ML19341A039: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:- - = _ -          .-.      .      .                      .-          -. _ .--  -.                  . _-
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                    ,                                        AVERAGE DAILY UNIT POWER LEVEL.                              .                                  .            .
AVERAGE DAILY UNIT POWER LEVEL.
DOCKETNO.             50-313                         .
DOCKETNO.
UNIT     ANO-1 DATE   1/15/81 S. Bremlett C0\lPLETED BY               1..
50-313 UNIT ANO-1 DATE 1/15/81 C0\\lPLETED BY 1.. S. Bremlett TELEPHONE (501) 968-5519 MONTH December.1980 DAY AVERAGE DAILY P0h'ER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) tMWe Neo.
TELEPHONE (501) 968-5519 MONTH             December.1980 DAY               AVERAGE DAILY P0h'ER LEVEL                             DAY     AVERAGE DAILY POWER LEVEL                                         -
3 588 i7 543~
(MWe Net)                                                   tMWe Neo .
4 540 is 543 3
3                         588                                         i7                   543~
560 39 544 4
4
554
:                          540                                       is 543 3                         560                                         39                   544
~
                                                                                                                                                                      ~
:o 544 s
4                          554                                        :o                   544 s                         546                                                             541 21 543 6                                           -
546 541 21 543 6
::                  541 7                         543                                         23                 540 1
541 7
8                          536                                        24                 401
543 23 540 8
                        ,                            26                                                           542 i
536 1
25 10     .
24 401 26 25 542 i
459                                         26                 543 ij                           539                                                             545 27 g,                         539                                         ,g                 536 13                         537                                         39                 534                                           .
10 459 26 543 ij 539 27 545 g,
14                         530                                         3o                 535 15                         542                                         3                 53?
539
16                         543 l
,g 536 13 537 39 534 14 530 3o 535 15 542 3
1 INSTRUCTI'ONS On this fntmat, list the average d:Sy unit piiwcr levelin MWe Net for each day in the reponmg month. Compute tu the nearest whole megawatt.
53?
      .                                                                                                                                                                      l (9/77 )
16 543 1
t 8102 sin $f __ -                              . _ _ - -
INSTRUCTI'ONS On this fntmat, list the average d:Sy unit piiwcr levelin MWe Net for each day in the reponmg month. Compute tu the nearest whole megawatt.
(9/77 )
t 8102 sin $f  


OPERATING DATA REPORT
OPERATING DATA REPORT
                                                                                                            ~ DOCKET NO.     50-313 DATE   l-Ab-di             !
~ DOCKET NO.
1 COMPLETED BY L. 5. dramlett TELEPHONE (bul) 906-2519 OPERATIC STATUS N "'
50-313 DATE l-Ab-di COMPLETED BY L. 5. dramlett TELEPHONE (bul) 906-2519 OPERATIC STATUS N "'
: 1. Unit Name:     Arkansas Nuclear One - Unit 1 i           '2. Reporting Period: December 1 - 31. 1980
Arkansas Nuclear One - Unit 1
: 3. Licensed Thermal Power (MWr):         2568                                                                                   -
: 1. Unit Name:
: 4. Narneplate Rating (Gross MWe): .        902.74
i
: 5. Design Electrical Rating (Net MWe):     850
'2. Reporting Period: December 1 - 31. 1980
: 3. Licensed Thermal Power (MWr):
2568 902.74
: 4. Narneplate Rating (Gross MWe):
850
: 5. Design Electrical Rating (Net MWe):
883
: 6. Maximum Dependable Capacity (Gross MWe):
: 6. Maximum Dependable Capacity (Gross MWe):
883 836 j             7. Maximum Dependable Capacity (Net MWe):
836 j
: 7. Maximum Dependable Capacity (Net MWe):
: 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:
None
None None
: 9. Power Level To Which Restricted,if Any (Net MWe):                         None 4          10. Reasons For Restrictions.lf Any:                   N/A This Montt                     Yr..to.Date           Cumulative 744.0                     8,784.0           52.915.0
: 9. Power Level To Which Restricted,if Any (Net MWe):
: 11. Hours in Reporting Period 732 .7                   5,651.8           35,790.3
N/A
: 12. Number Of Hours Reactor Was Critical 0                     647.6             4,895.0
: 10. Reasons For Restrictions.lf Any:
: 13. Reactor Resene Shutdon Hours 723.8                     5,574.5           35,045.0
4 This Montt Yr..to.Date Cumulative 744.0 8,784.0 52.915.0
: 14. Hours Generator On.Line 0                        20.8               817.5
: 11. Hours in Reporting Period 732.7 5,651.8 35,790.3
: 15. Unit Reserve Shutdown Hours 1,319,548.0                 12 ,9 11,172.0         84,173,216.0
: 12. Number Of Hours Reactor Was Critical 0
: 16. Gross Thermal Energy Generated (MWH)                                                                                      "
647.6 4,895.0
: 17. Gross Electrical Energy Generated (MWH) 406,920.0                   3,977,405.0 ,27,698,561.0 386 ,162.0                 3,781,602.0           26,415,639.0
: 13. Reactor Resene Shutdon Hours
: 18. Net Electrical Energy Generated (MWHb 97.3                         63.0               66.2
: 14. Hours Generator On.Line 723.8 5,574.5 35,045.0 0
20.8 817.5
: 15. Unit Reserve Shutdown Hours
: 16. Gross Thermal Energy Generated (MWH) 1,319,548.0 12,9 11,172.0 84,173,216.0 406,920.0 3,977,405.0,27,698,561.0
: 17. Gross Electrical Energy Generated (MWH) 386,162.0 3,781,602.0 26,415,639.0
: 18. Net Electrical Energy Generated (MWHb 97.3 63.0 66.2
: 19. Unit Service Factor
: 19. Unit Service Factor
: 20. Unit Availability Factor                                         97.3                         63.7               67.8 62.1                         51.5               59.7-
: 20. Unit Availability Factor 97.3 63.7 67.8 62.1 51.5 59.7-
: 21. Unit Capacity Factor (Using MDC Neti                                         ,
: 21. Unit Capacity Factor (Using MDC Neti
61.1                        50.6                58.7
: 22. Unit Capacity Factor (Using DER Net) 61.1 50.6 58.7 2
!          22. Unit Capacity Factor (Using DER Net)                                       .
25.3 17.3
2                          25.3                 17.3
: 23. Unit Forced Outage Rate
: 23. Unit Forced Outage Rate                                           _4.         ,
_4.
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, atS ! art, w               Each1:
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, atS ! art, w Each1:
d
d March 15,1981 l
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
March 15,1981 l
: 26. Units In Test Status (Prior to Commercial Operationi:
: 26. Units In Test Status (Prior to Commercial Operationi:                               Forecast               Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION
Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION
("/77 i
("/77 i


                                                                                                                                                                                                                      .e a                                                                                         t UNIT SiluTDOWNS AND POWER REDUC 110NS                     DOCKET NO. 50-313                                                                       'i UNIT NAhlE .ANO IINTT T                                                                   ,
. e t
DATE       1/15/81                                                     ,
a UNIT SiluTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-313
COMPLETED BY         L1 S. Brnmlett REPORT MONTil December TELEPflONE (5011 968-7519 "L
'i UNIT NAhlE.ANO IINTT T DATE 1/15/81 COMPLETED BY L1 S. Brnmlett REPORT MONTil December TELEPflONE (5011 968-7519 "L
No.          Date h
,$9 3
                                          ,$9 5g 3
Y-Licensee E r, h
                                                          @      js5 Y-       Licensee Event E r, gy        h 93 Cause & Curreceive Action to                                                               q' H
Cause & Curreceive No.
                                          $~             cE       .5gd:!       Reporise     ui o       gU                 Psevent Recurrence e                                     O c5
Date h
                                                                                                                                                                                                                  ?
5g js5 Event gy 93 Action to q'
a 80-13       801208       F. 20.2           11           3       None       llA     ZZZZZZ     The reactor tripped due to secondary                                                               ',
$~
plant load oscillations. The exact                                                                 i cause is unknown. Ilowever, the oscillations are believed to be due to a governor valve being close to its break open point.
cE
I                   2                                                         3                                 4 F: Forced           Reason:                                                   Method:                           Exhibis G . Inst:uctions S: Scheduled       A Equipment Failure (Explain)                               1-Manual                         for Prepasation of Daia 11 Maintenance of Test                                     7 4 fannal Scram.                 Entiy Sheets for I.ieensee C Refueling                                                 1 A tomatic Scram.               livent Report (Llilu File (NUREG.
.5gd:!
D Regulaiory Resisiciion                                   4 Othes (Explain)                 0161i E-Ope:ator Tsaining & License fixamination F.Administ rative                                                                         5 G. Ope s ailon.il l'e sor (lix plain t                                                       Exhibis 1 Same Source (9/77)                 Il Othes (Explain)
Reporise ui o gU Psevent Recurrence H
e O
c5
?
a 80-13 801208 F.
20.2 11 3
None llA ZZZZZZ The reactor tripped due to secondary plant load oscillations. The exact i
cause is unknown. Ilowever, the oscillations are believed to be due to a governor valve being close to its break open point.
I 2
3 4
F: Forced Reason:
Method:
Exhibis G. Inst:uctions S: Scheduled A Equipment Failure (Explain) 1-Manual for Prepasation of Daia 11 Maintenance of Test 7 4 fannal Scram.
Entiy Sheets for I.ieensee C Refueling 1 A tomatic Scram.
livent Report (Llilu File (NUREG.
D Regulaiory Resisiciion 4 Othes (Explain) 0161i E-Ope:ator Tsaining & License fixamination F.Administ rative 5
G. Ope s ailon.il l'e sor (lix plain t Exhibis 1 Same Source (9/77)
Il Othes (Explain)


          .                                                              DATE: January. 1981
DATE:
* REFUELING INFORMATION l.. Name of facility. Arkansas Nuclear One - Unit 1                                 l
January. 1981 REFUELING INFORMATION l..
: 2. Scheduled date for next refueling shutdown.       1/2/81(Shutdown)
Name of facility.
: 3. Scheduled date for restart following refueling.       3/15/81
Arkansas Nuclear One - Unit 1 2.
: 4. Will refueling or resumption of operation thereaf ter require a                       j technical specification change or other license amendment?                           ;
Scheduled date for next refueling shutdown.
1/2/81(Shutdown) 3.
Scheduled date for restart following refueling.
3/15/81 4.
Will refueling or resumption of operation thereaf ter require a j
technical specification change or other license amendment?
If answer is yes, what, in general, will these be?
If answer is yes, what, in general, will these be?
I If answer is no, has the reload fuel design' aui core configuration been reviewed by your Plant Safety Review Gm=ittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?                                           -
If answer is no, has the reload fuel design' aui core configuration been reviewed by your Plant Safety Review Gm=ittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes. Reload recort and associated croocsed Technical Soecification chances. Also, the safety analysis of four demonstration high burn-uo assemblies will be provided.
Yes.
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information. Partial submittal 10/31/80.         Comolete by 2/1/81
Reload recort and associated croocsed Technical Soecification chances.
: 6. Important licensing considerations associated with refueling, e.g. ,
Also, the safety analysis of four demonstration high burn-uo assemblies will be provided.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information. Partial submittal 10/31/80.
Comolete by 2/1/81 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or ' supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
new or different fuel design or ' supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Will reload 68 fresh fuel assemblies and coerate for acoroximatelv 16 mon ths. Four of which will be high burn-uo test assemblies.
Will reload 68 fresh fuel assemblies and coerate for acoroximatelv 16 mon ths.
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a)           177             b)     176
Four of which will be high burn-uo test assemblies.
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested er is planned, in number cf fuel assemblies.
7.
;                present         590               increase size by           0
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 176 8.
: 9. The projected date of the last refueling that can be discharged ~
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested er is planned, in number cf fuel assemblies.
present 590 increase size by 0
9.
The projected date of the last refueling that can be discharged ~
to the spent fuel pool assuming the present licensed capacity.
to the spent fuel pool assuming the present licensed capacity.
DATE:     1986 l
l DATE:
l
1986 l


NRC MONTHLY OPERATING REPORT OPERATING  
NRC MONTHLY OPERATING REPORT OPERATING  


==SUMMARY==
==SUMMARY==
  - DECEMBER 1980 UNIT I The unit began the month at about 93% full power with power limited by the pressure differential (level) problem on "A" OTSG. On 12-1-80 the "D" reactor coolant pump was manually secured because of seal cavity pressure problems. Therefore, power operation was limited to
  - DECEMBER 1980 UNIT I The unit began the month at about 93% full power with power limited by the pressure differential (level) problem on "A" OTSG. On 12-1-80 the "D" reactor coolant pump was manually secured because of seal cavity pressure problems. Therefore, power operation was limited to three pumps for the remainder of the month. On 12-8-80 the reactor tripped on 9/ Flow /A$.
            . three pumps for the remainder of the month. On 12-8-80 the reactor tripped on 9/ Flow /A$. This was caused by secondary load oscillations which were believed to be caused from a governor valve being close           ,
This was caused by secondary load oscillations which were believed to be caused from a governor valve being close to its break open point. On 12-24-80 power was reduced about 15% at the request of the system dispatcher when a 500 KV transmission line was lost. The unit operated the remainder of the month with preparations being made for the refueling shutdown in January.
to its break open point. On 12-24-80 power was reduced about 15% at the request of the system dispatcher when a 500 KV transmission line was lost. The unit operated the remainder of the month with preparations being made for the refueling shutdown in January.
9 1
9 1
1 l
1 l
l
.}}
.}}

Latest revision as of 17:38, 24 December 2024

Monthly Operating Rept for Dec 1980
ML19341A039
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 01/15/1981
From: Bramlett L
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19341A036 List:
References
NUDOCS 8101210494
Download: ML19341A039 (5)


Text

- - = _ -

AVERAGE DAILY UNIT POWER LEVEL.

DOCKETNO.

50-313 UNIT ANO-1 DATE 1/15/81 C0\\lPLETED BY 1.. S. Bremlett TELEPHONE (501) 968-5519 MONTH December.1980 DAY AVERAGE DAILY P0h'ER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) tMWe Neo.

3 588 i7 543~

4 540 is 543 3

560 39 544 4

554

~

o 544 s

546 541 21 543 6

541 7

543 23 540 8

536 1

24 401 26 25 542 i

10 459 26 543 ij 539 27 545 g,

539

,g 536 13 537 39 534 14 530 3o 535 15 542 3

53?

16 543 1

INSTRUCTI'ONS On this fntmat, list the average d:Sy unit piiwcr levelin MWe Net for each day in the reponmg month. Compute tu the nearest whole megawatt.

(9/77 )

t 8102 sin $f

OPERATING DATA REPORT

~ DOCKET NO.

50-313 DATE l-Ab-di COMPLETED BY L. 5. dramlett TELEPHONE (bul) 906-2519 OPERATIC STATUS N "'

Arkansas Nuclear One - Unit 1

1. Unit Name:

i

'2. Reporting Period: December 1 - 31. 1980

3. Licensed Thermal Power (MWr):

2568 902.74

4. Narneplate Rating (Gross MWe):

850

5. Design Electrical Rating (Net MWe):

883

6. Maximum Dependable Capacity (Gross MWe):

836 j

7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

None None

9. Power Level To Which Restricted,if Any (Net MWe):

N/A

10. Reasons For Restrictions.lf Any:

4 This Montt Yr..to.Date Cumulative 744.0 8,784.0 52.915.0

11. Hours in Reporting Period 732.7 5,651.8 35,790.3
12. Number Of Hours Reactor Was Critical 0

647.6 4,895.0

13. Reactor Resene Shutdon Hours
14. Hours Generator On.Line 723.8 5,574.5 35,045.0 0

20.8 817.5

15. Unit Reserve Shutdown Hours
16. Gross Thermal Energy Generated (MWH) 1,319,548.0 12,9 11,172.0 84,173,216.0 406,920.0 3,977,405.0,27,698,561.0
17. Gross Electrical Energy Generated (MWH) 386,162.0 3,781,602.0 26,415,639.0
18. Net Electrical Energy Generated (MWHb 97.3 63.0 66.2
19. Unit Service Factor
20. Unit Availability Factor 97.3 63.7 67.8 62.1 51.5 59.7-
21. Unit Capacity Factor (Using MDC Neti
22. Unit Capacity Factor (Using DER Net) 61.1 50.6 58.7 2

25.3 17.3

23. Unit Forced Outage Rate

_4.

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, atS ! art, w Each1:

d March 15,1981 l

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units In Test Status (Prior to Commercial Operationi:

Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION

("/77 i

. e t

a UNIT SiluTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-313

'i UNIT NAhlE.ANO IINTT T DATE 1/15/81 COMPLETED BY L1 S. Brnmlett REPORT MONTil December TELEPflONE (5011 968-7519 "L

,$9 3

Y-Licensee E r, h

Cause & Curreceive No.

Date h

5g js5 Event gy 93 Action to q'

$~

cE

.5gd:!

Reporise ui o gU Psevent Recurrence H

e O

c5

?

a 80-13 801208 F.

20.2 11 3

None llA ZZZZZZ The reactor tripped due to secondary plant load oscillations. The exact i

cause is unknown. Ilowever, the oscillations are believed to be due to a governor valve being close to its break open point.

I 2

3 4

F: Forced Reason:

Method:

Exhibis G. Inst:uctions S: Scheduled A Equipment Failure (Explain) 1-Manual for Prepasation of Daia 11 Maintenance of Test 7 4 fannal Scram.

Entiy Sheets for I.ieensee C Refueling 1 A tomatic Scram.

livent Report (Llilu File (NUREG.

D Regulaiory Resisiciion 4 Othes (Explain) 0161i E-Ope:ator Tsaining & License fixamination F.Administ rative 5

G. Ope s ailon.il l'e sor (lix plain t Exhibis 1 Same Source (9/77)

Il Othes (Explain)

DATE:

January. 1981 REFUELING INFORMATION l..

Name of facility.

Arkansas Nuclear One - Unit 1 2.

Scheduled date for next refueling shutdown.

1/2/81(Shutdown) 3.

Scheduled date for restart following refueling.

3/15/81 4.

Will refueling or resumption of operation thereaf ter require a j

technical specification change or other license amendment?

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design' aui core configuration been reviewed by your Plant Safety Review Gm=ittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes.

Reload recort and associated croocsed Technical Soecification chances.

Also, the safety analysis of four demonstration high burn-uo assemblies will be provided.

5.

Scheduled date(s) for submitting proposed licensing action and supporting information. Partial submittal 10/31/80.

Comolete by 2/1/81 6.

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

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

Will reload 68 fresh fuel assemblies and coerate for acoroximatelv 16 mon ths.

Four of which will be high burn-uo test assemblies.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 177 b) 176 8.

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

present 590 increase size by 0

9.

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

to the spent fuel pool assuming the present licensed capacity.

l DATE:

1986 l

NRC MONTHLY OPERATING REPORT OPERATING

SUMMARY

- DECEMBER 1980 UNIT I The unit began the month at about 93% full power with power limited by the pressure differential (level) problem on "A" OTSG. On 12-1-80 the "D" reactor coolant pump was manually secured because of seal cavity pressure problems. Therefore, power operation was limited to three pumps for the remainder of the month. On 12-8-80 the reactor tripped on 9/ Flow /A$.

This was caused by secondary load oscillations which were believed to be caused from a governor valve being close to its break open point. On 12-24-80 power was reduced about 15% at the request of the system dispatcher when a 500 KV transmission line was lost. The unit operated the remainder of the month with preparations being made for the refueling shutdown in January.

9 1

1 l

.