ML20091K899
| ML20091K899 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/30/1984 |
| From: | Mineck D, Putnam K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| DEAC-84-298, NUDOCS 8406070238 | |
| Download: ML20091K899 (4) | |
Text
' ~
t OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 5-15-84 COIPLETED BY Ken S.Putnam TELEPHONE 319-851-7456 OPERATING STATUS Notes
- 1. Unit Name Guane Arnold Energy Center
- 2. Reporting Period AprIi. 1984
- 3. Licensed Thermal Power t h):
1658
- 4. Nameplate Rating (Gross h):
565
- 5. Design Electrical Rating (Not M):
538
- 6. Eximum Dependable Capacity (Gross h):
545
- 7. hximum Dependable Capacity (Not h):
515
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since the Last Report, Give Reasons:
- 9. Power Level to inich Restricted, if Any (Not h ):
- 10. Reasons For RestrIctlons, If Any:
This enth Yr-to-Date Cumulat ive
- 11. Hours in Reporting Period 719.0 2903.0 81047.0
- 12. Number of Hours Reactor hs Critical 373.8 2342.4 58277.4
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 307.3 2300.2 56742.9
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0___
- 16. Gross Thermal Energy Generated ( MH) 478944 3523560 71272122
- 17. Gross Electrical Energy Generated ( MH) 161951 1198625 23892682
- 18. Not Electrical Energy Generated ( MH) 152885 1131463 22370054
- 19. Unit Service Factor 42.7 79.2 70.0
- 20. Unit Availability Factor 42.7 79.2 70.0
- 21. Unit Capacity Factor (Using IOC Net) 41.5 75.7 53.6
- 22. Unit Capacity Factor (UsIN DER Net) 39.5 72.4 51.3
- 23. Unit Forced Outage Rate 57.3 20.8 17.4
- 24. Shutdowns Scheduled Over Next 6 Enths (Type, Date, and Duration of Each):
mintenance outage beginnIng my 16, 1984 lasting 2 to 4 weeks.
- 25. If Shut Down At End Of Report Per!od, Estimated Date of Startup:
Turbine Rating: 565.7 h Generator Rating: 663.5 ( NfA) x.90 (Power I actor) = 597 Mts lh(9f773
/
0406070238 840430 PDR ADOCK 05000331 R
t
': 4
- AVERAGE DAILY UNIT POIER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Enerny Center DATE 5-15-84 COIPLETED BY Ken S. Putnam TELEPHONE 319-851-7456 10 NTH Aorli, 1964 DAY AVERAE DAILY PotER LEVEL DAY AVERAGE DAILY P0iER LEVEL
- ( 8eep-Net)
(8m -Net) l 484 17 0
2 505 to 0
3 5')7 19 0
4 50d 20 0
-5 511 21 0
6' 511 22 0
-7'-
506 23 0
8-462 24 0
9 506 25 0
' 10 506 26 0
ti 507 27 0
12
'502 28 0
13 324 29 0
14 0
30 0
15 0
31 16 0
INSTRUCTIONS On this format, list the everage delly unit power level in lean-Net for each day in the reporting month. Compute to the nearest whole megewett.
(9/77)
.s UNIT SHUTDO WNS AND PO WER REDUCTIONS Dackot No.
050-0331 Unit Name Duane Arnold Energy Center Date 5-15-84 REPORT PONTH April Completed by Ken S. Putnam Telephone 319-851-7456 L
4-en o cm N
o c +a y
to OE y5y Licensee Ey yy Cause & Correct Ivo g
No.
Date E
M$
jyy Event yj gj Action to M.
53 y@g Report #
g o
Prevent Recurrence O
E-3 EO o
3 84-04-13 F
411.7 A
1 LER 84-013 AD
- FCV, "A"
recirculation bypass valve VTV and its associated vent valve had packing, leakage. The packing was repaired, stopping the leakage.
l I
I 2
3 4
F: Forced Reason:
htthod:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Denual for Preparation of Data 8-mlntenance or Test 2-knual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NURES D-Regulatory Restriction 4-Other(Explain) 01611 E-Operator Training & License Examinatloa F-Administrative 5
G-Operational Error (Explain)
Exhibit 1-Same Source (9/77)
H-Other(Explain)
Docket No. 050-0331 Unit Duane Arnold Energy Ctr Date kh y 15, 1984 Completed by _ Ken S. Putnam Telephone 319-851-7456 REFUELING INFORhmTION 1
Name of.. facility.
A.
Duane Arnold Energy Center it.
' Scheduled date for next refueling shutdown.
A.
January, 1985 3.
Scheduled date for restart following refueling.
A.
April, 1985 E4 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 enPLHGR curves for new fuel bundles being Introduced for Cycle 8 5
Scheduled date(s) for submitting proposed licensing action and supporting Information.
July, 1984 6
Important licensing considerations associated with refueling, e.g., new or different fuel design or suoplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None 7
The number of fuel assemblies (a) In the core and (b) In th6 spent fuel storage pool.
A.
a) 3be b) 576 l
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 assualng the present licensed capacity.
A.
1998 l
J
Docket No.
050-033l Unit Duane Arnold Energy Center Date Ma y 15, 1984
>AJOR SAFETY RELATED halNTENANCE Completed by Kenneth S. Putnam Telephono 319-851-7456 DATE SYSTEM CO WONENT DESCRIPTION 04-13-84 Diesel Generator Diesel Generator Annual inspection and Overhaul to 04-29-84 04-16-84.
MS I V M5 l V Actuators Cleaned and lubricated spring guides 04-21-64 "A" Recirculation System Discharge Bypass Valve t>O-1629)
Repacked valves.
Inspected and repaired I
nearby electrical components for steam damage.
(LER 84-013) 04-29-84,
APRM APRM "E" Power Supply Repaired power supply to prevent voltage I
ripple.
6
~.4"a e
Dockot Ns, 055-0331 Unit Duane Arnold Energy Ctr Date kn y, 1984 Completed by Ken Putnam Telephone 319-851-7456 NARR AT I VE SU MERY OF OPERATING EXPERI ENCE 04-08-84 Normal plant operation at 550 MWe (gross).
04-04-84 At 0517 hours0.00598 days <br />0.144 hours <br />8.54828e-4 weeks <br />1.967185e-4 months <br />, at approximately 955 power, the automatic control of the scoop tube position for controlling recirculation flow became erratic. The scoop tube was manually positioned and locked prior to excessive power build-up.
A mild reactor transient resulted in neutron flux swinging from approximately 805 to approximately 1875 power (scram did not occur as the transient was insufficient for RPS Initiation).
'04-13-64 During normal full power operation, the unidentitled leakage to tne drywell floor drain sump increased to greater than the 5 gpm limit set by technical specifications. A controlled shutdown commenced. At 1451 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.521055e-4 months <br /> an unusual event was declared due to a 45 minute drywell floor drain "unidentitled" leakage rate of 9 gpm.
The unidentitled leakage was later found to be gross packing leaks on the " T" recirculation pump discha go bypass valve and its associated von: valve.
(LER 84-013)
At 1717 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.533185e-4 months <br /> the main generator was taken off line commencing an outage for repair of the unidentitled leakage and performance of annual surveillance testing.
At 1916 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.29038e-4 months <br /> the reactor was subcritical.
04-14-84 The unusual event was cancelled at 1408 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.35744e-4 months <br /> with the reactor shutdown and leakage identitled.
04-16-84 During surveillance testing of Group 5 Isolation (secondary containment latogrity) a partial Group 3 Isolation of the Reactor Water Cleanup system spuriously occurred. This deviation was repeated on 4-23-84 and 4-25-64 for diagnostic purposes.
(LER-84-014 pending).
04-29-84 At 1831 hoars the reactor was critical.
04-30-84 At 0018 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> the reactor was driven subcritical for inspection of the drywell.
At 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br /> the reactor was critical.
At 0237 hours0.00274 days <br />0.0658 hours <br />3.918651e-4 weeks <br />9.01785e-5 months <br /> the reactor scrammed due to an IR Wupscale trip.
(LER 84-015 pending)
At 1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br /> the reactor was critical.
At 2201 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.374805e-4 months <br /> the main generator was brought on-line.
At 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />, normal plant start-up was continuing with operation at 64 MWe gross.
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DAEC-84-298 9
i Director., Office of Inspection and Enforcement U 'g l
U. S. Nuclear Regulatory Connission OA Washington, D. C.
20555 gA Attn:
Document Control Desk
Subject:
Duar.e Arnold Energy Center Docket No. 50-331 Op. License DPR-49 April,1984 Monthly Operatir.g Report
Dear Sirs:
Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for April,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 6.11.1.c and Regulatory Guide 10.1.
Very truly yours, Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center
-DLM/KSP/kp*
Enclosures File A-118d, TE-5 cc:
Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Maryland National Bank Bldg.
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 Marion, IA 52302 Washington, D. C. 20555 (1)
Mr. George Toyne, Gen. Mgr.
U. S. Nuclear Regulatory Commission Corn Belt Power Cooperative ATTN: Mr. M. Thadani Box 508 Washin C.
b555 y
INP0 Records Center j
1100 Circle 75 Parkway 7
L Suite 1500 Atlanta, GA 30339 Duane Arnold Energy Center e P.O. Box 351
- Cedar 11apuds, Iowa 52406 31918517611