the event.
A Significant Incident Finding Team was established to investigate the event.
1 F: Forced                                                       2 Reason:                                                       3 hiethod:                         4 IEEE Standard 805-1984 S: Scheduled                                                       A- Equipment Failure                                           1 - hianual
1 F: Forced 2 Reason:
* B - hiaintenance or Test                                       2 - AfanualScram.
3 hiethod:
C- Refueling                                                   3 - Automatic Scram.             5 IEEE Standard 803A-1983 D - Regulatory Restriction                                     4 - Continued E - Operator Training & License Examination                     5 - Reduced Load F- Administrative                                               9 - Other                                                                               ,
4 IEEE Standard 805-1984 S: Scheduled A-Equipment Failure 1 - hianual B - hiaintenance or Test 2 - AfanualScram.
G - Operational Error H - Other
C-Refueling 3 - Automatic Scram.
5 IEEE Standard 803A-1983 D - Regulatory Restriction 4 - Continued E - Operator Training & License Examination 5 - Reduced Load F-Administrative 9 - Other G - Operational Error H - Other


l' w
l' w
AVERAGE DAILY UNIT POWER LEVEL co**********************************************************************
AVERAGE DAILY UNIT POWER LEVEL co**********************************************************************
Docket No. 50-318 Calvert Cliffs Unit No. 2' _
Docket No. 50-318 Calvert Cliffs Unit No.
February 15, 1994 Prepared by Frank Piazza.                             __ ,
2' _
Telephone: (410) 260-3821                                 '
February 15, 1994 Prepared by Frank Piazza.
JANUARY     1994                                                         .
Telephone: (410) 260-3821 JANUARY 1994 t
                                                            ***************                                                            t Average Daily Power Level                                   Average Daily Power--Level Day             (MWe-Net)                                         Day           (MWe-Net) 1                   871                                       17                   0                     -!
Average Daily Power Level Average Daily Power--Level Day (MWe-Net)
2                     869                                       18                   0                       ,
Day (MWe-Net) 1 871 17 0
3                     870                                       19                 168 4                     871                                       20                 856 5                     871                                       21                 863 6                     853                                       22                 865 7                     853                                       23                 868 8                     776                                       24                 867 9                     871                                       25                 864 10                     885                                       26                 866 11                     886                                       27                 866 12                     196                                       28                 869 13                             0                               29                 869 14                             0                               30                 869 15                             0                               31                 869 16                             0 d
2 869 18 0
                                      -    ,w-. . - . -    r - or             u -.e- e     w -                                  y
3 870 19 168 4
871 20 856 5
871 21 863 6
853 22 865 7
853 23 868 8
776 24 867 9
871 25 864 10 885 26 866 11 886 27 866 12 196 28 869 13 0
29 869 14 0
30 869 15 0
31 869 16 0
d
,w-.
r or u
-.e-e w
y


I l
I DOCKET NO. 50-318 CALVERT CLIFFS - UNIT 2 February 15,1994
l
    .                                                                                                            1 DOCKET NO. 50-318 CALVERT CLIFFS - UNIT 2 February 15,1994


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERlENCE January 1994 1
OF OPERATING EXPERlENCE January 1994 1
The Unit began the month at 100% reactor power (875 MWe). De reactor power was reduced to approximately 82% (720 MWe) on 1/8S4 at 0200 for planned maintenance, Main Turbine valve testing, and water box cleaning. Power was restored to 100% (870 MWe) at 2330 on 1/8S4.
The Unit began the month at 100% reactor power (875 MWe). De reactor power was reduced to approximately 82% (720 MWe) on 1/8S4 at 0200 for planned maintenance, Main Turbine valve testing, and water box cleaning. Power was restored to 100% (870 MWe) at 2330 on 1/8S4.
On 1/12N4 at 0552. a protective relay for a 13 KV Voltage Regulator that was being installed, but not     !
On 1/12N4 at 0552. a protective relay for a 13 KV Voltage Regulator that was being installed, but not yet in operation, actuated on a spurious signal and caused a reactor trip. The trip was a result of the opening of the feeder breaker (# 252-2103) for the 13 KV/4 KV step down transformer (U-4000-22).
yet in operation, actuated on a spurious signal and caused a reactor trip. The trip was a result of the opening of the feeder breaker (# 252-2103) for the 13 KV/4 KV step down transformer (U-4000-22).         -
He reactor tripped immediately when protective safety equipment actuated. The spurious relay 1
He reactor tripped immediately when protective safety equipment actuated. The spurious relay             1 actuation was caused by an intermittent ground on the DC control power circuit which generated a signal to a new solid state seal-in-relay. This scal-in-relay was overly sensitive because its associated sensor was not yet connected. As part of the immediate corrective actions, the voltage regulator           1 protective circuits for both Units were disconnected and the voltage regulator bypass switches were       l tagged in the shut position. This action climinated the possibility of the circuit tripping either Unit umil resolution of the probicm was completed. A Significant Incident Finding Team was also established to investigate the event for the long term corrective resolutions.                           )
actuation was caused by an intermittent ground on the DC control power circuit which generated a signal to a new solid state seal-in-relay. This scal-in-relay was overly sensitive because its associated sensor was not yet connected. As part of the immediate corrective actions, the voltage regulator 1
protective circuits for both Units were disconnected and the voltage regulator bypass switches were tagged in the shut position. This action climinated the possibility of the circuit tripping either Unit umil resolution of the probicm was completed. A Significant Incident Finding Team was also established to investigate the event for the long term corrective resolutions.
)
While in a shutdown condition, a leak was detected in the leak off detection line which monitors reactor vessel head seal leak. The line was repaired while the Unit was shutdown.
While in a shutdown condition, a leak was detected in the leak off detection line which monitors reactor vessel head seal leak. The line was repaired while the Unit was shutdown.
The Unit was returned to power and paralleled to the grid on 1/1994 at 1350, remaining at 100%
The Unit was returned to power and paralleled to the grid on 1/1994 at 1350, remaining at 100%
Line 207: Line 258:


January 6. 1994
January 6. 1994
,    .    *NFM 94-004 l           Page 3 of 4 4
*NFM 94-004 l
REFUELING INFORMATION REQUEST
Page 3 of 4 4
: 1. Name of facility: Calvert Cliffs Nuclear Power Plant. Unit No. 2                                     ,
REFUELING INFORMATION REQUEST 1.
: c.      Scheduled date for next refueling shutdown: March 3, 1995.
Name of facility: Calvert Cliffs Nuclear Power Plant. Unit No. 2 Scheduled date for next refueling shutdown: March 3, 1995.
: 3.     Scheduled date for restart following refueling:                                 May 17, 1995.
c.
: 4.     Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
3.
Scheduled date for restart following refueling:
May 17, 1995.
4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Unknown.
Unknown.
S.     Scheduled date(s) for submitting proposed licensing action and supporting information.                                                                             ,
S.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Unknown.
Unknown.
: 6.       Important licensing considerations associated with the refueling.
6.
Important licensing considerations associated with the refueling.
None identified at this time.
None identified at this time.
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
7.
(a) 217. (b) 1426. (Note 2) *                                                   -
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
Spent fuel pools are common to Units 1 and 2.
(a) 217.
: 8.       (a) The present licensed spent fuel pool storage ca)acity. and (b) the size of any increase in licensed storage capacity tlat has been requested or is planned, in number of fuel assemblies.                                               J (a) 4710 (NOTE 1)                 (b) 0.
(b) 1426.
a
(Note 2)
: 9.       The projected date of the last refueling that can be discharged to the                               ;
* Spent fuel pools are common to Units 1 and 2.
                    -Spent Fuel Pool assuming the present licensed capacity and maintaining space for one full core off-load.
8.
(a) The present licensed spent fuel pool storage ca)acity. and (b) the size of any increase in licensed storage capacity tlat has been requested or is planned, in number of fuel assemblies.
J (a) 4710 (NOTE 1)
(b) 0.
a 9.
The projected date of the last refueling that can be discharged to the
-Spent Fuel Pool assuming the present licensed capacity and maintaining space for one full core off-load.
March 2016.
March 2016.
* Entry has changed since last report.
Entry has changed since last report.
NOTE 1: 4710 total licensed site storage capacity.                                                           i (1830 pool + 2880 ISFSI)
NOTE 1: 4710 total licensed site storage capacity.
NOTE 2:                 72 Spent Fuel Assemblies in the ISFSI.
i (1830 pool + 2880 ISFSI)
NOTE 2:
72 Spent Fuel Assemblies in the ISFSI.
i
i
        +    -- -    - - _ _ _ _ _ . - _        .- _ _ _  .    .  .,-r--.       .. -. . . - - . -    + _ - - - _ , _}}
.,-r--.
+ _ - - - _,
+
-}}

Latest revision as of 21:37, 16 December 2024

Monthly Operating Repts for Jan 1994 for Calvert Cliffs Nuclear Power Plant
ML20063L108
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/31/1994
From: Piazza F
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20063L107 List:
References
NUDOCS 9403040004
Download: ML20063L108 (10)


Text

.

I' a

.co************************************************************r*************

UNIT 1 OPERATING DATA REPORT oo*********************************************************r****************

Docket No. 50-317 February 15,.1994

~

Prepared by Frank Piazza Telephone: (410) 2 60-3 821 l

OPERATING STATUS 1.

UNIT NAME Calvert Cliffs Unit 1 2.

REPORTING PERIOD JANUARY 1994 3.

LICENSED THERMAL POWER (MWT) 2700 4.

NAMEPLATE RATING (GROSS MWe) 918 5.

DESIGN ELECTRICAL RATING (NET MWe) 845

6. MAXIMUM DEPENDABLE CAP'Y (GROSS MWe) 860 7.

MAXIMUM DEPENDABLE CAP'Y (NET MWe) 830 8.

CHANGE IN CAPACITY RATINGS NONE 9.

POWER LEVEL TO WHICH RESTRICTED N/A

10. REASONS FOR RESTRICTIONS N/A Cumulative This month Year-to-Date to Date l
11. HOURS IN REPORTING PERIOD 744 744 164,245
12. NUMBER OF HOURS REACTOR WAS CRITICAL 561.4 561.4 117,530.4
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0

'3,019.4

14. HOURS GENERATOR ON LINE 561.4 561.4 115,139.8
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,511,925 1,511,925 291,826,744
17. GROSS ELECTRICAL ENERGY GEN'TED(MWH) 507,645 507,645 96,981,191
18. NET ELECTRICAL ENERGY GENERATED (MWH) 483,493 483,493 92,287,775 l
19. UNIT SERVICE FACTOR 75.5 75.5 70.1-
20. UNIT AVAILABILITY FACTOR 75.5 75.5 70.1 j

'21.

UNIT CAPACITY FACTOR (USING MDC NET) 78.3 78.3 68.1L

22. UNIT CAPACITY FACTOR (USING DER NET) 76.9 76.9 66.5-
23. UNIT FORCED OUTAGE RATE 24.5 24.5

'8.8

24. SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION):

Refueling, February 8, 1994, 90 Days

.l

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:

February 2, 1994-t i

9403040004 940215 E

PDR ADOCK 05000317 R

PDR l

UNIT SIIUTDOWNS AND POWER REDUCllONS DOCKET NO. 317 UNIT NAME Cahrrt Cliffs-U1

~

DATE February 15.1994 i

COMPLETED BY Frank Pia 77a TELEPHONE (4101 260-3821 REPORT MONTIl Jnnuary 1994 MEUIOD OF SIlUTUNG LICENSEE CAUSE & CORRECnVE 3

DURNRON DOWN EVENT SYS1 tim COMPONENT ACDONTO (IIOURS)

REASON 2 REACIUR3 REPORT #

CODE 4 CODES PREVENT RECURRENCE NO.

DATE TYPEI 94-01 940124 F

182.6 A

3 317/94-01 ED INVT The Unit automatically shutdown on 1/24/94 at 0926 due to a loss of the 120 Vac Vital Panel 1YO2. The loss of the panel was due to the failure of the voltage regulator card in the 12 Vital Inverter which resulted in the loss of the 120 Vac Vital Panel and the Unit trip.

Circuit cards were replaced and load tested both statically and dynamically. Due to the ongoing trouble shooting to determine the exact cause of the failure, an Unusual Event #3765 was declared and the Unit was cooled down and entered into Mode 5 at 2105 on 1/26N4.

A Significant incident Finding Team was established to investigate the cause and to determine long term corrective resolutions.

1 F: Forced 2 Reason:

3 Method:

4 IEEE Standard 805-1984 l

S: Scheduled A - Equipment Failure 1 - Manual -

B - Maintenance or Test 2 - Manual Scram.

C-Refueling 3 - Automatic Scram.

5 IEEE Standard 803A-1983 4 - Continued D - Regulatory Restriction 5 - Reduced Load E - Operator Training & License Examination F-Administrative 9 - Other G - Operational Error H - Other

h

.a F

-AVERAGE DAILY UNIT POWER LEVEL oc**********************************************************************

-Docket No. 50-317 Calvert Cliffs Unit No. 1 February-15, 1994 Prepared by Frank Piazza Telephone: (410) 260-3821 JANUARY 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net)

Day (MWe-Net) 1 867 17 863 2

867 18 866 3

868 19 867 4

868 20 870 i

5 868 21 870 6

883 22 870 i

7 886 23 870 8

868 24 323 9

867 25 0

10 854 26 0

11 853

'27 0

i 12 866 28 0-13 869 29 0

14 872 30 0

i l

15 871 31 0

16 868 F

1 I

I c

DOCKET NO. 50-317 i

CALVERT CLIFFS - UNIT 1 i

February 15,1994 l

SUMMARY

OF OPERATING EXPERIENCE I

January 1994 He unit began the month at 100% reactor power (870 MWe).

On 1/24f>4 at 0926, the unit tripped due to a loss of the 120 Vac Vital Panel 1Y02. The loss of the Panel was due to the failure of the voltage regulator in the 12 Vital Inverter. A Significant Incident Finding Team was immediately formed to investigate the cause of the inverter failure and to -

determine future corrective actions. Because the root cause for the inverter failure was not determined in sufficient time, the unit commenced cooldown at 1050 on 1/26/94 as required by Technical Specifications and entered Mode 5 at 2105. The Inverter Voltage Regulator Board was -

subsequently found to be faulty and was replaced.

The Unit ended the month shutdown in Mode 3 after starting a plant heat-up.

l l

1

)

1 I

1

I January 6. 1994 NFM 94-004-l Page 2 of 4 1

REFUELING INFORMATION REQUEST l

1 1.

Name of facility: Calvert Cliffs Nuclear Power.. Plant, Unit No.1.

2.

Scheduled date for next refueling shutdown:

February 8, 1994.

i 3.

Scheduled date for restart following refueling:

May 9, 1994.

4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other-license amendment?

Operation after refueling will require either " Core Operating Limits 1

Report" or will require a change to Technical Specification 3/4.2.2,.

i

" Linear Heat Rate".

5.

Scheduled date(s) for submitting proposed licensing action and supporting informatiori.

Submitted September 1993 for Core Operating Limits Report.

6.

Important licensing considerations associated with the refueling, None identified at this time.

7, The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217.

(b) 1426. (Note 2) *

- t Spent fuel pools are common to Units 1 and 2.

{

8.

(a) The present licensed spent fuel pool storage ca3acity, and (b) the size of any increase in licensed storage capacity tlat has been requested or is planned, in number of fuel assemblies.

(a) 4710. (NOTE 1)

(b) 0.

i 9

The projected date of the last refueling that can be discharged to the Spent Fuel Pool assuming the present licensed capacity and maintaining -

space for one full core off-load.

March 2014 Entry has changed since last report.

- i NOTE 1: 4710 total licensed site storage capacity.

-(1830 pool + 2880 ISFSI) i 72 Spent Fuel Assemblies in the ISFSI.

NOTE 2:

I 1

L r

.~

W l

l l

Cd**************************************************************************

UNIT 2 OPERATING DATA REPORT QQ**************************************************************************

i l

Docket No. 50-318 l

February 15, 1994 Prepared by Frank Piazza Telephone : (410) 260-3821 OPERATING STATUS 1.

UNIT NAME Calvert Cliffs Unit 2

2. REPORTING PERIOD JANUARY 1994 3.

LICENSED THERMAL POWER (MWT) 2700 4.

NAMEPLATE RATING (GROSS MWe) 911

5. DESIGN ELECTRICAL RATING.(NET MWe) 845 6.

MAXIMUM DEPENDABLE CAP'Y (GROSS MWe) 860

7. MAXIMUM DEPENDABLE CAP'Y (NET MWe) 830 8.

CHANGE IN CAPACITY RATINGS NONE

{

9.

POWER LEVEL TO WHICH RESTRICTED N/A l_

10. REASONS FOR RESTRICTIONS N/A Cumulative This month Year-to-Date to Date
11. HOURS IN REPORTING PERIOD

'744 744 147,600

12. NUMBER OF HOURS REACTOR WAS CRITICAL 571.2 571.2 106,608.0-
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1,296.6
14. HOURS GENERATOR ON LINE 568.0 568.0 105,091.6
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 1,509,766 1,509,766 268,375,309
17. GROSS ELECTRICAL ENERGY GEN'TED(MWH) 506,297 506,297-88,662,166 l
18. NET ELECTRICAL ENERGY GENERATED (MWH) 483,609 483,609 84,726,743
19. UNIT SERVICE FACTOR 76.3 76.3 71.2
20. UNIT AVAILABILITY FACTOR 76.3 76.3 71.2
21. UNIT CAPACITY FACTOR (USING MDC NET) 78.3 78.3 69.6
22. UNIT CAPACITY FACTOR (USING DER NET) 76.9 76.9 67.9'
23. UNIT FORCED OUTAGE RATE 23.7 23.7 5.8
24. SHUTDOWNS SCHEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION):

N/A

25. IF UNIT IS SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:

N/A

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-318 UNITNAME Calwrt ClitTs-U2 DATE February 15.1004 i

COMPLETED BY Frank Piana TELEPHONE (410) 2NL3821 REPORTMONTil January 1994 METilOD OF SillTITING LICENSEE CAUSE & CORRECITVE DURATION DOWN EVENT SYSTEM COMPONENT ACITON TO (IIOURS)

REASON 2 REACIOR3 REPORT #

CODE 4 CODES PREVENT RECURRENCE No.

DATE TYPEI 94-01 940112 F

176.0 A

3 3183 401 El RLY Unit automatically shutdown at 0552 on 1/12N4 when a protective relay for the 13KV Voltage Regulator which was being installed, but not yet operational, caused the supply breaker (# 252-2103) for the Senice Transformer (# U-4000-22) to open.

This resulted in the loss of the Senice Transformer and actuation of other safety features to trip the Unit.

A ground in the associated 125 VDC control circuit interacted with the 125 VDC ground detection system producing a signal which actuated the protective relay and tripped the Unit.

All leads for the new voltage regulator protective circuits for both Units were disconnected and the voltage regulator bypass switches were tagged in the shut position, removing the possibility of the circuitry tripping either Unit.

A Significant Incident Finding Team was established to investigate the event.

1 F: Forced 2 Reason:

3 hiethod:

4 IEEE Standard 805-1984 S: Scheduled A-Equipment Failure 1 - hianual B - hiaintenance or Test 2 - AfanualScram.

C-Refueling 3 - Automatic Scram.

5 IEEE Standard 803A-1983 D - Regulatory Restriction 4 - Continued E - Operator Training & License Examination 5 - Reduced Load F-Administrative 9 - Other G - Operational Error H - Other

l' w

AVERAGE DAILY UNIT POWER LEVEL co**********************************************************************

Docket No. 50-318 Calvert Cliffs Unit No.

2' _

February 15, 1994 Prepared by Frank Piazza.

Telephone: (410) 260-3821 JANUARY 1994 t

Average Daily Power Level Average Daily Power--Level Day (MWe-Net)

Day (MWe-Net) 1 871 17 0

2 869 18 0

3 870 19 168 4

871 20 856 5

871 21 863 6

853 22 865 7

853 23 868 8

776 24 867 9

871 25 864 10 885 26 866 11 886 27 866 12 196 28 869 13 0

29 869 14 0

30 869 15 0

31 869 16 0

d

,w-.

r or u

-.e-e w

y

I DOCKET NO. 50-318 CALVERT CLIFFS - UNIT 2 February 15,1994

SUMMARY

OF OPERATING EXPERlENCE January 1994 1

The Unit began the month at 100% reactor power (875 MWe). De reactor power was reduced to approximately 82% (720 MWe) on 1/8S4 at 0200 for planned maintenance, Main Turbine valve testing, and water box cleaning. Power was restored to 100% (870 MWe) at 2330 on 1/8S4.

On 1/12N4 at 0552. a protective relay for a 13 KV Voltage Regulator that was being installed, but not yet in operation, actuated on a spurious signal and caused a reactor trip. The trip was a result of the opening of the feeder breaker (# 252-2103) for the 13 KV/4 KV step down transformer (U-4000-22).

He reactor tripped immediately when protective safety equipment actuated. The spurious relay 1

actuation was caused by an intermittent ground on the DC control power circuit which generated a signal to a new solid state seal-in-relay. This scal-in-relay was overly sensitive because its associated sensor was not yet connected. As part of the immediate corrective actions, the voltage regulator 1

protective circuits for both Units were disconnected and the voltage regulator bypass switches were tagged in the shut position. This action climinated the possibility of the circuit tripping either Unit umil resolution of the probicm was completed. A Significant Incident Finding Team was also established to investigate the event for the long term corrective resolutions.

)

While in a shutdown condition, a leak was detected in the leak off detection line which monitors reactor vessel head seal leak. The line was repaired while the Unit was shutdown.

The Unit was returned to power and paralleled to the grid on 1/1994 at 1350, remaining at 100%

power (865 MWe) for the remainder of the month.

January 6. 1994

  • NFM 94-004 l

Page 3 of 4 4

REFUELING INFORMATION REQUEST 1.

Name of facility: Calvert Cliffs Nuclear Power Plant. Unit No. 2 Scheduled date for next refueling shutdown: March 3, 1995.

c.

3.

Scheduled date for restart following refueling:

May 17, 1995.

4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Unknown.

S.

Scheduled date(s) for submitting proposed licensing action and supporting information.

Unknown.

6.

Important licensing considerations associated with the refueling.

None identified at this time.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217.

(b) 1426.

(Note 2)

  • Spent fuel pools are common to Units 1 and 2.

8.

(a) The present licensed spent fuel pool storage ca)acity. and (b) the size of any increase in licensed storage capacity tlat has been requested or is planned, in number of fuel assemblies.

J (a) 4710 (NOTE 1)

(b) 0.

a 9.

The projected date of the last refueling that can be discharged to the

-Spent Fuel Pool assuming the present licensed capacity and maintaining space for one full core off-load.

March 2016.

Entry has changed since last report.

NOTE 1: 4710 total licensed site storage capacity.

i (1830 pool + 2880 ISFSI)

NOTE 2:

72 Spent Fuel Assemblies in the ISFSI.

i

.,-r--.

+ _ - - - _,

+

-