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=Text=
=Text=
{{#Wiki_filter:__
{{#Wiki_filter:_ _
8 005130s{No OPERATING DATA REPORT                                                       A
8 005130s{No OPERATING DATA REPORT A
                                                                                                      +
+
)                                                                                                  DOCKET NO. 50-302 DATE 5/5/80 CO)!PLETED BY MW Culver TELEPHONE (on6T 70s-6486 OPERATING STATUS Crystal River #3                                        N"8e5                        ~
DOCKET NO. 50-302
)
DATE 5/5/80 CO)!PLETED BY MW Culver TELEPHONE (on6T 70s-6486 OPERATING STATUS
: l. Unit Name:
: l. Unit Name:
: 2. Reporting Period:4/1/80 - 4/30/80
Crystal River #3 N"8e5
~
: 2. Reporting Period:4/1/80 - 4/30/80 2452
: 3. Licensed 1 hermal Pow er (MWt ):
: 3. Licensed 1 hermal Pow er (MWt ):
2452
890
: 4. Nameplate Rating (Gross MWet:
: 4. Nameplate Rating (Gross MWet:
890
: 5. Design Electrical Rating (Net MWel: 825 821
: 5. Design Electrical Rating (Net MWel: 825
: 6. 51asimum Dependable Capacity (Gross MWet:
: 6. 51asimum Dependable Capacity (Gross MWet:      821
: 7. Maximum Dependable Capacity (Net MWet:
782
782
{
{
: 7. Maximum Dependable Capacity (Net MWet:
d
d
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
: 9. Power Lesel To which Restricted.If Any (Net MWe):     None
None
: 9. Power Lesel To which Restricted.If Any (Net MWe):
: 10. Reasons For Restrictions. If Any:
: 10. Reasons For Restrictions. If Any:
A This Month             Yr..t o.Dat e       Cumularise I1. Hours in Reporting Period                               714                   94M                 27479
A This Month Yr..t o.Dat e Cumularise I1. Hours in Reporting Period 714 94M 27479
: 12. Number Of Hours Reactor has Critical                       0                 1305.5             16455 8 -
: 12. Number Of Hours Reactor has Critical 0
: 13. Reactor Resene Shutdown Hours                             0                       0             1116.9
1305.5 16455 8
: 14. Hours Generator On.Line                                   0                 1297.4           15997.6
: 13. Reactor Resene Shutdown Hours 0
: 15. Unit Reserve Shutdown flours                               0                       0                   0
0 1116.9
: 16. Gross Thermal Energy Generated (MWH)                       0             3085927             35402838 17 Gross Electrical Energy Generated (MWH)                     0    ,_,,    1058396             1203016/:
: 14. Hours Generator On.Line 0
: 18. Net Electrica! Energ> Generated (MWH)                       0             1009335             11400975
1297.4 15997.6
: 19. Unit Senice Factor                                         0                     44.7%             58.2%
: 15. Unit Reserve Shutdown flours 0
: 20. Unit Asailability Factor                                   0                       44.7%             58.2%
0 0
: 21. Unit Capacity Factor (Using MDC Net 1                       0                       44.5%             53.1%
: 16. Gross Thermal Energy Generated (MWH) 0 3085927 35402838 17 Gross Electrical Energy Generated (MWH) 1058396 1203016/:
: 22. Unit Capacity Factor (Using DER Net)                       0                      42.1%            50.3%
0
: 23. Unit Forced Outage Rate                                     0                       18.0%             34.4%
: 18. Net Electrica! Energ> Generated (MWH) 0 1009335 11400975
: 19. Unit Senice Factor 0
44.7%
58.2%
: 20. Unit Asailability Factor 0
44.7%
58.2%
: 21. Unit Capacity Factor (Using MDC Net 1 0
44.5%
53.1%
0 42.1%
50.3%
: 22. Unit Capacity Factor (Using DER Net)
: 23. Unit Forced Outage Rate 0
18.0%
34.4%
: 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each :
: 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each :
continuing refueling outage
continuing refueling outage
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:       6/10/80
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
: 26. Units In Test Status (Prior to Commercial Operationi:                       Forecas:           Achies ed INITI AL CRITICALITY                                                                                   O INITI AL ELECTRICITY                                                             1/30/77 COslMERCl 4 L OPER ATION                                                         3/13/77 g y "*
6/10/80
: 26. Units In Test Status (Prior to Commercial Operationi:
Forecas:
Achies ed INITI AL CRITICALITY O
INITI AL ELECTRICITY 1/30/77 COslMERCl 4 L OPER ATION 3/13/77 g y "*
* g
* g
              .D e-r
.D e-r


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-302 LWIT FLCRP-3 DATE    5/5/80 COMPLETED BY       M. W. Culver.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-302 LWIT FLCRP-3 5/5/80 DATE COMPLETED BY M. W. Culver.
TELEPHONE (904)795-6486 MONTH       Ar>ril 1980 DAY       AVERAGE DAILY POWER LEVEL                         DA'l         AVERAGE DAILY POWER LEVEL (MWe-Net)                                                 iMWe-Net) 1                       0                                   g7                     0 2                       0                                     3                     0 3                       0                                 39     __
TELEPHONE (904)795-6486 MONTH Ar>ril 1980 DAY AVERAGE DAILY POWER LEVEL DA'l AVERAGE DAILY POWER LEVEL (MWe-Net) iMWe-Net) 1 0
0 4                       0                                 20                       0                           l
0 g7 2
      \         5                       0                                                           0 21 6
0 3
0                                  ,                        0 7                       0                                 23                       0                           I
0 3
  .            8                        0                                 24                       0 9                         0                                                           0 25 10                         0                                                           0 26 1I                         O 27                       0 12                         0                                 2S                       0 13                         0                                                           0 29 14                         0                                                           0 30 15                         0 3,
0 39 0
0 16 INSTRUCTIONS On this format. list the average dady unit power levelin MWe Net for each day in the reporting month. Compute to the nearest w. tole megawatt.
4 0
20 0
\\
5 0
0 21 0
0 6
7 0
23 0
I 8
0 24 0
9 0
0 25 10 0
0 26 1I O
0 27 12 0
2S 0
13 0
0 29 14 0
0 30 0
15 3,
16 0
INSTRUCTIONS On this format. list the average dady unit power levelin MWe Net for each day in the reporting month. Compute to the nearest w. tole megawatt.
(9/77)
(9/77)


                                                                                              -~             ..      - . _ _ ~           - . - . -       . . . .      -
-~
UNIT SilU1 DOWNS ANI) POWElt REI)UCIlONS                           DOCKEINO. 50-3-2 UNil N AME FLCRP-3 DAIE 5 /5 /80 COMPI.E1EI) ny MW Culver REPORI MONiil _ _ rril A
-. _ _ ~
1 El EPIIONE (904)795-6486 I.iterKee                 *
DOCKEINO. 50-3-2 UNIT SilU1 DOWNS ANI) POWElt REI)UCIlONS UNil N AME FLCRP-3 DAIE 5 /5 /80 A
                                    %          =3          h                              [",                                       Cause & ('or retfive Nn.           Date     g         3g         4   .g g s         Event     :o         8. ,g                              Atiinn in H
COMPI.E1EI) ny MW Culver
fE          5                Report rr   cfiG       $U                           Prevent itecurrente 3 if, =j
_ rril REPORI MONiil _
                                                                <                                    u O                                                                                       .
1 El EPIIONE (904)795-6486
80-9           800401-     S       719           C     4           N/A       ZZ     ZZZZZZ         Continuation of the refueling outage begun on 3/7/80.
=3 h
T R
I.iterKee
LD 25'e)
[",
Cause & ('or retfive
: 8.,g Atiinn in Nn.
Date g
3g 4
.g g s Event
:o Report rr cfiG
$U Prevent itecurrente fE 5
H 3 if, =j u
O 80-9 800401-S 719 C
4 N/A ZZ ZZZZZZ Continuation of the refueling outage begun on 3/7/80.
TR LD 25'e)
C3 y
C3 y
b 5 ...1
b 5
...1
[d r
[d r
I                       2                                                   3                                       4 F: l'orced       s   iteason:                                             Method:                                     Exhibit G - Instructions 5: Stheduled         A l quipment Failure (Explain)                       1 Manual                                   for Preparation of Data B Maintenance of Test                                 2 Manual Scrarn.                           Entry Sheets for 1.icensee C.ilefueling                                         3. Antomatic Scram.                         Event Iteport (i.Eit) File (NilRI G.
I 2
D Regulatory Restriction                             4-Ot her ( Explain)                         0161) 1:-Operator Training & l.icense I xamination F Administrative -                                                                         5 G Operational I.r ror (Explain)                                                                   Exhibit I . Same Source I'8/77)                   Il-Ot her ( E xplain )
3 4
F: l'orced s
iteason:
Method:
Exhibit G - Instructions 5: Stheduled A l quipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2 Manual Scrarn.
Entry Sheets for 1.icensee C.ilefueling
: 3. Antomatic Scram.
Event Iteport (i.Eit) File (NilRI G.
D Regulatory Restriction 4-Ot her ( Explain) 0161) 1:-Operator Training & l.icense I xamination F Administrative -
5 G Operational I.r ror (Explain)
Exhibit I. Same Source I'8/77)
Il-Ot her ( E xplain )


MONTHLY STATUS REPORT REFUELING INFORMATION RE0 VEST
MONTHLY STATUS REPORT REFUELING INFORMATION RE0 VEST 1.
: 1. Name of Facility:   Crystal River Unit 3
Name of Facility:
: 2. Scheduled date of next refueling shutdown:     Currently shut down
Crystal River Unit 3 2.
: 3. Scheduled date for restart following refueling: June, 1980
Scheduled date of next refueling shutdown:
: 4. Will refueling or resumption of operation thereafter require a technical specification. change or other license amendment? Yes. In general, changes to the CR #3 technical specifications will include:
Currently shut down 3.
: a. Moderator Temperature Coefficient (3.1.1.3) i             b. Control Rod Insertion Limits (3.1.3.6)
Scheduled date for restart following refueling: June, 1980 4.
: c. Control Rod Group Assignments (3.1.3.7)
Will refueling or resumption of operation thereafter require a technical specification. change or other license amendment?
: d. Axial Inhalance Limits (3.2.1)
Yes.
:              e. Refueling Boron Concentration (3.9.1)
In general, changes to the CR #3 technical specifications will include:
a.
Moderator Temperature Coefficient (3.1.1.3) i b.
Control Rod Insertion Limits (3.1.3.6) c.
Control Rod Group Assignments (3.1.3.7) d.
Axial Inhalance 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.
: 5. Scheduled date(s) for submitting proposed licensing action   and supporting information: April, 1980
5.
: 6. Important licensing considerations associated with refueling,     e.g.,
Scheduled date(s) for submitting proposed licensing action and supporting information:
new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes .in fuel design, or new operating procedures.
April, 1980 6.
Florida Power Corporation is presently discussing with the NRC staff our intent to request that the power level of CR #3 be raised from the 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 continue our discussions with the NRC in order to obtain the power upgrade during Cycle 3 operation.
Important licensing considerations associated with refueling, e.g.,
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool,
new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes.in fuel design, or new operating procedures.
: a. 177 assemblies
Florida Power Corporation is presently discussing with the NRC staff our intent to request that the power level of CR #3 be raised from the present level of 2452 MW (t) to the ultimate core power level of 2544 MW (t) as described in the CR #3 FSAR.
: b. 112 assemblies 4
FPC submitted, on February 28, 1979, our reload report justifying Cycle 2 operation of CR #3 at 2544 MW (t).
: 8. 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, i           a. Present storage capacity. - Pool A - 120 plus 8 failed fuel-assemblies.
On May 25, 1979, FPC modified its Cycle 2 reload report justifying continued operation of 2452 MW (t).
It is our intent to continue our discussions with the NRC in order to obtain the power upgrade during Cycle 3 operation.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a.
177 assemblies b.
112 assemblies 4
8.
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, i
a.
Present storage capacity. - Pool A - 120 plus 8 failed fuel-assemblies.
Pool B - 120 plus 8 failed fuel assemblies.
Pool B - 120 plus 8 failed fuel assemblies.
Simpson(MSRpt)DN89
Simpson(MSRpt)DN89


                ','          8.     (Continued)
8.
(Continued)
(,
(,
: b. Filed request on January 9, 1978 with NRC concerning expansion of
b.
                    ,/                     Pool A from 120 to 544 assemblies plus 6 failed fuel assemblies
Filed request on January 9, 1978 with NRC concerning expansion of
                ?/          -
,/
and expansion of Pool B from 120 to 609 assemblies. Expansion of I
Pool A from 120 to 544 assemblies plus 6 failed fuel assemblies and expansion of Pool B from 120 to 609 assemblies. Expansion of
Pool A is to occur after the refueling in March, 1980.         The       ,
?/
        ,                                  Pool B expansion will occur at a later refueling outage
I Pool A is to occur after the refueling in March, 1980.
                      -                    (approximately .1986) .
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 i
9.
The projected date of the last refueling that can be discharged to the spent fuel assuming the present licensed capacity.
1981-1982 i
i 4
i
i
;
4 i
(
(
I   ,
I
                  .f z
.f z
                                ,i
,i Simpson(MSRpt)Dh89
                                !.                                                                                  ,;
_}}
Simpson(MSRpt)Dh89
                                                                                                                . _}}

Latest revision as of 02:13, 2 January 2025

Monthly Operating Rept for Apr 1980
ML19309H519
Person / Time
Site: Crystal River 
Issue date: 05/05/1980
From: Culver M
FLORIDA POWER CORP.
To:
Shared Package
ML19309H518 List:
References
NUDOCS 8005130446
Download: ML19309H519 (5)
v • d • e


Text

_ _

8 005130s{No OPERATING DATA REPORT A

+

DOCKET NO. 50-302

)

DATE 5/5/80 CO)!PLETED BY MW Culver TELEPHONE (on6T 70s-6486 OPERATING STATUS

l. Unit Name:

Crystal River #3 N"8e5

~

2. Reporting Period:4/1/80 - 4/30/80 2452
3. Licensed 1 hermal Pow er (MWt ):

890

4. Nameplate Rating (Gross MWet:
5. Design Electrical Rating (Net MWel: 825 821
6. 51asimum Dependable Capacity (Gross MWet:

782

{

7. Maximum Dependable Capacity (Net MWet:

d

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Lesel To which Restricted.If Any (Net MWe):
10. Reasons For Restrictions. If Any:

A This Month Yr..t o.Dat e Cumularise I1. Hours in Reporting Period 714 94M 27479

12. Number Of Hours Reactor has Critical 0

1305.5 16455 8

13. Reactor Resene Shutdown Hours 0

0 1116.9

14. Hours Generator On.Line 0

1297.4 15997.6

15. Unit Reserve Shutdown flours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 3085927 35402838 17 Gross Electrical Energy Generated (MWH) 1058396 1203016/:

0

18. Net Electrica! Energ> Generated (MWH) 0 1009335 11400975
19. Unit Senice Factor 0

44.7%

58.2%

20. Unit Asailability Factor 0

44.7%

58.2%

21. Unit Capacity Factor (Using MDC Net 1 0

44.5%

53.1%

0 42.1%

50.3%

22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Outage Rate 0

18.0%

34.4%

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each :

continuing refueling outage

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

6/10/80

26. Units In Test Status (Prior to Commercial Operationi:

Forecas:

Achies ed INITI AL CRITICALITY O

INITI AL ELECTRICITY 1/30/77 COslMERCl 4 L OPER ATION 3/13/77 g y "*

  • g

.D e-r

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-302 LWIT FLCRP-3 5/5/80 DATE COMPLETED BY M. W. Culver.

TELEPHONE (904)795-6486 MONTH Ar>ril 1980 DAY AVERAGE DAILY POWER LEVEL DA'l AVERAGE DAILY POWER LEVEL (MWe-Net) iMWe-Net) 1 0

0 g7 2

0 3

0 3

0 39 0

4 0

20 0

\\

5 0

0 21 0

0 6

7 0

23 0

I 8

0 24 0

9 0

0 25 10 0

0 26 1I O

0 27 12 0

2S 0

13 0

0 29 14 0

0 30 0

15 3,

16 0

INSTRUCTIONS On this format. list the average dady unit power levelin MWe Net for each day in the reporting month. Compute to the nearest w. tole megawatt.

(9/77)

-~

-. _ _ ~

DOCKEINO. 50-3-2 UNIT SilU1 DOWNS ANI) POWElt REI)UCIlONS UNil N AME FLCRP-3 DAIE 5 /5 /80 A

COMPI.E1EI) ny MW Culver

_ rril REPORI MONiil _

1 El EPIIONE (904)795-6486

=3 h

I.iterKee

[",

Cause & ('or retfive

8.,g Atiinn in Nn.

Date g

3g 4

.g g s Event

o Report rr cfiG

$U Prevent itecurrente fE 5

H 3 if, =j u

O 80-9 800401-S 719 C

4 N/A ZZ ZZZZZZ Continuation of the refueling outage begun on 3/7/80.

TR LD 25'e)

C3 y

b 5

...1

[d r

I 2

3 4

F: l'orced s

iteason:

Method:

Exhibit G - Instructions 5: Stheduled A l quipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2 Manual Scrarn.

Entry Sheets for 1.icensee C.ilefueling

3. Antomatic Scram.

Event Iteport (i.Eit) File (NilRI G.

D Regulatory Restriction 4-Ot her ( Explain) 0161) 1:-Operator Training & l.icense I xamination F Administrative -

5 G Operational I.r ror (Explain)

Exhibit I. Same Source I'8/77)

Il-Ot her ( E xplain )

MONTHLY STATUS REPORT REFUELING INFORMATION RE0 VEST 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: June, 1980 4.

Will refueling or resumption of operation thereafter 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) i b.

Control Rod Insertion Limits (3.1.3.6) c.

Control Rod Group Assignments (3.1.3.7) d.

Axial Inhalance 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.

5.

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

April, 1980 6.

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

new or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes.in fuel design, or new operating procedures.

Florida Power Corporation is presently discussing with the NRC staff our intent to request that the power level of CR #3 be raised from the 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 continue our discussions with the NRC in order to obtain the power upgrade during Cycle 3 operation.

7.

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

177 assemblies b.

112 assemblies 4

8.

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, i

a.

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

Pool B - 120 plus 8 failed fuel assemblies.

Simpson(MSRpt)DN89

8.

(Continued)

(,

b.

Filed request on January 9, 1978 with NRC concerning expansion of

,/

Pool A from 120 to 544 assemblies plus 6 failed fuel assemblies and expansion of Pool B from 120 to 609 assemblies. Expansion of

?/

I Pool A is to occur after the refueling in 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

i 4

i

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,i Simpson(MSRpt)Dh89

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