ML20023A863

Monthly Operating Rept for Sept 1982

ML20023A863
Person / Time
Site:	Duane Arnold
Issue date:	10/13/1982
From:	Watson M IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20023A862	List: ML20023A860 ML20023A863
References
NUDOCS 8210200096
Download: ML20023A863 (7)

Text

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE October 13, 1982 COMPLETED BY Mark E. Watson b---

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TELEPHONE 319-851-5611 OPERATING STATUS I. Unit Name:

Duane Arnold Eneroy Center

. Notes

2. Reporting Period:

Sootember 1982

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Gross MWe): 565 (Turbine Rating)

S. Design Electrical Rating (Net MWe): 538

6. Maximum Dependable Capacity (Gross MWe): 646

7. Maximum Dependable Capacity (Net MWe):

515

8. 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:

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f This Month Yr.-to Date Cumulative 720.0 6551.0 67175.0 L

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 720.0 4821.0 48299.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Ilours Generator On-Line 720.0 4604.3 46993.7 l

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15. Unit Reserve Shutdown flours 0.0 0.0 0.0 -

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16. Gross Thermal Energy Generated (MWH) 423364.8 5259355.6 58312753.6

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17. Gross Electrical Energy Generated (MWH) 134222.0 1753941.0 19528981.0 _ _ _

18. Net Electrical Energy Generated (MWH) 121057.2 1641700.2 18273285.5

19. Unit Service Factor 100.0 70.3 70.0

20. Unit Availability Factor 100.0 70.3 70.0

21. Unit Capacity Factor (Using MDC Net) 32.6 48.7 -

52.8

22. Unit Capacity Factor (Using DER Net) 31.3 46.6 50.6

23. Unit Forced Outage Rate 0.0 25.5 18.1

24. Shutdowns Scheduled Over Nest 6 Months (Type. D.ite.and Duration of Each):

First Quarter 1983 Refueling

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

8210200 O %

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• Turbine Rating: 565.7 MWe

("IIII Generator Rating: 663.5 (MVA) x.90 (Power Factor) = 597 MWe

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 Duane ArnoIS.

UNIT Enerny cantor DATE October 13, 1982 COMPLETED BY Mark E. Watson TELEPHONE 319-851-5611

)

MONTH _Sentember 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 223 168

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37 2

214 173

,3 3

70s 39 170 4

179 20 172 5

180 171 21 6

IRI 22 171 7

244 23 169 248-169 g

24 9

259 25 172 go 19 1 26 171 181 171-27 12 177 28 167 13 185 163 29 34 187 30 166 15 19n 3

g, INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) e

DOCKET NO. 050-0331 UNIT SHUTDOWNS AND POWER REDUCTIONS UNITNAME nuano Arnold Energy Ctr DATE ni +nhor 1t 1oe COMPLETED 8Y Mark E. Watson REPORTMONTH SeDtenber.1982 TELEPHONE 319-851-5611 E

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3 j.E3 Licensee Ev,

• • L Cause & Corrective No.

Date g

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255 Event gg Ed

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H yE 5

j gji g Report a mO Prevent Recurrence g

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16 820310 F

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N/A N/A N/A N/A Load reduction by load dispatcher i

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4 l

F: Forced Reason:

Method:

Exhibit G -Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I-Same Source (9/77)

II-Other (Explain) d

Date 0ctober 13, 1982.

Completed by Mark Watson MAJOR SAFETY RELATED MAINTENANCE

.. 4 elophone 319-as1 cA11 DATE SYSTEM COMPONENT DESCRIPTION 9-2-82 Standby Diesel Air Pressure Relief Valve Replace' valve Compressor

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9-12-82 HPC Inboard Isolation Valve.

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Replace TDS 9-14-82 RHRSW Pump IP-22D Reset, impeller 9-14-82 RHRSW Pump IP-22A Res5f' impeller '

9-14-82 HPCI Steamline Pipe Supports' Rehligned

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9-17-82 RCIC Upper isolation -valve for LS-2407 Repacked.

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9-20-82 RHRSW IP-22A Pump Repack 9-21-82 RHRSW

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IP-22C Pump Repack.

Sole'oid valves'SV '4134A & B '

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9-24282 Offgas System n

Replaced.

9-24-82 RHRSW Pump IP-22D Set impeller lift '

9-27-82 Drywell Rad. Mon.

Radiation ~ Monitor i

Dried ou't sat. detector 9-27-82 trywell Particulate Monitor Dried out sat.' de'tector Radiation Monitor 0

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Unit Duani Arnold Eneroy Center Data October 13, 1982 Completed by Mark E. Watson Telephone 319-851-5611 REFUELING INFORMATION 1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A.

1st quarter,1983 3.

Scheduled date for restart following refueling.

A.

Unknown

-4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

A.

Yes. New MAPLHGR 6bles will have to be included in Technical Specifications.

5.

Scheduled date(s) for submitting propose'd licensing action and supporting information.

A.

Unknown at this time.

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6.

Important licensing considerations associated with refueling, e.g., new I

or different fuel design or supplier, unreviewed design or performance

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analysis methods, significant changet in fuel design, new operating procedures.

A*

New fuel assemblies to be placed in the reactor will be more highly

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enriched than those currently in use.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

A.

a) 368 b) 448 8.

The present licensed spent fuel pool storage capacity and'the size of any increase in licensed storage capacity that has been requested o'r 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 6

l Docht N2. 050-0331

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Unit DuanS Arnold Energy Center

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Data October 13, 1982

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Completed by Mark-E. Watson /

Telephone 319-851-5611 l

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE l

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F 9-1 Normal operation at 211 Nie net.,

9-2 During norm'al operation, while investigating a " river water intake

. system IC-102 trouble" alarm, HS-2960B was found in the 'off' position.

HS-2906B is the mode switch for IP-112B, the 'B'. river water supply (RWSS) traveling screen wash pump., 'B' RWSS was declared inoperable.

R0' Report 82-057 9-10 During normal operation, the 'B' RWSS traveling sc een 1F-368 would not run in either ' auto' or ' continuous' mode.

The 'B' RWSS was declared inoperable.

I R0 Report 82-058 9-10 During normal operation, workmen in the RCIC rocm reported a marked l

increase in room temperature.

Subsequent investigation revealed that

...the drive. belt for RCIC. room cooling unit.IV-AC-15A.was broken.. Since._

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redundant IV-AC-15B was inoperable for repairs, RCIC: pump 1P-226 was j

inoperable.

1 R0 Report 82-059 9-10 During normal operation, the 'B' RWSS traveling screen 1F-36B would not run in either ' auto' or ' continuous' mode.

The 'B' RWSS was l

declared inoperable.

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R0 Report 82-060 l

9-12 During normal operation, HPCI steam supply isolated due to erroneous signal from TDS-2260A.

HPCI was declared inoperable. Upon operability testing, HPCI did not meet fast start requirements. ECCS subsystems testing resulted in RCIC declared inop. due to turbine trip.

R0 Report 82-056 9-14 During normal operation, RHR Service Water pumps ' A' and 'D' failed to meet Teqhnical Specification flow and head requirements during testing.

R0 Report 82-0,61 i

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f Docktt No. 050-0331 Unit Duana Arnald Energy center Date October 13. 1982 Completed by M3rk "E. Watson Telephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE

~ 9-22 During normal operation, surv'eillance testing pressure differential switch ~PDS-4304, which controls reactor building to suppression chamber vacuum breaker CV-4304, tripped consecutively out-of-spec.

R0 Report 82-062 9-27 During normal operation, surveillance testing, reactor building isolation damper IV-AD-1783 failed to close when given an isolation signal.

. Redundant damper IV-AD-17A3 -was closed.

R0 Report 82-063

.s.

4 9-28 During normal operations, 'B' SBFU heater tripped on overtemperature after operating 3 minutes.

'B' SBFU declared inop.

R0 Report Pending 9-29 During normal operations, personnel found 1B4401 LPCI Injection Valve feed breaker racking mechanism access door open. Breaker,was inoperable.

R0 Report Pending O

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