ML112340071
| ML112340071 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/13/1978 |
| From: | Hammond E IES Utilities, (Formerly Iowa Electric Light & Power Co) |
| To: | NRC/IE |
| Shared Package | |
| ML112340072 | List: |
| References | |
| NUDOCS 7811210390 | |
| Download: ML112340071 (9) | |
Text
REGULATO4INFORMATION DISTRIBUTION *STEM DOCKET NBR: 50-331 DUANE ARNOLD RECIPIENT:-
ORIGINATOR:
HAMMOND,E. L.
COMPANY NAME:
IA ELEC LTGHT & PwR
SUBJECT:
DOC DATE:
781113 ACCESSION NBR:
7811210390 COPIES RECEIVED:
LTR 1
SIZE:
1+7 ENCL Forwards Monthly Oper Rept for Oct 1978.
DTSTRTHUttTION CfUDEjt A0OA DISTRYIUTyflk' TITLE:
ANJIIALo SEMI-ANNHAL & MONTHLY OPERATING RPTS (OL STAGE)
NOTARIZED NAMF
-B R _.
Vf I KE MTPC H A N A P r)IRECTnP Dt,)P AD) FOR~ SYS & PROJ ENGINERIN HP REACjrR SAFETY HR PLANIT SYSTEMS bR EFF CORE PERFCnRMANCE MiR EFFLUENTj' TREAT SYS LPOR NJATL g-AB TERA NSIC BROOK HA VEN ACRS ENCL?
W/6 ENCL W/ENCL W/2 F NL W/2 ENCL W/? FNCL
- ,/
F N CL
/FNCL N / F N C L N/ ENCL
/ EN CL W F N C L W/ENCL W/FNCL W/ENCL W/ENCL
/ EN C L W /F N CL W/ENCL W/ ENCL W/ENCL W/15 ENCL FOR ACTION ORB#3 BC TflTAL NuMBtER rF CnPIES PEQIJIRED!
A4R~
I
50 03I IOWA ELECTRic LIGHT AND POWER COMPANY DUANE ARNOLD ENERGY CENTER P.
78 -
444 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Monthly Operating Report File: A-118d
Dear Sirs:
Please find enclosed 10 copies of the Duane Arnold Energy Center Monthly Operating Report for October, 1978. The report has been prepared in accordance with the requirements of Regulatory Guide 1.16 and distribution has been made in accordance with Regulatory Guide 10.1.
Very truly yours, E11erL. Hammond Chief Engineer Duane Arnold Energy Center ELH/JVS/nf Encl cc:
D. Arnold S. Tuthill J. Wallace J. Rehnstrom L. Root W. Bryant D. Mineck D. Wilson B. York R. Hannen Dennis Murdock George Toyne Directorate of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 (1)
Director, Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (2)
OPERATING DATA REPORT DOCKET NO.
DATE COMPLETED BY TELEPHONE 050-0331 11-13-78 J.
Van Sickel 319-851-5611
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
8.
OPERATING STATUS UnitName:
Duane Arnold Energy Center Notes Reporting Period:
October, 1978 Licensed Thermal Power (MWt):
1 658 Nameplate Rating (Gross MWe):
565 (Turbine Rating)
Design Electrical Rating (Net MWe):
538 Maximum Dependable Capacity (Gross MWe):
545 Maximum Dependable Capacity (Net MWe):
515 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
- 11. Hours In Reporting Period 745 7,296 32,856
- 12. Number Of Hours Reactor Was Critical 0
3,058.8 23,612.8
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 0
2,904.3 22,987
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 3,956,424 28,061 640
- 17. Gross Electrical Energy Generated (MWH) 0 1,307,325 9,337,429
- 18. Net Electrical Energy Generated (MWH) 0 1,227,561 8,716,300
- 19. Unit Service Factor 0%
39.8%
70.0%
- 20. Unit Availability Factor 0%
39.8%
70.0%
- 21. Unit Capacity Factor (Using MDC Net) 0%
32.7%
51.5%
- 22. Unit Capacity Factor (Using DER Net) 0%
31.3%
49.3%
- 23. Unit Forced Outage Rate 100%
53.9%
1-6.4%
- 24. Shutdowns Scheduled 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 Generator Rating:
663.5 (MVA) x.90 (Power Factor) = 597 MWe (9/77)
0 0o AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
050-0331 UNIT Dhuane Arnold Eneray DATE 11-13-78 COMPLETED BY J. Van Sickel TELEPHONE 31q-851-5611 October, 1978 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 n
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 n
18 19 20 21 22 23 24 25 26 27 28 29 30 31 0
0 0
0 0
0 0
0 0
0 0
0 0
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
MONTH
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORTMONTH
- October, 1978 DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 050-0331 Duane Arnold Energy Cent, 11-13-78 J. Van Sickel 319-851 -5611 Licensee Cause & Corrective Date Event o
Action ito Report 0
Prevent Recurrence U
Continuation of previous shutdown to replace recirculation system inlet nozzle safe ends.
780617 F
745 A
3 78-030 CB PIPEXX I
F: Forced S: Scheduled Reason:
A-Equipment Failure (Explain)
B-Maintenance oi Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) li-Other (Explain) 3 4
Method:
I -Manual 2-Manual Scram.
3-Automatic Scram.
4-Other (Explain) 5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit I - Same Source (9/77) 0 I
0 I
Generating Statistics for month of October, 1978 for (name of unit)
Ual AL
-E~
enter Geneatin Staisic forrte mont oonh0 Gross Mwe rated capacitY 565 Gross Mwh generated in month Maximum gross Mwe permitted by license Cif less than 100%)
Cumulative gross Kwe generated from initial startup to end of month Primary reasons for any substantial down time Shutdown to reoIac...
et nozzle safe ends.
Total length of outages 745 Scheduled 0
Forced 745 atw-Stalstics of Nuclear Power Generation atw-At Month, Monat:
October 1 978 Gr..- -
Cumulative total Gross of electricity electricity Hours on produced since produced line during start-up at during the the month end of month Name of Nuclear Power Plant mot Name des Kernkraftwerks Brutto-Strom-Betriebs-Ges.-Brutto erzeugung atunden stromerzeugung w~hrend des w~hrend des seit Inbetrieb Monats Monats name am MWh MWh Arnold-0 0
11054,79
') e. g. Shutdown for Refueling (1), MaIntonance (2), Repairs (3) (Time)
- 1) z. B. Stillstand durch Brennstolfwechsel (1), Wartung (2). Reparaturen (3) (Zeltraum) omstrom-Statistik Remarks 1)
Besonderes 1)
Shutdown for re-airs 71 i
Doc'-et No.
050-0331
- A DuaneR Arnold Energy Center I'November I13, 1918 Completed. by J. Van Sickel Telephone 319-851-5611 NARRATIVE
SUMMARY
OF OPERATING'EXPERIENCE Nb significant operational events occurred during October.
The plant remained in the cold shutdown condition with all fuel removed from the reactor to facilitate replacement of all eight recirculation system inlet nozzle safe ends.
MAJOR SAFETY RELATED MAINTENANCE DATE SYSTEM COMPONENT DESCRIPTION Primary Containment Containment Atmospheric Control Standby diesel generator Control rod drive electrical 10-2-78 10-11-78 10-16-78 10-18-78 Recalibrated instrumentation to conform to design change Recalibrated temperature recorder Changes generator bearing oil Replaced.switch L
Suppression chamber water level instrumentation TR 4368A 1G-21 34-39 select switch Docket No.
050-0331 Unit ijanp Arnald Fnprgy ('nter Date Novemhr 13, 1978 Completed by 1 Van Sicke.
Telephone j1-gq1-5611
REFUELING INFORMATION Docket No. 050-0331 Unit Duane Arnold Energy Center Date November 13, 1978 Completed by J. Van Sickel
.. Name of facility.
Telephone 319-851-5611 A. Duane Arnold Energy Center
- 2. Scheduled date for next refueling shutdown.
A. Unknown. Under review-due to present extended outage.
- 3.
Scheduled date for restart following refueling.
A. Unknown. Under review due to present extended outage.
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
A. MCPR and MAPLHGR operating limits as derived from transient and accident analyses.
- 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
A. Unknown.
- 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. The reload will consist of up-to 100 8 x 8 2 water rod bundles.
- 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
A. a) 0 b) 644
- 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 S