ML20235U824
| ML20235U824 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 06/30/1987 |
| From: | Axline J, Hannen R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| DAEC-87-0771, DAEC-87-771, NUDOCS 8707220603 | |
| Download: ML20235U824 (8) | |
Text
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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 07-15-87 COMPLETED BY Jeff S. AxlIne TELEPHONE 319-851-7600 OPERATING STATUS Notes
- 1. Unit Name Duane Arnold Energy Center
- 2. Reporting Period June, 1987 E
- 3. Licensed Thermal Power (MWt): 1658
- 4. Nameplate Rating (Gross MWe):
565 (Turbine)
- 5. Design Electrical Rating (Net MWe): 538
- 6. Maximum Dependable Capacity (Gross MWe: 545
- 7. Maximum Dependable Capacity (Net MWe):
515 8 If Changes Occur in Capacity Ratings (ttems Number 3 through 7) Since the 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
- 11. Hours in Reporting Period 720 4343 108791
- 12. Number of Hours Reactor Was Critical 82.8 1776.3
'6446.6
- 13. Reactor Reserve Shutdown Hours 0
0 192.8
- 14. Hours Generator On-Line 13.3 1704.6 74445.2
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 4027.2 2195678.4 94277871.8
- 17. Gross Electrical Energy Generated (MWH) 997 756232 31614317.0
- 18. Net Electrical Energy Generated (MWH) 627.9 706440.8 29611240.9
- 19. Unit Service Factor 1.8 39.2, 68.4
- 20. Unit Avellability Factor 1.8 39.(,
68.4
- 21. Unit Capacity Factor (Using MDC Net)
.2 31.6 52.9
'22. Unit Capacity Factor (Using DER Net)
.2 30.2 50.6
- 23. Unti Forced Outage Rate 0
0 14.6
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Maintenance outaae, beginnino July 4, 1987 Scheduled to last approximately 4 days.
- 25. If Shut Down At End of Report Period, Estimated Date Of Startup:
8707220603 870630 9 ;I (9f77)
PDR ADOCK 05000331 10 R
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AVERAGE DAILY UNIT POTER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 07-15-87 COMPLETED BY Jeff S. AxIine TELEPHONE 319-851-7600 MONTH June, 1987 DAY-
, AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1-0 17 0
2' O
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6'.
0 22 0
7 0
23 0
.8 0
24 0
9 0
25 0
10 0
26 0
i 11 0
27 0
12 0
28 0
l 13 0
29 0
14 0
30 26 i
15 -
0 16 0
j INSTRUCTIONS i
On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute the nearsst whole megawatt.
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DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 07-15-87 COMPLETED BY Jeff S.
Axtine TELEPHONE 319-851-7600 REFUELING INFORMATION 1.
Name of facility.
A.
Duane Arnold Energy Center
(
2.
Scheduled date for next refueling shutdown.
A.
September 14, 1988 3.
Scheduled date for restart following refueling.
A.
June 26, 1987 4
Will refueling or resumption of operation thereafter require a technical specification change or.other license amendment?
Yes A.
Reload license submittel B.
Additional MAPLHGR curves for new fuel bundles being introduced for Cycle 9 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
A.
Submitted B.
Submitted 6.
Important licensing considerations associated wIth refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methocs, significant changes in fuel design, new operating procedures.
None 7
The number of fuel assemblies (a) in the core and (b) In the spent fuel storage pool.
A.
a) 368 b) 824 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 capacity.
A.
1998
DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 07-15-87 COMPLETED BY Jeff S.
Axline TELEPHONE 319-851-7600 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE 6-1-87 At the beginning of the month the Ouane Arnold Energy Center (DAEC) was in cold shutdown preparing special tests to meet regulatory requrlements for contect testing.
There were three reportable events this month.
LER 87-019 (described last month) has been renumbered 87-018.
6-5-87 On this any it was determined by the NRC that various relay contacts were not being tested per Technical Specification requirements.
This discovery evolved into 51 special logic tests which extended the refuel outage approximately 3 weeks.
6-17-87 At 0009 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, a Reactor Protection System (RPS) actuation occurred due to Main Steam Line High Radiation signals generated during augmented surveillance testing on logic systems.
The plant was shutdown ei the time and no rod motion occurred.
As immediate corrective actions, the RPS trip was reset (at 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />) and the surveillance test suspended.
The test was modified and was completed without further incident at approximately 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />.
The root cause of the ev6at was a procedural Inadequacy since the procedure did not include a step to reset the RPS trip on one division (half scram) prior to beginning testing on the other RPS division.
All systems operated as designed and, as a result, there was no threat to the health or safety of the public.
(LER 87-019) 6-18-87 At 0729 hours0.00844 days <br />0.203 hours <br />0.00121 weeks <br />2.773845e-4 months <br />, en Emergency Diesel Generator
('A' EDG) start occurred due to signals generated during augmented surveillance testing on logic systems.
The plant was shutdown at the time.
As immediate corrective actions, the EDG was secured (at 0733 hours0.00848 days <br />0.204 hours <br />0.00121 weeks <br />2.789065e-4 months <br />) and the surveillance test suspended.
The test was modified to preclude any automatic starts and was completed without further Incident.
The root cause of the event was a personnel error by utility personnel.
The error was in inadvertently shorting across contacts on test equipment Installed to block the EDG start.
All systems operated as designed and, as a result, there was no threat to the health and safety of the public.
l I
(LER 87-020) 6-24-87 On this day it was determined that General Electric HGA relays which are used at the DAEC may not be seismically quellfled to the specifications in Section 3.10.1.1 of the UFSAR.
After researching the problem further it was determined that these relays did not meet the regulred seismic qualifications needed for normally closed safety system logic.
All relays used for the above function were replaced by slesmically quellfled HFA relays before startup.
(LER 87-021)
DOCKET NO. 050-0331 UNIT D u s t.
Arnold Energy Center DATE 07-15-87 COMPLETED BY Jeff S.
Axline TELEPHONE 319-851-7600 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE 6-26-87 Pre-startup special logic testing was completed today.
6-27-87 With the Reactor mode switch in startup after a refuel outage, the Reactor Coolant Chloride ton and Conductivity Analysis Surveillance Test Procedure was performed at 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br />.
The surveillance, which is required dally, war not performed again until June 28, 1987 at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />.
The root cause of this event was personal interpretation by a utility employee.
The worker thought once every calender day was sufficient.
Licensing personnel are currently evaluating the DAEC technical specifications to determine the deportability of this event.
6-30-87 At the end of the month the cycle 8/9 refueling outage was completed.
All necessary contact testing was completed, meeting the NRC requirements for startup.
At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br />, with the reactor at approximately 22% power, the generator was s y n c h r ofi l r e d to the grid.
Earller in the day, at 0454 hours0.00525 days <br />0.126 hours <br />7.506614e-4 weeks <br />1.72747e-4 months <br />, it was found that the
'A' Outboard Main Steam isolation valve would not fully open after cycling.
When It was later determined that the valve stem was hanging up on the Junk ring, the valve was declared inoperabia until it could be repaired.
At this time it was decided that the reacto' would have to shutdown before repair could begin.
A maintenance outage was scheduled, which began on July 4,
1987, to repair the valve.
5
6 '
-E Iowa Electric Light and Power Company July 15, 1987 DAEC-87-0771 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C.
20555
Subject:
Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 June,1987 Monthly Operating Report
Dear Sirs:
Please find enclosed the Duane Arnold Energy Center Monthly Operating Report for June, 1987.
The ' eport has been prepared in accordance with the guidelines r
of Regulatory Guide 1.16 and distribution has been made in accordance with DAEC Technical Specifications, Appendix A, Section 6.11.1.c.
er-y tr ty y urs, 2-w%
Rick L Hannen Plant Superintendent - Nuclear Duane Arnold Energy Center RLH/JA/go*
Enclosures File A-118d cc: Mr. A. Bert Davis Mr. Phillip Ross Regional Administrator U. S. Nuclear Regulatory Commission Region III Maryland National Bank Building U. S. Nuclear Regulatory Commission Washington, D. C.
20555 (2) 799 Roosevelt Road Glen Ellyn, IL 60137 (1)
NRC Resident Inspector Mr. Anthony J. Cappucci Mr. Dennis Murdock Project Manager Central Iowa Power Cooperative BWR Project Directorate #2 Box 2517 U. S. Nuclear Regulatory Commission Cedar Rapids, IA 52406 7920 Norfolk Avenue Bethesda, MD 20814 Mr. Russ Gamble Corn Belt Power Cooperative INP0 Records Center 130013th Street North l
1100 Circle 75 Parkway Humboldt, IA 50548 Suite 1500 Atlanta, GA 30339 k
f?
6s s Duane. Arnold Energy Center
- 3277 DAEC fload
- Palo, Iowa 52324
- 319 851 7611
_ _ _ _ _ _