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TELEPl!ONE 319-851-5611 OPER ATING STATUS Notes | OPER ATING DATA REPORT 050-0331 DOCKET NO. | ||
DATE December 14, 1983 COMPLETED BY | |||
: 2. Rep'orting Period: | _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) | |||
: 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 | ||
: 7. Maximum Dependable Capacity (Net MWe): | |||
: 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): | : 9. Power Level To Which Restricted,if Any (Net MWe): | ||
: 10. Reasons For Restrictions.If Any: | : 10. Reasons For Restrictions.If Any: | ||
This Month | This Month Yr to.Date Cumulative l | ||
: 12. Number Of Hours Reactor Was Critical | : 11. Hours In Reporting Pedod 790 8.016 59.880 | ||
: 13. Reactor Resene Shutdown Hours | : 12. Number Of Hours Reactor Was Critical 720 5,581.5 42,750.2 | ||
: 13. Reactor Resene Shutdown Hours 0 | |||
: 15. Unit Reserve Shutdown Hours | 0 0 | ||
16.' Gross Thermal Energy Generated (MWH) | '14. Hours Generator On-Line 720 5,400.6 41,677.6 | ||
: 17. Gross Electrical Energy Generated (MWH) | : 15. Unit Reserve Shutdown Hours 0 | ||
2,191,976 | 0 0. | ||
: 18. Net Electrical Energy Generated.(MWH) 211,o66 | 16.' Gross Thermal Energy Generated (MWH) 691.361 6,501,630 52,500,268 | ||
: 19. Unit Sen-ice Factor | : 17. Gross Electrical Energy Generated (MWH) 228,252 2,191,976 17,594,663 l | ||
: 20. Unit Availability Factor | : 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 | 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) | |||
0.0% | : 23. Unit Forced ' | ||
: 24. Shutdowns Sene | 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 | ||
Generator Rating: | Generator Rating: | ||
663.5 (MVA) x.90 (Power Factor) = 597 MWe j | |||
( | 8112210378 811214" | ||
( | |||
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 | ||
.1 Van Sirkel_ | |||
DOCKET NO. 050-0331 Duane Arnold UNIT rnnenu ennter DATE -December 14, 1981 COMPLETED BY | ILEPHONE -319-851-5611 MONTH November; 1981 | ||
ILEPHONE -319-851-5611 MONTH | ~ | ||
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) | |||
DAY | (MWe-Net) 1 219 c | ||
17 331-2 235 326' ig 3 | |||
(MWe-Net) | 7A? | ||
19 322 4 | |||
17 | 250 20 296 334 290 5 | ||
19 | 21 6 | ||
"316 ' | |||
275-22 7 | |||
32-1 3d9 23 8 | |||
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 | ||
-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 | |||
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Docket No | 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. | |||
* Telephone 319-851-56TI | A. | ||
Duane Arnold Energy Center 2. | |||
A. Duane Arnold Energy Center | Scheduled date for next refueling shutdown. | ||
A: | |||
A: | Fall, 1982 | ||
'3. | |||
A. Unknown | Scheduled date for restart following refueling. | ||
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? | ||
A. | |||
Yes. | |||
New'MAPI.HGR. tables will have to be included in Technical Specifications. | |||
6.' Important-licensing considerations associated with refueling, | 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. | ||
New fuel assemblies to be placed in the reacto'r will be more highly enriched than those' currently in use. | |||
A. a) | 'The n' umber of fuel assemblics (a) in the core and (b) in the spent 7. | ||
fuel storage pool. | |||
A. | |||
A. 2050 | 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. 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 - | ~ | ||
~~ | |||
~ | |||
~ | |||
~ | |||
~ | |||
W 4 | 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 | 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. | |||
11-4 | 11-4 Control rod group 36 was withdrawn to position 48. A power increase 'was begun. | ||
11-5. | 11-5. | ||
valves. | The plant was operating at 341 MWe, 11-6. | ||
R0 Report 81-041 11-14 | '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 | R0 Report 81-041 11-14 | ||
i R0 Report 81-039 11-18 | -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 | 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 | 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 | ||
NARRATIVE | |||
Telephone 319-851-5611 | |||
==SUMMARY== | ==SUMMARY== | ||
Latest revision as of 00:33, 20 December 2024
| ML20039A851 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| 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
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. ^-
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.
_.