ML20039A851: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 19: Line 19:
{{#Wiki_filter:,
{{#Wiki_filter:,
_ u.
_ u.
t       :                                                                                                                                                                                  j OPER ATING DATA REPORT DOCKET NO. 050-0331 DATE December 14, 1983 Van Sickel COMPLETED BY _J.
t j
TELEPl!ONE 319-851-5611 OPER ATING STATUS Notes
OPER ATING DATA REPORT 050-0331 DOCKET NO.
                . l. Unit Name:       Duane Arnold Enerav Center                                                                                                               ,
DATE December 14, 1983 COMPLETED BY
: 2. Rep'orting Period:       November,1981 1000                                                                                                                 ~
_J. Van Sickel TELEPl!ONE 319-851-5611 OPER ATING STATUS Notes
. l. Unit Name:
Duane Arnold Enerav Center
: 2. Rep'orting Period:
November,1981 1000
~
: 3. Licensed Thermal Power (MWt):
: 3. Licensed Thermal Power (MWt):
              *4. Nameplate Rating (Gross MWe): -565 (Turbine Rating)
*4. Nameplate Rating (Gross MWe): -565 (Turbine Rating)
: 5. Design Electrical Rating (Net MWe): W
: 5. Design Electrical Rating (Net MWe): W
: 6. Maximum Dependable Capacity (Gross MWe): 645                                                                                                                             "
: 6. Maximum Dependable Capacity (Gross MWe): 645
l
: 7. Maximum Dependable Capacity (Net MWe):
: 7. Maximum Dependable Capacity (Net MWe):           515
515
              . 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:
I l
: 9. Power Level To Which Restricted,if Any (Net MWe):
: 9. Power Level To Which Restricted,if Any (Net MWe):
: 10. Reasons For Restrictions.If Any:
: 10. Reasons For Restrictions.If Any:
This Month           Yr to.Date               Cumulative l             11. Hours In Reporting Pedod                                   790                   8.016                             59.880 .
This Month Yr to.Date Cumulative l
: 12. Number Of Hours Reactor Was Critical                       720                   5,581.5                           42,750.2
: 11. Hours In Reporting Pedod 790 8.016 59.880
: 13. Reactor Resene Shutdown Hours                                 0                       0                                                                 0
: 12. Number Of Hours Reactor Was Critical 720 5,581.5 42,750.2
            '14. Hours Generator On-Line                                     720                   5,400.6                           41,677.6
: 13. Reactor Resene Shutdown Hours 0
: 15. Unit Reserve Shutdown Hours                                   0                       0                                                                   0.
0 0
16.' Gross Thermal Energy Generated (MWH)                 691.361             6,501,630                 52,500,268                                                         .
'14. Hours Generator On-Line 720 5,400.6 41,677.6
: 17. Gross Electrical Energy Generated (MWH)               228,252     ,_,
: 15. Unit Reserve Shutdown Hours 0
2,191,976                 17,594,663
0 0.
: 18. Net Electrical Energy Generated.(MWH) 211,o66             2,051,618                 16,463,656 l
16.' Gross Thermal Energy Generated (MWH) 691.361 6,501,630 52,500,268
: 19. Unit Sen-ice Factor                                         100.0%                 67.4%                                                         69.6%
: 17. Gross Electrical Energy Generated (MWH) 228,252 2,191,976 17,594,663 l
: 20. Unit Availability Factor                         ,          100.0%                   67.4%                                                         69.6%
: 18. Net Electrical Energy Generated.(MWH) 211,o66 2,051,618 16,463,656
: 21. Unit Capacity Factor (Using MDC Net) -                        57.1%
: 19. Unit Sen-ice Factor 100.0%
* 49.7%                                                        53.4%
67.4%
69.6%
: 20. Unit Availability Factor 100.0%
67.4%
69.6%
l
l
: 22. Unit Capacity Factor (Using DER Net)                         54.7%                 47.6%                                                         51.1%
: 21. Unit Capacity Factor (Using MDC Net) -
57.1%
* 49.7%
53.4%
54.7%
47.6%
51.1%
[
[
!            23. Unit Forced '         e Rate -                   .
: 22. Unit Capacity Factor (Using DER Net)
0.0%                   4.0%                                                         17.3%
: 23. Unit Forced '
: 24. Shutdowns Sene       .ed Over Next 6 Months (Type. Date.and Duration of Each):               ..
e Rate -
0.0%
4.0%
17.3%
: 24. Shutdowns Sene
.ed Over Next 6 Months (Type. Date.and Duration of Each):
: 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:
;
* Turbine Rating:
* Turbine Rating:             565.7 MWe l
565.7 MWe l
Generator Rating:             663.5 (MVA) x .90 (Power Factor) = 597 MWe                               .,
Generator Rating:
j        8112210378 811214"                                                                               .
663.5 (MVA) x.90 (Power Factor) = 597 MWe j
(       PDR ADOCK 05000331-                                                                                     '
8112210378 811214"
R PDR                                                                                                        - (9/77)
(
_._.m_____ _ _ _ . _ _ _ . _ . - _ . - _ _ _ _ _ _
PDR ADOCK 05000331-
- (9/77)
R PDR
..m


fs                                                                                                                         ,
fs AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 Duane Arnold UNIT rnnenu ennter DATE -December 14, 1981 COMPLETED BY
                                        ,                                    AVERAGE DAILY UNIT POWER LEVEL               ,
.1 Van Sirkel_
DOCKET NO. 050-0331 Duane Arnold UNIT rnnenu ennter DATE -December 14, 1981 COMPLETED BY   .1 Van Sirkel_
ILEPHONE -319-851-5611 MONTH November; 1981
ILEPHONE -319-851-5611 MONTH       November; 1981
~
                                                                        ~
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
DAY       AVERAGE DAILY POWER LEVEL                                                   DAY AVERAGE DAILY POWER LEVEL
(MWe-Net) 1 219 c
  *                                            (MWe-Net)                                                   .
17 331-2 235 326' ig 3
(MWe-Net)
7A?
* c 219 1
19 322 4
17             331-2                         235                                                     ig            326' 3                         7A?
250 20 296 334 290 5
19             322 4                         250                                                     20           296 5   .
21 6
                                          .      334                                                                    290 21 6                       "316 '                                                   22            275-7                         32-1 23             3d9 8                         323                                                                   279 24 9                         329'                                                                   264                           -
"316 '
25 10                           324                                                                     252 26
275-22 7
                ' 11                           197                                                                     254-27      .
32-1 3d9 23 8
12                            325                                                                   253 28 13                           323                                                                   255 29 j4                         -326                                                     30             255 15                           329 33 16                           177 INS 1 RUCTIONS On this format, list the average daily unit power levelin MWe-Net for each day in the reporting inonth. Compute to the nearest whole rnegawatt.
323 279 24 9
2                                                                                                                               ,
329' 25 264 10 324 252 26
(9/77l
' 11 197 27 254-325 253 12 28 13 323 255 29 j4
                                                    ,            , , , - , .    % % ..,--- e - - <-- =
-326 30 255 15 329 33 16 177 INS 1 RUCTIONS On this format, list the average daily unit power levelin MWe-Net for each day in the reporting inonth. Compute to the nearest whole rnegawatt.
2 (9/77l
..,--- e - - <-- =


                                                              -  - -.w         - u -       -          -n-             -      s .~             ~.          .        ..
-.w u -
-n-s
.~
~.
e s
e s
                                                                                                =
=
O                   j M m. .
O j
* ng   M                                                                                                                                    ,
M m..
                                            =,
M ng
=,
o r Co n.
o r Co n.
C_ C.
C_ C.
O C.
O C.
U u
U c
c G
u G
l4 NOMMCOM>M                                                                                             Type l
l4 NOMMCOM>M
          =, b b N b k.N                 - c RC O o 3      c.s
=, b b N b k.N R Type l "3 - c c.s a a.u.c.-C
                      ~  n,
- o 3 n, M
                        *  = aMC a.u.c.-
~ * = C C 3 E F E ;r gt.3 O
                                    "3 C 3
=s a
        - '      E F E ;r gt .3
m E.' G' :~ 2 5' u s Du.rau.on
                =s a
-m un
m E.' G' :~-m
.g _;; a qq m o.,.
          . .                    2 5' unus                                                                  Du.rau.on
(Hours) n a
        .g _;; a qq                   m n o., .
E. m T ". x -
a                                                                    (Hours)
m cu u
E.                               m u m T ". x -
non ~ **
        %.      p  non =M_    ~ ** cu *C n 65 =. H5            a  n                                                                                                                                              >
* C p
m        R* -n.       --                                                                    Reason 3 x
=M_
e.;ac              m u
H5 n 65 =.
              'u_       .
R* n.
: u.     e.
Reason 3 a n
                        .                  u                                                                Methad of
-m
                ~-
'u_
                  --    M                v 5'                                                               Shutting                                       C                            '
e.; c x
p                                                                                                                                 '*
m a
Down Reactor 3                                       H E" -                                                                                                                               m 5'                                                                                                                 m               C
u u.
                        ".                                                                                                                  m ao               H c
e.
m'
Methad of
                                                                                                            'M a m r
-u
                                                                                                                      -.                   O               O O
~-
                                                                                                              * <R
5' M
                                                                                                              ~3                            N                                            <
C Shutting v
H
p Down Reactor 3 H
                                                                                                              ~3o
E" -
m 5'
m m
C ao H
c
'M r
O O
m' a m -.
~3 <R N
O 2:
~
~3o H
~M w
*t n-m v2
>2 d
O
=
v O
O PYY~K..
System x
O>rr ii.*c u u,"
Code 4 m
a y
3 =o O'
-: aca x
m a O E. M,.
m2m
.s mo
* n n.,
Component c
n w u o
: e. n a Code 5 e
O5*
co 3
~
~
                                                                                                                  ~Mn-                    w                2:
O a
m
2m u
                                                                                                              *t                          :v                                          .
A o
2                >
**J l')
d                2 O
' O 4%
                                                                                                                                              =              v PYY~K. .                                                                                                      O              O O>rr System                        <
m ommmm n-u C
* x m
c m v c A
ii.*c    3u=o  u ,"                                                              Code 4                        a              y O'
- < n.
                              -: aca a O E. M, .                                                                                  ..              m              x m
.a s -, ~ ts.
m2m                                                                                                            .s              o n* n n.,                                                                        Component                                      c wu                                                                                                        -
8>N e r 2 n
e              o
ev =.
: e. n a                                                                            Code 5                      co              3 O5*  a                                                                                                        ~              O 2
~ ~
m u                            A                                                                                           o
* 3 7.
                                                                                                              **J                           'O m           .
mH
ommmm       C                                                                  n-l')
-n m m HY E
u c                 4%
p _v -
mv              c A
p1 zQ
                              - <nsn.
=g>o g a
                              .a       -, ~evts.
?EE-age
                            ~~
~
                                                =.                                                            8>N                       e m m HY r 2                                 .
n-up o
p *"_v3 7.
204.2 c,
E
-e E s-
                                                                                                              -n p1     %                mH
"c3 M M M M.O m
              ~                  n- up                                                                      age                      =g>o             zQ g
n Q
a                  ?EE-
=
: E s-c, "c3 o
c s.
204.2
3
            -e                         m                                                                      n      Q                  M M M M.O
~
              =                       c g~ s. ~                                                             3 G                 F                                                                           n tn                 m             c                                                             a       n W ,.C9 n                                                                                               W G C C O w = D c U1 4                  ""' o: o -E' sa                                                        '                                  @            7 m O
G F
: c.                 *T13 CNn " a                                                                                                       *C t 3 s
g~
                                                                            .                                                            8
n tn m
              #*                              u O                                                                                                      Co G 3 m O W 3 7               w 2                                                                                                     w           t d C                                                                                                      i     V 5       -5 .w
c a
                                                                                                                                        @      ".      3 M                                                                                                     @ n w O m                                                                                                     w X4           "
n W,.C9 n W G C C O
Qe W @        =   1 a
""' o: o -E' 7
wM e                                                 D3                    .
m O D c U1 w
                                                                                                                                        .            Co m                         t9-p*1
=
                                                                                                                                                      'C 5<
4 sa c.
                                                                                                                ,-          .                            n d
*T13 " a Co G 3 m O 8
                                                                                                                                                        ,"s
*C t 3
* A.A     m--e                                           . -  ,
s CN u
                                                                        . ._, .        . ^-
O n W 3 7
w 2
w t d.w i
V 5
-5 C
3 M
@ n w O m
w X4 Q
W 1
=
e a
wM D3 e
Co m t
p*1 9-
'C 5<
n d
,"s A.A m--e
. ^-


Docket No   U50-0331
Docket No U50-0331 Unit Duane Arnold Energd Date December 14, 1981 REFUELING INFCRf!ATION Completed by _J. VanfSicke
                -                                                                  Unit Duane Arnold Energd
* Telephone 319-851-56TI 1.
    '                                                                                Date December 14, 1981 REFUELING INFCRf!ATION Completed by _J. VanfSicke
Name of facility.
* Telephone 319-851-56TI
A.
: 1. Name of facility.                                                                 ,
Duane Arnold Energy Center 2.
A. Duane Arnold Energy Center
Scheduled date for next refueling shutdown.
: 2. Scheduled date for next refueling shutdown.
A:
A:   Fall , 1982
Fall, 1982
                  '3. Scheduled date for restart following refueling.                                      .
'3.
A. Unknown                                   .
Scheduled date for restart following refueling.
          .        4. Will refueling or resumption of operation thereafter require a technical specification change or other license amend, ment?
A.
A. Yes. New'MAPI.HGR. tables will have to be included in Technical Specifications.
Unknown 4.
V                                                                                                 .
Will refueling or resumption of operation thereafter require a technical specification change or other license amend, ment?
            ,      5. Scheduled date(s) for submitting proposed licensing action and
A.
              .        supporting information.
Yes.
                      !A. Unknown at this time.
New'MAPI.HGR. tables will have to be included in Technical Specifications.
6.' Important-licensing considerations associated with refueling,     e.g.,
V 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
!A.
Unknown at this time.
6.'
Important-licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or per-formance analysis methods, significant changes in' fuel design, new operating procedures.
new or different fuel design or supplier, unreviewed design or per-formance analysis methods, significant changes in' fuel design, new operating procedures.
~
~
A. New fuel assemblies to be placed in the reacto'r will be more highly enriched than those' currently in use.      ,                          .
A.
: 7. 'The n' umber of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.
New fuel assemblies to be placed in the reacto'r will be more highly enriched than those' currently in use.
A. a)   368   b),448
'The n' umber of fuel assemblics (a) in the core and (b) in the spent 7.
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested
fuel storage pool.
              .        or is planned, in number of fuel assemblies.
A.
A. 2050
a) 368 b),448 8.
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capncity.
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. 1998 o
A.
2050 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capncity.
A.
1998 o
9 e
9 e


' ~         ~       ~~                         ~               ~   ~ ~
' ~
Docket No -   050-0331 Unit Dunno Arnold Fuerav fontti
~
                                                                            .                Date December 14, 1981" MAJOR SAFETY RELATED MAINTENANCE                                 by  J  an    ckel f0e p neL     g_g   g
~~
  .DATE                   SYSTEM                         COMPONENT                               DESCRIPTION 11-2-81     CRD Hydraulic             V-17-111                             Replaced valve c11-4     Containment               SV-8116B                             Replaced coil' Atmo. spheric Control 11-6   River _ Water Supply     CV-4909                             Replaced SV-4909 11-6-81     Containment               SV-8103B                   ,        Replaced coil Atmospheric Control 11-6-81     Containment               AN 8181A                             Replaced flow controller Atmospheric Control 11-21-81   Containment               AN 8181A                             Installed new chemicals Atmospheric Control                                                                   .
~
a b
~
4 e
~
                                                                ?
~
W 4 a
Docket No -
                                                                                                                  ~,
050-0331 Unit Dunno Arnold Fuerav fontti Date December 14, 1981" f0 by J
an ckel MAJOR SAFETY RELATED MAINTENANCE e p neL g_g g
.DATE SYSTEM COMPONENT DESCRIPTION 11-2-81 CRD Hydraulic V-17-111 Replaced valve c11-4 Containment SV-8116B Replaced coil' Atmo. spheric Control 11-6 River _ Water Supply CV-4909 Replaced SV-4909 11-6-81 Containment SV-8103B Replaced coil Atmospheric Control 11-6-81 Containment AN 8181A Replaced flow controller Atmospheric Control 11-21-81 Containment AN 8181A Installed new chemicals Atmospheric Control a
b 4
e
?
W 4
a
~,


Docket No. 050-0331' Unit Duane Arnold Energy Center Date December 14, 1981 Completed by J. Van Sickel Telephone 319-851'-5611 NARRATIVE  
Docket No. 050-0331' Unit Duane Arnold Energy Center Date December 14, 1981 Completed by J. Van Sickel Telephone 319-851'-5611 NARRATIVE  


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE 11-1         . At the beginning of the report period the plant was operating at 237 MWe.
OF OPERATING EXPERIENCE 11-1
. At the beginning of the report period the plant was operating at 237 MWe.
The plant was being operated at reduced power levels due-to lack of system
The plant was being operated at reduced power levels due-to lack of system
                    . demand.
. demand.
11-4         Control rod group 36 was withdrawn to position 48. A power increase 'was begun.
11-4 Control rod group 36 was withdrawn to position 48. A power increase 'was begun.
11-5.         The plant was operating at 341 MWe, 11-6.       'During normal operation while performing an operational inspection, a leak was discovered in the reactor water cleanup system outboard of both isolation       '
11-5.
valves.
The plant was operating at 341 MWe, 11-6.
R0 Report 81-041 11-14       -During a weekly control rod exercise surveillance test, an overtravel alarm was received for control rod 26-15, indicating the CRD had uncoupled.
'During normal operation while performing an operational inspection, a leak was discovered in the reactor water cleanup system outboard of both isolation valves.
R0 Report 81-042 11-17         During power operation, the instrument line drain valve, V-18-20, for "B" scram instrument volume level switch LS-1861 was found locked open.
R0 Report 81-041 11-14
i R0 Report 81-039 11-18         During normal operation, it was found that reactor water cleanup system return isolation valve M0V 2740 would not cycle.
-During a weekly control rod exercise surveillance test, an overtravel alarm was received for control rod 26-15, indicating the CRD had uncoupled.
R0 Report 81-040 11-24         During normal operation secondary containment-isolation' damper IV-AD-15B began cycling and was removed from service.
R0 Report 81-042 11-17 During power operation, the instrument line drain valve, V-18-20, for "B" scram instrument volume level switch LS-1861 was found locked open.
R0 Report Pending 11-24         While testing the "A" control building standby filter unit, isolation. damper                                         _
i R0 Report 81-039 11-18 During normal operation, it was found that reactor water cleanup system return isolation valve M0V 2740 would not cycle.
IV-AD-31A was found inoperable.
R0 Report 81-040 11-24 During normal operation secondary containment-isolation' damper IV-AD-15B began cycling and was removed from service.
R0 Report Pending 11-24 While testing the "A" control building standby filter unit, isolation. damper IV-AD-31A was found inoperable.
R0 Report Pending
R0 Report Pending


Docket No. 050-0331
Docket No. 050-0331 Unit Duane Arnold Energy Center Date December 14, 1981 Completed by J. Van Sickel Telephone 319-851-5611 1
    ;                                                    Unit Duane Arnold Energy Center Date December 14, 1981 Completed by J. Van Sickel     ,
NARRATIVE  
Telephone 319-851-5611         1 NARRATIVE  


==SUMMARY==
==SUMMARY==

Latest revision as of 00:33, 20 December 2024

Monthly Operating Rept for Nov 1981
ML20039A851
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 12/14/1981
From: Van Sickel J
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20039A849 List:
References
NUDOCS 8112210378
Download: ML20039A851 (7)


Text

,

_ u.

t j

OPER ATING DATA REPORT 050-0331 DOCKET NO.

DATE December 14, 1983 COMPLETED BY

_J. Van Sickel TELEPl!ONE 319-851-5611 OPER ATING STATUS Notes

. l. Unit Name:

Duane Arnold Enerav Center

2. Rep'orting Period:

November,1981 1000

~

3. Licensed Thermal Power (MWt):
  • 4. Nameplate Rating (Gross MWe): -565 (Turbine Rating)
5. Design Electrical Rating (Net MWe): W
6. Maximum Dependable Capacity (Gross MWe): 645
7. Maximum Dependable Capacity (Net MWe):

515

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

9. Power Level To Which Restricted,if Any (Net MWe):
10. Reasons For Restrictions.If Any:

This Month Yr to.Date Cumulative l

11. Hours In Reporting Pedod 790 8.016 59.880
12. Number Of Hours Reactor Was Critical 720 5,581.5 42,750.2
13. Reactor Resene Shutdown Hours 0

0 0

'14. Hours Generator On-Line 720 5,400.6 41,677.6

15. Unit Reserve Shutdown Hours 0

0 0.

16.' Gross Thermal Energy Generated (MWH) 691.361 6,501,630 52,500,268

17. Gross Electrical Energy Generated (MWH) 228,252 2,191,976 17,594,663 l
18. Net Electrical Energy Generated.(MWH) 211,o66 2,051,618 16,463,656
19. Unit Sen-ice Factor 100.0%

67.4%

69.6%

20. Unit Availability Factor 100.0%

67.4%

69.6%

l

21. Unit Capacity Factor (Using MDC Net) -

57.1%

  • 49.7%

53.4%

54.7%

47.6%

51.1%

[

22. Unit Capacity Factor (Using DER Net)
23. Unit Forced '

e Rate -

0.0%

4.0%

17.3%

24. Shutdowns Sene

.ed Over Next 6 Months (Type. Date.and Duration of Each):

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

565.7 MWe l

Generator Rating:

663.5 (MVA) x.90 (Power Factor) = 597 MWe j

8112210378 811214"

(

PDR ADOCK 05000331-

- (9/77)

R PDR

..m

fs AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 Duane Arnold UNIT rnnenu ennter DATE -December 14, 1981 COMPLETED BY

.1 Van Sirkel_

ILEPHONE -319-851-5611 MONTH November; 1981

~

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 219 c

17 331-2 235 326' ig 3

7A?

19 322 4

250 20 296 334 290 5

21 6

"316 '

275-22 7

32-1 3d9 23 8

323 279 24 9

329' 25 264 10 324 252 26

' 11 197 27 254-325 253 12 28 13 323 255 29 j4

-326 30 255 15 329 33 16 177 INS 1 RUCTIONS On this format, list the average daily unit power levelin MWe-Net for each day in the reporting inonth. Compute to the nearest whole rnegawatt.

2 (9/77l

..,--- e - - <-- =

-.w u -

-n-s

.~

~.

e s

=

O j

M m..

M ng

=,

o r Co n.

C_ C.

O C.

U c

u G

l4 NOMMCOM>M

=, b b N b k.N R Type l "3 - c c.s a a.u.c.-C

- o 3 n, M

~ * = C C 3 E F E ;r gt.3 O

=s a

m E.' G' :~ 2 5' u s Du.rau.on

-m un

.g _;; a qq m o.,.

(Hours) n a

E. m T ". x -

m cu u

non ~ **

  • C p

=M_

H5 n 65 =.

R* n.

Reason 3 a n

-m

'u_

e.; c x

m a

u u.

e.

Methad of

-u

~-

5' M

C Shutting v

p Down Reactor 3 H

E" -

m 5'

m m

C ao H

c

'M r

O O

m' a m -.

~3 <R N

O 2:

~

~3o H

~M w

  • t n-m v2

>2 d

O

=

v O

O PYY~K..

System x

O>rr ii.*c u u,"

Code 4 m

a y

3 =o O'

-: aca x

m a O E. M,.

m2m

.s mo

  • n n.,

Component c

n w u o

e. n a Code 5 e

O5*

co 3

~

O a

2m u

A o

    • J l')

' O 4%

m ommmm n-u C

c m v c A

- < n.

.a s -, ~ ts.

8>N e r 2 n

ev =.

~ ~

  • 3 7.

mH

-n m m HY E

p _v -

p1 zQ

=g>o g a

?EE-age

~

n-up o

204.2 c,

-e E s-

"c3 M M M M.O m

n Q

=

c s.

3

~

G F

g~

n tn m

c a

n W,.C9 n W G C C O

""' o: o -E' 7

m O D c U1 w

=

4 sa c.

  • T13 " a Co G 3 m O 8
  • C t 3

s CN u

O n W 3 7

w 2

w t d.w i

V 5

-5 C

3 M

@ n w O m

w X4 Q

W 1

=

e a

wM D3 e

Co m t

p*1 9-

'C 5<

n d

,"s A.A m--e

. ^-

Docket No U50-0331 Unit Duane Arnold Energd Date December 14, 1981 REFUELING INFCRf!ATION Completed by _J. VanfSicke

  • Telephone 319-851-56TI 1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A:

Fall, 1982

'3.

Scheduled date for restart following refueling.

A.

Unknown 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amend, ment?

A.

Yes.

New'MAPI.HGR. tables will have to be included in Technical Specifications.

V 5.

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

!A.

Unknown at this time.

6.'

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

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

~

A.

New fuel assemblies to be placed in the reacto'r will be more highly enriched than those' currently in use.

'The n' umber of fuel assemblics (a) in the core and (b) in the spent 7.

fuel storage pool.

A.

a) 368 b),448 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.

A.

2050 9.

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

A.

1998 o

9 e

' ~

~

~~

~

~

~

~

Docket No -

050-0331 Unit Dunno Arnold Fuerav fontti Date December 14, 1981" f0 by J

an ckel MAJOR SAFETY RELATED MAINTENANCE e p neL g_g g

.DATE SYSTEM COMPONENT DESCRIPTION 11-2-81 CRD Hydraulic V-17-111 Replaced valve c11-4 Containment SV-8116B Replaced coil' Atmo. spheric Control 11-6 River _ Water Supply CV-4909 Replaced SV-4909 11-6-81 Containment SV-8103B Replaced coil Atmospheric Control 11-6-81 Containment AN 8181A Replaced flow controller Atmospheric Control 11-21-81 Containment AN 8181A Installed new chemicals Atmospheric Control a

b 4

e

?

W 4

a

~,

Docket No. 050-0331' Unit Duane Arnold Energy Center Date December 14, 1981 Completed by J. Van Sickel Telephone 319-851'-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 11-1

. At the beginning of the report period the plant was operating at 237 MWe.

The plant was being operated at reduced power levels due-to lack of system

. demand.

11-4 Control rod group 36 was withdrawn to position 48. A power increase 'was begun.

11-5.

The plant was operating at 341 MWe, 11-6.

'During normal operation while performing an operational inspection, a leak was discovered in the reactor water cleanup system outboard of both isolation valves.

R0 Report 81-041 11-14

-During a weekly control rod exercise surveillance test, an overtravel alarm was received for control rod 26-15, indicating the CRD had uncoupled.

R0 Report 81-042 11-17 During power operation, the instrument line drain valve, V-18-20, for "B" scram instrument volume level switch LS-1861 was found locked open.

i R0 Report 81-039 11-18 During normal operation, it was found that reactor water cleanup system return isolation valve M0V 2740 would not cycle.

R0 Report 81-040 11-24 During normal operation secondary containment-isolation' damper IV-AD-15B began cycling and was removed from service.

R0 Report Pending 11-24 While testing the "A" control building standby filter unit, isolation. damper IV-AD-31A was found inoperable.

R0 Report Pending

Docket No. 050-0331 Unit Duane Arnold Energy Center Date December 14, 1981 Completed by J. Van Sickel Telephone 319-851-5611 1

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 11-27 IV-AD-31A was tested and declared operable.

11-28 The "A" reactor feed pump and "A" condensate pump were secured.

11-30 The plant was operating at 273 MWe.

_.