ML20128P359
| ML20128P359 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/30/1985 |
| From: | Mineck D, Bernard Thomas IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| DAEC-85-622, NUDOCS 8507260394 | |
| Download: ML20128P359 (8) | |
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1 OPERATIPG DATA REPORT DOCVET NO. 050-0331 l
DATE 07-15-85 l
C04PLETED BY Bradford Thomas l
TE'.EPHONE 319-851-7359 i
l OPERATING STATUS Notes I
- 1. Unit Nome Duane Arnold Energy Center I
- 2. Reporting Period June. 1985 I
- 3. Licensed Thermal Power (MWt):
1658 l
' 4. Nomeplate Rating (Gross MWe):
565 (Turbine) t l
- 5. Design Electrical Rating (Not MWe):
538
[
- 6. Maximum Dependable Capacity (Gross MWe):
54 5
- 7. Maximum Dependable Capacity (Not MWe):
515
- 8. If Changes Occur in capacity Ratings (ltems Number 3 Through 7) Since the Last Report, Give Reasons:
- 9. Power Level to which Restricted, if Any (Not MWe):
- 10. Reasons For Restrictions, if Any:
This Month Yr-to-Date Cumu lat ive
- 11. Hours in Reporting Period 720.0 4343.0 91271.0
- 12. Nueer of Hours Reactor Was Critical 0
773.8 63362.5
- 13. Reactor Reserve Shutdown Hours 0
0 150.3
- 14. Hours Generator On-Line 0
773.1 61620.8
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 1005468 77465403 17.' Gross Electrical Energy Generated (MWH) 0 335850 25923204
- 18. Not Electrical Energy Generated (WWH) 0 313652 24269804
- 19. Unit Service Factor 0
17.8 67.5
- 20. Unit Availability Factor 0
17.8 67.5
- 21. Unit Capacity Factor (Using M E Net) 0 14.0 51.6
- 22. Unit Capacity Factor (Using DER Not) 0 13.4 49.4
- 23. Unit Forced Outage Rate 0
0 16.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
R
- 25. ' If Shut Down At End Of Report Period, Estimated Date of Startup July 16. 1985 fb ill (9/77)
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Enercy Center DATE 07-15-85 COMPLETED BY Bradford Thomes TELEPHONE 319-851-7339 MONTH June. 1985 OAY.
AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
s 2
0 18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
j 7
0 23 0
8 0
24 0
9-0 25 0
10.
0 26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
31 15 0
+
16 0
I INSTRUCTIONS f
On this format, list the everage delly unit power level in MWe-Net for oech day in the reporting month. Compute to I
p
,he -,.st. hole mooe..tt.
(9/77)
7 I
Docket No. 050-0331 Unit Name Ouane Arnold Energy Center i
Date 07-15-85 Completed by Bradford Thomas Telephone 319-851-7339 I
REFUEL ING lNFORMATION 1.
Name of facility.
A.
Duane Arnold Energy Center 2
Scheduled date for next refueling shutdown.
A.
Currently in progress.
3.
Scheduled date for restart following refueling.
A.
July 16, 1985 4
Will refueling or resumption of operation thereafter require a technical specification change or other license amendmentf i
Yes.
A.
Reload license submittal.
B.
Additional MAPLHGR curves for new fuel bundles being Introduced for Cycle 8.
C.
Revised spent fuel storage technical specifications.
D.
Supplemental Reload license submittal for Cycle 8 lead test fuel assemblies including MAPLHGR curves.
5 Scheduled date(s) for submitting proposed licensing action and supporting,lnformation.
A.
Submitted and approved C.
Submitted and approved B.
Submitted and approved O.
Submitted and approved 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.
5 GE Lead test assemblies which incorporate advanced fuel designs were loaded for Cycle 8 7.
The number of fuel assemblies (a) in the core and (b) In the spent fuel storage pool.
A.
a) 368 b) 696
Docket No. 050-0331 Unit Name Duane Arnold Energy Center Date 07-15-85 Completed by Bradford Thomas Telephone 319-851-7339 REFUELING INFORMATION (Continued) 8 The presert 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.
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Drckot N3 050-0331 Unit Name Duane Arnold Energy Center Date 07-15-85 MAJOR / SAFETY RELATED MAINTENANCE Com p l et ed by Bradford Thomas Telephone 319-851-7339 DATE SYSTEM COMPONENT DESCRIPTION Pricr to Recirculation Piping Weld overlay repa ir of areas of 6/04/85 recirculation piping in which defects had been d et ect ed were c om p l et ed on 6/04/85.
(See LER 85-010) 6/02/05 Control Rod Drives Control Rods inspection and refurbishing of several control rod drive mechanisms oc c u r r ed prior to fuel loading.
S I
l
Docket No. 050-0331 Unit Name Duano Arnold Energy Center Date 07-15-85 Completed by Bradford Thomas Telephone 319-851-7339 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE I
06/01/85 At the beginning of the month the Duane Arnold Energy Center was continuing l
an extended refuel and maintenance outage with the reactor partially refueled.
06/06/85 At 0928 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.53104e-4 months <br /> a full Reactor Protection System (RPS) trip occurred due to a spurious high (>155 power) Average Power Range Monitor (APRM) trip.
This was'during the time that maintenance was being performed on a Local Power Range Monitor (LPRM).
The cause of the trip is bel ieved to be the LPRM spiking high when it was placed back into service.
(LER 85-018) 06/07/85 At 1738 hours0.0201 days <br />0.483 hours <br />0.00287 weeks <br />6.61309e-4 months <br /> maintenance was performed on CRD 18-11, without electrically tagging out other control rod s centered around the cel l.
The cause of the event was operator error.
(LER A5-019) l 06/10/85 At 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> while going to the aid of an injured co-wor ker a second worker inadvertently manually tripped (bumped) the supply f eed er breaker f r om the startup transformer.
The "B"
side of tne Reactor Protection system actuated on loss of power.
The "B"
Emergency Diesel Generator auto-started.
Groups 2, 3, 4,
and 5 Isolations and the "B"
Standby Gas treatment syst6m actuated.
At 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />, a momentary upscale signal from the "A" Average Power Ra ng e Monitor actuated the "A"
Reactor Protection System, resulting in a full scram.
(LER 85-020) 06/13/85 At 1911 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.271355e-4 months <br /> core refueling was completed.
06/14/85 At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> the spent f uel water l ev el was inadvertently a l l ow ed to decrease slightly below technical specification level of 36 feet.
(LER 85-021) 06/17/85 At 1358 hours0.0157 days <br />0.377 hours <br />0.00225 weeks <br />5.16719e-4 months <br /> the "B"
side logic caused associated Group 3 primary containment isolation valves to close and the Standby Gas Treatment system to Initiate.
The cause of the isolation signal was the loosening of a screw to accommodate the Installation of a jumper, which caused a momentary loss of power to the "B"
logic. Durirg the Installation of a second j um p er an alligator clip was grounded out causing a fuse to blow.
On 6/20/85 while performing Refuel Floor Exhaust Rad iation Monitor checks, a jumper was r emov ed before returning the Instrument to operation causing a Group 3 Isolation signal.
(LER 85-022)
/
06 23/85 At 1534 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.83687e-4 months <br /> the plan for startup transformer reenergization was complete.
06/24/85 At 1236 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.70298e-4 months <br /> the reactor vessel and head flange thermal limitation test was initiated in preparation for reactor vessel head Installation.
t 06/26/85 At 0401 hours0.00464 days <br />0.111 hours <br />6.630291e-4 weeks <br />1.525805e-4 months <br /> all vessel head bolt tensioning was complete.
06/26/85 At 1916 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.29038e-4 months <br />, hydrostatic testing of the reactor pressure vessel and Class I piping commenced.
06/30/85 At the end of the month the reactor core was fully loaded, and the vessel head in place.
Iowa Electric 1.ight and Ibwer Company July 15, 1985 DAEC-85-622 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attn:
Document Control Desk
Subject:
Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 June, 1985 Monthly Operating Report
Dear Sirs:
Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for June, I?85.
The report has been prepared in accordance with the guidelines of Regulatory Guide 1.16 and distribution has been made in accordance with DAEC Technical Specifications, Appendix A Section 6.11.1.c and Regulatory Guide 10.1.
Very truly yours, Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center Enclosures File A-118d, TE-5 cc:
Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Commission i
U. S. Nuclear Regulatory Commission Maryland National Bank Building Region III Washington, D. C.
20555 799 Roosevelt Road Glen Ellyn, IL 60137 (1)
NRC Resident Inspector Director, Office of Management and Mr. Dennis Murdock Program Analysis Central Iowa Power Cooperative U. S. Nuclear Regulatory Commission Box 2517 Washington, D. C. 20555 (1)
Marion, IA 52302 U. S. Nuclear Regulatory Commission Mr. Russ Gamble ATTN: Mr. M. Thadani Corn Belt Power Cooperative Phillips Building 1300 13th Street North Washington, D. C. 20555 Humboldt, IA 50548 INP0 Records Center 1100 Circle 75 Parkway Suite 1500 Atlanta, GA 30339
.