ML20093G806
| ML20093G806 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 06/30/1984 |
| From: | Mineck D, Putnam K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| DAEC-84-445, NUDOCS 8407240424 | |
| Download: ML20093G806 (8) | |
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OPERATifG DATA REPORT f
DOCKET NO. 050-0331 DATE 7-15-84 COMPLETED BY Ken S.Putnam TELEPHONE 319-851-7456
[
OPERATING STATUS Notes
- 1. Unit Name Duane Arnold Energy Center
- 2. Reporting Period June. 1984
- 3. Licensed Thermal Power (MWt):
1658
- 4. Nameplate Rating (Gross Mie):
565
- 5. Design Electrical Rating (Not MWe):
538
- 6. Maximum Dependable Capacity (Gross MWe):
545 l
- 7. Maximum Dependable Capacity (Not MWe):
515
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since the Last Report, GIvo Reasons:
2
- 9. Power Level to Which Restricted, If Any (Not MWe):
- 10. Reasons For Restrictions, if Anyt j
I This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Pa,rlod 720.0 4367.0 82511.0 1
- 12. Number of Hours Reactor was Critical 295.9 3028.5 58963.5
- 13. Reactor Reserve Shutdown Hours 150.3 150.3 150.3
- 14. Hours Generator On-Line 241.5 2930.5 57373.2
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 5
- 16. Gross Thermal Energy Generated (MWH) 293287 4268656 72017219 l
- 17. Gross Electrical Energy Generated (MWH) 93133 1445283 24139340
- 18. Not Electrical Energy Gr,nerated (MWH) 86849 1361982 22600572
- 19. Unit Service Factor 33.5 67.1 69.5 4
- 20. Unit Availability Factor 33.5 67.1 69.5
- 21. Unit Capacity Factor (Using MDC Net) 23.4 60.6 53.2 1
- 22. Unit Capacity Factor (Using DER Net) 22.4
' 58.0 50.9 h
- 23. Unit Forced Outage Rate 35.7 20.1 17.4
~
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Dete,'and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
l
- Turbine Reting: 565.7 MWe Generator Rating:.663.5 (MVA) x.90 (Power Factor) = 597 MWe 8407240424 840630 PDR ADOCK 05000331
-(9/77)-
R PDR
' AVERAGE DAILY UNIT POWER LEVEL i
e DOCKET NO. 050-0331 LMIT Duane Arnold Energy Center DATE 7-15-84 i
COMFLETED BY Ken S. Putnam TELEPHONE 319-851-7456 MONTH June, 1984 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i
(MWe-Net)
(MWe-Net) 1 0
17 258 2
0 18 271 3
0 19 368 4
0 20 452 5
0 21 480 6
0 22 479 7
0 23 478 8
0 24 470 9
0 25 48 10 0
26 0
il 0
27 0
12 0
28 0
13 0
29 0
l 14 0
30 0
15 79 31 16 229 i
INSTRUCTIONS 1
- On this format, list the average daily unit power level in MWo-Net for each day in the reporting month. Compute to f
the nearest whole megawatt.
(9/77).-
1
+
i e
a l
t L
~ _ _. _.. _
i e.'
UNIT SHUTDOWNS AND POWER REDUCTIONS Docket No.
050-0331' Unit Name Duane Arnold Energy Center Date 7-15-84 REPORT. MONTH June, 1984 Completed by Ken S.-Putnam Telephone 319-851-7456 m
L.
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EU Licensee
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Cause & CorrectIvo
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Event-uE.
EO Action to to.
Date e
o Eo E
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Report #
O.
Prevent Recurrence F-s :r e
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05-17-84.
S 344.3' B.
1 LER 84-016 JM ISV "C"
Inboard MSIV piston / main disc separation.
Valve repaired. Outage prolonged due to.Inoperability of i
main generator.
i
?
5 06-25-84 F.
134.2 A
I LER 84-021 EK BLO Failure of scavenger air blower rendered "B"
diesel I
generator inoperable.
4 I
l t
2 3
4 1
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Fallure(Explain):
1-Manual for Preparation of Data 4
B-Ma in tena n ce or Test 2-Manual Scram.
Entry Sheets for Licensee i
}.
C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG t D-Regulatory Restriction 4-Other(Explain) 0151)
E-Operator Training,& License Examination F-Administrative 5
{
.G-Operational. Error (Explain)
Exhl bi t 1-Same Source
. (9/77)
H-Other(Explain)
Docket No.
050-0331 Unit Duane Arnold Energy Center Date July 15, 1984 MAJOR SAFETY RELATED MAINTENANCE Completed by Kenneth S.
Putnam Telephone 319-851-7456 DATE SYSTEM COMPONENT DESCRIPTION C6-06-84 Main Steam Lines "C"
inboard MSiv Completed repairs and inspections initiated May 17, 1984 "C"
Out boa rd MSIV (LER 84-016)
"B" Inboard MSly 06-19-84 Reactor Protect ion System Reactor High Pressure Switches Recalibrated pressure switches that had drifted high.
(LER 84-023) 06-3T-84 Standby Diesel Generators Diesel Generator IG-21 Replaced scaverging air blower, blower 4
drive gears and coupling, and turbocharger. Performed eng i ne and generator Inspections.
(LER 84-021)
a.
Docket No. 050-0331 Unit Duane Arnold Energy Ctr Date July 15, 1984 Completed by Ken S. Putnam Telephone 319-851-7456
' REFUELING INFORMATION 1.
Name of facility.
A.
Duane Arnold Energy Center 2.
Scheduled date for next ref ue ling shutdown.
A.
January, 1985 (Tentative schedule) 3.
Scheduled date for restart following refueling.
A.
April, 1985 4
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
A.
Reload license submittal including power uprate.
B.
Additional M APLHGR curves for new fuel bundles belrg Introduced for Cycle 8 5
Scheduled date(s) for submitting proposed licensing action and s upport ing Information.
July, 1984 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 pr o ced u r e s.
None 7
The number of fuel assemblies (a) In the core and (b) in the spent fuel storage pool.
A.
a) 368 b) 576
.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 ref ueling that can be discharged-to the spent fuel pool assuming the present licensed capacity.
A.
1998
- 7..
.~
e,
Docket No. 055-0331 Unit Duane Arnold Energy Ctr Dats July, 1984 Completed by Ken Putnam Telephone 319-851-7456 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE 06-01-84 Reactor in cold shutdown. Outage for repair of main steam isolation valves continues.
At 1613 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.137465e-4 months <br /> a fire alarm was received as a result of minor smoke produced when the motor for the "A"
river water supply pump burned out.
06-03-84 At 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> the reactor water cleanup system Isolated due to a spurlous electrical signal.
Similar spurlous isolations occurred on 06-05-84 and 06-06-84 (LER 84-019) 06-07-64 At 1146 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.36053e-4 months <br /> the reactor was critical. Multiple criticalltles were achieved for operator training while awaiting the completion of repairs to the main generator due to a hydrogen seal leak.
06-13-84 At 1902 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.23711e-4 months <br /> the reactor was critical.
06-14-84 At 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> the HPCI turbine exhibited slower than usual fast start times.
Additional testing and Inspection demonstrated HPCI turbine operability by 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />.
At 1348 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.12914e-4 months <br /> the reactor was driven subcritical for drywell inspection. AT 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br /> the reactor was again critical.
06-15-84 At 0819 hours0.00948 days <br />0.228 hours <br />0.00135 weeks <br />3.116295e-4 months <br /> the generator was put on line.
06-16-84 AT 0106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> the "A"
reactor feed pump tripped due to an oil line orifice sizing problem.
l 06-17-84 At 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> a standby filter unit tripped on a spurious high radiation signal. The unit tripped again at 1725 hours0.02 days <br />0.479 hours <br />0.00285 weeks <br />6.563625e-4 months <br />.
A lightning storm is believed to have caused the spurious signals.
(LER 84-020 pending)
At 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br /> the "B"
standby diesel generator tripped during testing due ta failure of the scavenger air blower.
The "B"
diesel genrator was declared inoperable commencing a 7 day LCO.
(LER 84-021) 06-18-84 A personnel error was discovered which had left a breaker tripred on the "B"
river water supply screen-wash-pump for the previous 3 days.
(River water supply system continued to supply Tech. Spec.
required flow in both loops throughout this pe r i od. )
F 1
I l
i
'e.
06-19-84 AT 1537 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.848285e-4 months <br /> a spurious one-half Group 111 primary containment iso lation occurred with initiation of one stand by gas treatment system.
(LER 84-022 pend ing)
Three out of four RPS reactor high pressure switch setpoints were found delfted high during surveillance testing.
(LER 84-023 pending) 06-20-84 The first cf four shipments of Cycle 8 fuel bundles was received on-site.
The next three shipments were received by 06-29-84 At 1346 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.12153e-4 months <br /> a conductivity element in the domineralization samp le.sys tem was declared inoperable as a result of conservative drifting.
A 30-day LCO was commenced.
At 1643 hours0.019 days <br />0.456 hours <br />0.00272 weeks <br />6.251615e-4 months <br /> the "A"
side stand by filter unit initiated on a spurious high radiation signal.
(LER 84-020 pen d ing) 06-24-84 The replacement scavenger air blower f or the Inoperable "B" standby diesel generator was found ru b bi ng.
As the delay In repairs to the diesel generator would exceed the time limit set by the 7-day LCO, a controlled shutdown was c om m e r. c e d.
At 1711 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.510355e-4 months <br /> an Unusua l Event was declared due to the Initiation of a shutdown r eq u i r ed by Technical Specifications.
At 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br /> a 24-hour LCO commenced due to the Inoperability of the standby diesel generator for 7 days.
~
06-25-84 At 0801 hours0.00927 days <br />0.223 hours <br />0.00132 weeks <br />3.047805e-4 months <br /> the main generator was taken off-line.
At 0907 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.451135e-4 months <br /> the reactor was subcritical.
At 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br /> the head vents were opened, placing the reactor in cold shutdown ending the 24-hour LCO and the Unusual Event.
06-30-84 At 0642 hours0.00743 days <br />0.178 hours <br />0.00106 weeks <br />2.44281e-4 months <br /> the reactor was critical. At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> the reactor was driven suberltical for drywell. entry and inspection.
At 1333 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.072065e-4 months <br /> a spurious s igna l caused the Isolation of the reactor water clean-up system.
(LER 84-024 pending)
At - 2212 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.41666e-4 months <br /> the main generator was placed on-line.
At 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> the plant was operating at 45 MWo (gross) and increasing in normal plant start-up.
r-Iowa Electric Light and Ibwer Company July 13, 1984 DAEC-84-445 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, 1984 Monthly Operating Report
Dear Sirs:
Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for June,1984. 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.ll.l.c and Regulatory Guide 10.1.
Very truly yours.
W Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/KSP/kp*
Enclosures File A-1186, TE-5 cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Comission Maryland National Bank Bldg.
Re11on III Washington, D. C.
20555 79; 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 Comission Marion, IA 52302 Washington, D. C. 20555 (1)
Mr. George Toyne, Gen. Mgr.
U. S. Nuclear Regulatory Comission Corn Belt Power Cooperative ATTN: Mr. M. Thadani Box 508 Phillips Bldg.
Humboldt, IA 50548 Washington, D. C. 20555 INP0 Records Center 4
1100 Circle 75 Parkway Suite 1500 s
Atl ant a,ogh, po}nery center. r.a aos as s. cedar napids. sowa suoe. a ssisss.res s}}