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OPERATING DATA REPORT gg DOCKET NO.           50 -30 2 DATE       3/4/80 COMPLETED BY           M.W. Culver TELEPHO'iE         (904) 795-6486 OPERATING STATUS
l OPERATING DATA REPORT gg DOCKET NO.
: 1. Unit Name:       Crystal River #3                                               Notes
50 -30 2 DATE 3/4/80 COMPLETED BY M.W. Culver TELEPHO'iE (904) 795-6486 OPERATING STATUS 1.
: 2. Reporting Period:           2/1/80       -
Unit Name:
2729/80
Crystal River #3 Notes 2729/80 2.
: 3. Licensed Thermal Power (MWi):                 '"2
Reporting Period:
: 4. Nameplate Rating (Gross MWe): -- m'
2/1/80 3.
: 5. Design Electrical Rating (Het Tide):               825
Licensed Thermal Power (MWi):
,      6. Maximum Dependable Capacity (Gross F1We): 821
'"2 4.
: 7.                                                                      782 7
Nameplate Rating (Gross MWe): -- m' 5.
      '8. Maximum If ChangesDependable Occur in Capacity   Capacity    (Net MWe)(: Itens Number 3 Through 7) Since Last Report, Ratings Reasons:
Design Electrical Rating (Het Tide):
: i.     9. Power Level to Which Restricted. If Any (Not MWe):                                             None
825 6.
: 10. Reasons For Restrictions. If Any:
Maximum Dependable Capacity (Gross F1We): 821 Maximum Dependable Capacity (Net MWe)(: Itens Number 3 Through 7) Since Last Report, 782 7
This Month                         Yr.-to-Date                     Cumulative
7.
: 11.     Ilours In Reporting Period                                           696                                         1440                       26016
If Changes Occur in Capacity Ratings
: 12. - Number of flours Reactor Was Critical                                     572.5                                       1305.5                     16455.8
'8.
,    13.       Reactor Reserve Shutdown llours                                         0.0                                           0.0                   1116.9
Reasons:
: 14.     Ilours Generator On-Line                                             568.0                                       1297.4                     15997.6
i.
: 15. Unit Reserve Shutdown llours                                                 0.0                                           0.0                         0.0
9.
    -16.       Gross Thermal Energy Generated (MWil)                           1345568                                 3085927                         35402838           ,
Power Level to Which Restricted.
i
If Any (Not MWe):
: 17.     Gross Electrical Energy Generated (MWil)                         458458                                 1058396                         12030164
None
  - 18.       Net Electrical Energy Generated (MWil)                               437893                             1009335                         11400975           i
: 10. Reasons For Restrictions.
    -19.       Unit Service Factor                                                       81.6%                                     90.1%                       61.5%
If Any:
;    20. Unit Availability Factor                                                         81.6%                                     90.1%                       61.5%
This Month Yr.-to-Date Cumulative 11.
: 21. Unit Capacity Factor (Using MDC lbt)                                           80.57.                                     89.6%                       56.0%
Ilours In Reporting Period 696 1440 26016
Unit Capacity Factor (Using DER Net)                                        76. 3f,                                  85.0%                      53.1%
: 12. - Number of flours Reactor Was Critical 572.5 1305.5 16455.8 13.
Reactor Reserve Shutdown llours 0.0 0.0 1116.9 14.
Ilours Generator On-Line 568.0 1297.4 15997.6
: 15. Unit Reserve Shutdown llours 0.0 0.0 0.0
-16.
Gross Thermal Energy Generated (MWil) 1345568 3085927 35402838 17.
Gross Electrical Energy Generated (MWil) 458458 1058396 12030164 i
- 18.
Net Electrical Energy Generated (MWil) 437893 1009335 11400975 i
-19.
Unit Service Factor 81.6%
90.1%
61.5%
: 20. Unit Availability Factor 81.6%
90.1%
61.5%
: 21. Unit Capacity Factor (Using MDC lbt) 80.57.
89.6%
56.0%
22.
22.
: 23. - Unit Forced Outage Rate                                                       18.4%                                     62.8%                       34.0 %
Unit Capacity Factor (Using DER Net)
<      24. Shutdown Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
: 76. 3f, 85.0%
Undergoin9 reevaluation due to present shutdown
53.1%
: 25.       If- Shut Down At End Of Report Period.             Estimated Date of Startup:                                       3/20/80                               l
: 23. - Unit Forced Outage Rate 18.4%
: 26.       Units in Test Status (Prior to Cunmercial Operation):                                                                   Forecast             Achieved INITIAL CRITICALITY                                                                                                                 1/14/77 INITIAL ELECTRICITY                                                                                                                 1/30/77 COMMERCIAL OPERATION                                                                                                               3/13/77 LSimpson(0pDataRpt)D92                                                                                                                                                 I
62.8%
                                                                              .                                            800319094
34.0 %
24.
Shutdown Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Undergoin9 reevaluation due to present shutdown 25.
If-Shut Down At End Of Report Period.
Estimated Date of Startup:
3/20/80 26.
Units in Test Status (Prior to Cunmercial Operation):
Forecast Achieved INITIAL CRITICALITY 1/14/77 INITIAL ELECTRICITY 1/30/77 COMMERCIAL OPERATION 3/13/77 LSimpson(0pDataRpt)D92 800319094


        ',                        AVERAGE DAILY UflIT POWER LEVEL DOCKET NO. 50-302 UNIT   FLCRP-3 DATE 3/3/80 COMPLETED BY   M. W. Culver TELEPHONE 904-795-6486 MONTH         February DAY   AVERAGE DAILY POWER LEVEL           DAY     AVERAGE DAILY POWER LEVEL (MWe-Net)                                       (Mt4e-Met) 1             800                         17                 793 2             796                         18                 793             ,
AVERAGE DAILY UflIT POWER LEVEL DOCKET NO.
3            798                         19                 794 4             794                         20                 795 5             784                         21                 794 6             750                         22                 795 7             754                         23                 794 8             778                         24                 795 9             485                         25                 651 10               0                         26                446 11             224                         27                 0 12             733                         28                 0 13             794                         29                 0 14             757                         30                 0 15             743                         31                 0 16             778 1
50-302 UNIT FLCRP-3 DATE 3/3/80 COMPLETED BY M. W. Culver TELEPHONE 904-795-6486 MONTH February DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
INSTRUCTIONS On this fonnat, list the average daily unit power level in Mde-Met for each day in the eporting month. Conpute to the nearest whole megawatt.
(Mt4e-Met) 1 800 17 793 2
796 18 793 3
798 19 794 4
794 20 795 5
784 21 794 6
750 22 795 7
754 23 794 8
778 24 795 9
485 25 651 26 446 10 0
11 224 27 0
12 733 28 0
13 794 29 0
14 757 30 0
15 743 31 0
16 778 1
INSTRUCTIONS On this fonnat, list the average daily unit power level in Mde-Met for each day in the eporting month.
Conpute to the nearest whole megawatt.
Simpson(0pDataRpt)D92
Simpson(0pDataRpt)D92


UNIT SHUTDOWNS AND POWER REDUCTIONS                           DOCKET NO.       50-302 UNIT NAME       FLLRP.-3 DATE     3/4/80 COMPLETED BY   M. W. CulNer REPORT MONTH     FEBRUARY                               TELEPHONE   904-795-6486 Typel   Dura-           Method tion             of         Licensee       Systgm   Component                 Cause & Corrective INo.
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
Date               (Hrs) Reason 2 Shutting     Event         Code       Code 5                       Action to Down         Report                                             Prevent Recurrence Reactor 3 Asyretric fault alana received; 80-6     800209             F     46.5   A         1         N/A             RB     CRDRVE       power reduced to 60% for 8.5 hrs.
50-302 UNIT NAME FLLRP.-3 DATE 3/4/80 COMPLETED BY M. W. CulNer REPORT MONTH FEBRUARY TELEPHONE 904-795-6486 Typel Dura-Method tion of Licensee Systgm Component Cause & Corrective INo.
then shutdown for repair when rod 6-1 dropped to its intimit the 2nd ti me. Dropped rod due to stator failure.
Date (Hrs)
:80-7     800225           F         0     A         4         N/A             CH     PIPEXX       Reduced power to 50* to repair a crack in a weld on the "B" MFWP recirc. line.
Reason 2 Shutting Event Code Code 5 Action to Down Report Prevent Recurrence Reactor 3 Asyretric fault alana received; 80-6 800209 F
80-8     800226           F       81.5   A         3       80-010/01T         IF     INSTRU       Loss of power to part of the plant instrumentation system resulting     i-in a forced shutdown                 !
46.5 A
(See Licensee Event Report).
1 N/A RB CRDRVE power reduced to 60% for 8.5 hrs.
F: Forced         2. Reason:                                     3 Method:             4 S: Scheduled         A. Equipment Failure (Explain)                 1. Manual               Exhibit G - Instructions B. Maintenance or Test                         2. Manual Scram           For Preparation of Data C. Refueling                                   3. Automatic Scran       Entry Sheets for Licensee D. Regulatory Restriction                     4.0ther(Explain)         Event Report (LER) File (NUREG-0161)
then shutdown for repair when rod 6-1 dropped to its intimit the 2nd ti me.
E.0peratcr Training & License Examination F. Administrative                                                     5 G. Operational Error (Explain)                                           Exhibit 1 - Same Source H.0ther (Explain)
Dropped rod due to stator failure.
      >impson(0pDataRpt)D92
:80-7 800225 F
0 A
4 N/A CH PIPEXX Reduced power to 50* to repair a crack in a weld on the "B" MFWP recirc. line.
80-8 800226 F
81.5 A
3 80-010/01T IF INSTRU Loss of power to part of the plant instrumentation system resulting i-in a forced shutdown (See Licensee Event Report).
F: Forced 2.
Reason:
3 Method:
4 S: Scheduled A. Equipment Failure (Explain)
: 1. Manual Exhibit G - Instructions B. Maintenance or Test
: 2. Manual Scram For Preparation of Data C. Refueling
: 3. Automatic Scran Entry Sheets for Licensee D. Regulatory Restriction 4.0ther(Explain)
Event Report (LER) File (NUREG-0161)
E.0peratcr Training & License Examination F. Administrative 5
l G. Operational Error (Explain)
Exhibit 1 - Same Source i
H.0ther (Explain)
>impson(0pDataRpt)D92


                                                                                            ~
~
o MONTilLY STATUS REPORT REFUELING INFORMATION REQUEST-
o MONTilLY STATUS REPORT REFUELING INFORMATION REQUEST-1.
: 1. Name of Facility: Crystal River Unit 3                                         .
Name of Facility: Crystal River Unit 3 2.
: 2. Scheduled date of next refueling shutdown: Currently shut down
Scheduled date of next refueling shutdown: Currently shut down 3.
: 3. Scheduled date for restart following refueling: vune, 1980
Scheduled date for restart following refueling: vune, 1980 4.
: 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment? Yes. In             ,
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment? Yes.
general, changes to the CR #3 technical specifications will include:
In general, changes to the CR #3 technical specifications will include:
: a. Moderator Temperature Coefficient (3.1.1.3)
a.
: b. Control Rod Insertion Limits (3.1.3.6)
Moderator Temperature Coefficient (3.1.1.3) b.
: c. Control Rod Group Assignments (3.1.3.7)
Control Rod Insertion Limits (3.1.3.6) c.
: d. Axial Imbalance Limits (3.2.1)
Control Rod Group Assignments (3.1.3.7) d.
: e. Refueling Boron Concentration (3.9.1)
Axial Imbalance Limits (3.2.1) e.
Refueling Boron Concentration (3.9.1)
These specifications will be reviewed and changed as necessary based on the reactivity of the third cycle as compared to that of the second cycle.
These specifications will be reviewed and changed as necessary based on the reactivity of the third cycle as compared to that of the second cycle.
l               5. Scheduled date(s) for submitting proposed licensing action and supporting information: March, 1980
l 5.
: 6. Important licensing considerations associated with refueling, e.g.,
Scheduled date(s) for submitting proposed licensing action and supporting information: March, 1980 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, or new operating procedures.
new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, or new operating procedures.
:                    Florida Power Corporation is presently discussing with the NRC staff 1                     our intent to request that the power level of CR #3 be raised from the i                     present level of 2452 MW (t) to the ultimate core power level of
Florida Power Corporation is presently discussing with the NRC staff 1
(                     2544 MW (t) as described in the CR #3 FSAR. FPC submitted, on February 28, 1979, our reload report justifying Cycle 2 operation of CR #3 at 2544 MW (t). On May 25, 1979, FPC modified its Cycle 2 reload report justifying continued operation of 2452 MW (t). It is our intent to cuntinue our discussions with the NRC in order to obtain
our intent to request that the power level of CR #3 be raised from the i
.                    the power upgrade at the April 1980 refueling outage.
present level of 2452 MW (t) to the ultimate core power level of
t
(
: 7. The number of fuel assemblies (a) in the core and (b) in the spent
2544 MW (t) as described in the CR #3 FSAR. FPC submitted, on February 28, 1979, our reload report justifying Cycle 2 operation of CR #3 at 2544 MW (t). On May 25, 1979, FPC modified its Cycle 2 reload report justifying continued operation of 2452 MW (t).
                    . fuel storage pool.
It is our intent to cuntinue our discussions with the NRC in order to obtain the power upgrade at the April 1980 refueling outage.
: a. 177 assemblies
t 7.
: b. 60 assemblies
The number of fuel assemblies (a) in the core and (b) in the spent
: 18. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies,
. fuel storage pool.
: a. Present storage capacity - Pool A - 120 plus 8 failed fuel assemblies.
a.
177 assemblies b.
60 assemblies 18.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies, a.
Present storage capacity - Pool A - 120 plus 8 failed fuel assemblies.
Pool B - 120 plus 8 failed fuel dssemblies.
Pool B - 120 plus 8 failed fuel dssemblies.
Simpson(MSRpt)DN89'                   -
Simpson(MSRpt)DN89'
: 8.   (Continued)
 
: b. Filed request on January 9,1978 with NRC concerning expansion of Pool A from 120 to 544 assenblies plus 6 failed fuel assemblies and expansion of Pool B from 120 to 609 assemblies. Expansion of Pool A is to occur af ter the refueling ia March,1980. The Pool B expansion will occur at a later refueling outage (approximately 1986).
8.
(Continued) b.
Filed request on January 9,1978 with NRC concerning expansion of Pool A from 120 to 544 assenblies plus 6 failed fuel assemblies and expansion of Pool B from 120 to 609 assemblies.
Expansion of Pool A is to occur af ter the refueling ia March,1980. The Pool B expansion will occur at a later refueling outage (approximately 1986).
Additional detailed design information concerning our fuel pool expansion was submitted to the Commission on March 3 and March 28, 1978, January 18, 1979, March 16, 1979, June 29, 1979, September 5, 1979 and October 10, 1979.
Additional detailed design information concerning our fuel pool expansion was submitted to the Commission on March 3 and March 28, 1978, January 18, 1979, March 16, 1979, June 29, 1979, September 5, 1979 and October 10, 1979.
: 9. The projected date of the last refueling that can be discharged to the spent fuel assuming the present licensed capacity. 1981-1982 1
9.
i Simpson(MSRpt)DN89                 .}}
The projected date of the last refueling that can be discharged to the spent fuel assuming the present licensed capacity.
1981-1982 i
Simpson(MSRpt)DN89
.}}

Latest revision as of 06:10, 2 January 2025

Monthly Operating Rept for Feb 1980
ML19305B338
Person / Time
Site: Crystal River 
Issue date: 03/04/1980
From: Culver M
FLORIDA POWER CORP.
To:
Shared Package
ML19305B328 List:
References
NUDOCS 8003190542
Download: ML19305B338 (5)
v • d • e


Text

,.

- _ _ _ =..

l OPERATING DATA REPORT gg DOCKET NO.

50 -30 2 DATE 3/4/80 COMPLETED BY M.W. Culver TELEPHO'iE (904) 795-6486 OPERATING STATUS 1.

Unit Name:

Crystal River #3 Notes 2729/80 2.

Reporting Period:

2/1/80 3.

Licensed Thermal Power (MWi):

'"2 4.

Nameplate Rating (Gross MWe): -- m' 5.

Design Electrical Rating (Het Tide):

825 6.

Maximum Dependable Capacity (Gross F1We): 821 Maximum Dependable Capacity (Net MWe)(: Itens Number 3 Through 7) Since Last Report, 782 7

7.

If Changes Occur in Capacity Ratings

'8.

Reasons:

i.

9.

Power Level to Which Restricted.

If Any (Not MWe):

None

10. Reasons For Restrictions.

If Any:

This Month Yr.-to-Date Cumulative 11.

Ilours In Reporting Period 696 1440 26016

12. - Number of flours Reactor Was Critical 572.5 1305.5 16455.8 13.

Reactor Reserve Shutdown llours 0.0 0.0 1116.9 14.

Ilours Generator On-Line 568.0 1297.4 15997.6

15. Unit Reserve Shutdown llours 0.0 0.0 0.0

-16.

Gross Thermal Energy Generated (MWil) 1345568 3085927 35402838 17.

Gross Electrical Energy Generated (MWil) 458458 1058396 12030164 i

- 18.

Net Electrical Energy Generated (MWil) 437893 1009335 11400975 i

-19.

Unit Service Factor 81.6%

90.1%

61.5%

20. Unit Availability Factor 81.6%

90.1%

61.5%

21. Unit Capacity Factor (Using MDC lbt) 80.57.

89.6%

56.0%

22.

Unit Capacity Factor (Using DER Net)

76. 3f, 85.0%

53.1%

23. - Unit Forced Outage Rate 18.4%

62.8%

34.0 %

24.

Shutdown Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Undergoin9 reevaluation due to present shutdown 25.

If-Shut Down At End Of Report Period.

Estimated Date of Startup:

3/20/80 26.

Units in Test Status (Prior to Cunmercial Operation):

Forecast Achieved INITIAL CRITICALITY 1/14/77 INITIAL ELECTRICITY 1/30/77 COMMERCIAL OPERATION 3/13/77 LSimpson(0pDataRpt)D92 800319094

AVERAGE DAILY UflIT POWER LEVEL DOCKET NO.

50-302 UNIT FLCRP-3 DATE 3/3/80 COMPLETED BY M. W. Culver TELEPHONE 904-795-6486 MONTH February DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(Mt4e-Met) 1 800 17 793 2

796 18 793 3

798 19 794 4

794 20 795 5

784 21 794 6

750 22 795 7

754 23 794 8

778 24 795 9

485 25 651 26 446 10 0

11 224 27 0

12 733 28 0

13 794 29 0

14 757 30 0

15 743 31 0

16 778 1

INSTRUCTIONS On this fonnat, list the average daily unit power level in Mde-Met for each day in the eporting month.

Conpute to the nearest whole megawatt.

Simpson(0pDataRpt)D92

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-302 UNIT NAME FLLRP.-3 DATE 3/4/80 COMPLETED BY M. W. CulNer REPORT MONTH FEBRUARY TELEPHONE 904-795-6486 Typel Dura-Method tion of Licensee Systgm Component Cause & Corrective INo.

Date (Hrs)

Reason 2 Shutting Event Code Code 5 Action to Down Report Prevent Recurrence Reactor 3 Asyretric fault alana received; 80-6 800209 F

46.5 A

1 N/A RB CRDRVE power reduced to 60% for 8.5 hrs.

then shutdown for repair when rod 6-1 dropped to its intimit the 2nd ti me.

Dropped rod due to stator failure.

80-7 800225 F

0 A

4 N/A CH PIPEXX Reduced power to 50* to repair a crack in a weld on the "B" MFWP recirc. line.

80-8 800226 F

81.5 A

3 80-010/01T IF INSTRU Loss of power to part of the plant instrumentation system resulting i-in a forced shutdown (See Licensee Event Report).

F: Forced 2.

Reason:

3 Method:

4 S: Scheduled A. Equipment Failure (Explain)

1. Manual Exhibit G - Instructions B. Maintenance or Test
2. Manual Scram For Preparation of Data C. Refueling
3. Automatic Scran Entry Sheets for Licensee D. Regulatory Restriction 4.0ther(Explain)

Event Report (LER) File (NUREG-0161)

E.0peratcr Training & License Examination F. Administrative 5

l G. Operational Error (Explain)

Exhibit 1 - Same Source i

H.0ther (Explain)

>impson(0pDataRpt)D92

~

o MONTilLY STATUS REPORT REFUELING INFORMATION REQUEST-1.

Name of Facility: Crystal River Unit 3 2.

Scheduled date of next refueling shutdown: Currently shut down 3.

Scheduled date for restart following refueling: vune, 1980 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment? Yes.

In general, changes to the CR #3 technical specifications will include:

a.

Moderator Temperature Coefficient (3.1.1.3) b.

Control Rod Insertion Limits (3.1.3.6) c.

Control Rod Group Assignments (3.1.3.7) d.

Axial Imbalance Limits (3.2.1) e.

Refueling Boron Concentration (3.9.1)

These specifications will be reviewed and changed as necessary based on the reactivity of the third cycle as compared to that of the second cycle.

l 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: March, 1980 6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, or new operating procedures.

Florida Power Corporation is presently discussing with the NRC staff 1

our intent to request that the power level of CR #3 be raised from the i

present level of 2452 MW (t) to the ultimate core power level of

(

2544 MW (t) as described in the CR #3 FSAR. FPC submitted, on February 28, 1979, our reload report justifying Cycle 2 operation of CR #3 at 2544 MW (t). On May 25, 1979, FPC modified its Cycle 2 reload report justifying continued operation of 2452 MW (t).

It is our intent to cuntinue our discussions with the NRC in order to obtain the power upgrade at the April 1980 refueling outage.

t 7.

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

. fuel storage pool.

a.

177 assemblies b.

60 assemblies 18.

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

Present storage capacity - Pool A - 120 plus 8 failed fuel assemblies.

Pool B - 120 plus 8 failed fuel dssemblies.

Simpson(MSRpt)DN89'

8.

(Continued) b.

Filed request on January 9,1978 with NRC concerning expansion of Pool A from 120 to 544 assenblies plus 6 failed fuel assemblies and expansion of Pool B from 120 to 609 assemblies.

Expansion of Pool A is to occur af ter the refueling ia March,1980. The Pool B expansion will occur at a later refueling outage (approximately 1986).

Additional detailed design information concerning our fuel pool expansion was submitted to the Commission on March 3 and March 28, 1978, January 18, 1979, March 16, 1979, June 29, 1979, September 5, 1979 and October 10, 1979.

9.

The projected date of the last refueling that can be discharged to the spent fuel assuming the present licensed capacity.

1981-1982 i

Simpson(MSRpt)DN89

.

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