Text

Monthly Operating Rept for Apr 1986
	ML20205P338
Person / Time
Site:	Duane Arnold
Issue date:	04/30/1986
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-86-0362, DAEC-86-362, NUDOCS 8605210344
	Download: ML20205P338 (9)
	v • d • e

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 05-15-86 COMPLETED BY Bradford N. Thomas TELEPHONE 319-851-7309 OPERATING STATUS Notes

1. Uni t Name Duane Arnold Energy Center

2. Reporting Period April, 1986

3. Licensed Thermal Power (WWt):

1658

4. Namepla te Rating (Gross MWe):

565 (Turbine)

5. Design Electrical Rating (Not MWe):

5 38

6. Maximum Dependable Capaci ty (Gross WWe):

54 5

7. Maximum Dependable Capacity (Net MWe):

5 15

8. If Changes Occur in Capaci ty Ratings (items Number 3 Through 7) Since the Last Report, Give Reasons:

1

]

9. Power Level to Which Restricted, if Any (Net MWe):

j

10. Reasons For Restrictions, if Any:

This Month Yr-to-Da te Cumu la ti ve

11. Hours in Reporting Period 719.0 2879.0 98567

12. Number of Hours Reactor Was Critical 587 2353.8 69675.7

13. Reactor Reserve Shutdown Hours 0

0 150.3

14. Hours Genera tor On-Line 577.9 2338 67897.5

15. Unit Reserve Shutdown Hours 0

0-0

16. Gross Thermal Energy Generated (MWH) 805980 2946996 85553230

17. Gross Electrical Energy Generated (MWH) 271714 1004209 28660270

18. Net Electrical Energy Generated (MWH) 255863 943354 26839991

19. Unit Service Factor 80.4 81.2 68.9

20. Uni t Availabili ty Factor 80.4 81.2 68.9

21. Unit Capacity Factor (Using MDC Net) 69.1 63.6 52.9

22. Unit Capaci ty Factor (Using DER Net) 66.1 60.9 50.6

23. Un i t Forced Ou tage Ra te 0

0 15.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

An uutage of approximately 3 days is being contemplated in the June or July time frame.

4 1

j

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

8605210344 860430 f

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' COMPLETED'tlY Br3dford N. Thomes '

TELEPH0hE 319-851-7309 MONTH April, 1986

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.c 14 521 30 463 15 538 31 16 5 34 4

lNSTRUCT IONS On th is f orma t, list the average daily unit powey level in MWe-Net for each day in the reporting month. Compute the nearest whole megawatt.

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Dockot No. 050-0331 Unit Naco Dusnn Arnald Ennrgy C ^a t~ r Dsto 05-15-86 MAJOR / SAFETY RELATED MAINTENANCE Comp l e ted by Bradford N.

Thomas Telephone 319-851-7309 DATE SYSTEM COMPONENT DESCRIPTION 04/01/86 '

Main Steam Line i so l a ti on Valve MSsV ( JH-IS V-4412)

Repaired damaged packing chamber material &

(MSIV) Sys tem stem galling (LER 86-011)

Sa f e ty Re l a ted Motor Opera tors Li mi torq ue Motor Opera tors Con ti nued inspection and replacement of Limitorque Motor Opera tor internal wiring to ensure compilance with Env i ronmen ta l Qua l i f i ca ti on (EQ) Standards 04/02/86 Service Air I ns trumen t and Service Air Performed major overhaul Compressor (IK001A) 04/05/86 Transverse incore Probe (TIP)

TIP

'A' Ball Valve Replaced inoperable Ball Valve 04/09/86 Standby Filter Unit (SFU)

'B' SFU Charcoal Replaced charcoal bed 04/10/86 S ta n d by Filter Unit (SFU)

Charcoal Deluge Stop Valve Refurbished leaking S top Valve Delugs System (CV7328B) 04/28/86 Reactor Core i sola tion Cooling RCIC Steam Leak Detection System I n s ta l l ed time delay in RCIC SLDS circuitry (RCIC) Sys tem (SLDS) Circuitry, RCIC test (LER 86-014 pending).

I n s ta l l ed a blind discharge piping flange In the RCIC tes t alscharge piping to allow maintenance on a HPCI test discharge valve.

04/30/86 High Pressure Coolant injection HPCI Steam Leak De tec ti on Sys tem i ns ta l l ed time delay in HPCI SLDS circuitry (HPCI)

(SLDS) Circuitry, HPCI test (LER 86-014 pending).

I n s ta l l ed a blind discharge piping flange in the HPCI test discharge piping to allow maintenance on the HPCI tes t discharge valve.

Docket No. 050-0331 Uni t Naco Duenn Arnold Energy Cnntar Da te 05-15-86 Completed by Bradford N.

Thomas Telephone 319-851-7309 REFUELING INFORMATION 1

Name of facility.

A.

Duano Arnold Energy Center 2

Scheduled ca te for.next ref ueling shu tdown.

A.

February, 1987 3.

Scheduled date f or res tart following refueling.

A.

AprII, 1987 4

Will ref ueling or resump tion of op era ti on thereaf ter require a technical specification change or other license amendment?

A.

None currently identitled 4

5 Scheduled date(s) for submi tting proposed licensing action and supporting I nf orma tion.

A.

None currently Iden ti t l ed 6

I m p o r ta n t licensing considera tions associated wi th refueling, e.g.,

new or different fuel design or supp!Ier, unreviewed design or performance analysis methods, signif1 cant-changes'In fuel design, new operating procedures.

None 7

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

A.

a) 368 b) 696 8.

The present licensed spent fuel pool storage capa c i ty and the sl2e of any increase in licensed storage ca p a c i ty that has been req u es ted or is planned, in number of fuel assemblies.

A.

2050 9

The projected da te of the las t ref ueling tha t ' can be discharged to the spent fuel pool assuming the present IIconsed capacity.

A.

1998

Dsckot No. 050-0331 Un i t N:so Dunn, Arnald Energy Cr'n ta r D3to 05-15 Completed by'Bradford N. Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 4/1/86 At the beginning of the Month the DAEC was in the final s tages of a planned maintenance ou tage which began on 3/15/86 At 1725 hours0.02 days 0.479 hours 0.00285 weeks 6.563625e-4 months main tenance personnel were observing Main Steam Line I sola tion Valve (MSiv) movement in preparation of surveillance tes ts.

During valve opening workers observed the valve hanging up in the partially open position. The valve was cycled closed.

On th e second a

openi ng a ttemp t, the valve again s tuck part way open.

Af ter removi ng.

the packing gland, the valve opened fully and the packing chamber material was drawn out of the bonnet.

Workers noticed the Junk Ring and the valve s tem to have surface galling.

Inves tiga ti on revealed a small piece of s te t l i te ma terial broke off the Junk Ring.

This is believed to have caused Valve Stem binding i n ' the packing chamber.

The root cause is unknown, but it is su s pec ted tha t there was a me ta l l urg i ca l flaw in the s te l l i te region. The remaining MSiv Valve Stems were visually inspected, w i th no surface galling found.

It was concluded this was an I s ol a ted occurrence and is unlikely to recur.

It was also concluded tha t the s tem galling would not have prevented i

closing the MSiv.

The galling was removed from the Junk Ring and Valve S tem.

On 4/04 /86 af ter reins talla tion of the packing chamber ma terial, the valve passed the Trip / Closure Time Check Surveillance Tes t and was s troking satisf actori ly.

(LER 86-011) 4/5/86 At 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months the

'A' Tip Ball Valve was not s troking satis f actorily during Local Leak Ra te Testing (LLRT) due to'a f au l ty re tu rn spring.

A new Tip Ball Valve from the warehouse was then i ns ta l l ed.

Upon I n s ta l l a ti on a 125 VDC ground was received. Closer I nves tiga ti on revealed a wiring error In the newly I ns ta l l ed Ball Valve. 'The add i ti ona l valves in the warehouse were then all tes ted and found to be incorrectly wired.

At 1710 hours0.0198 days 0.475 hours 0.00283 weeks 6.50655e-4 months the newly Ins ta lled Bal l Valve was rewired and re i n s ta l l ed.

At 1745 hours0.0202 days 0.485 hours 0.00289 weeks 6.639725e-4 months the ' ' A ' T I p Ball Valve successfully passed a LLRT and was returned to service.

At 1918 hours0.0222 days 0.533 hours 0.00317 weeks 7.29799e-4 months Reac tor Startup commenced.

4/6/86 At 1202 hours0.0139 days 0.334 hours 0.00199 weeks 4.57361e-4 months the Reactor was driven cri tical af ter personnel.exi ted the drywell following the primary containment walkdown at 400 PSIG primary sys tem pressure.

At 1831 hours0.0212 days 0.509 hours 0.00303 weeks 6.966955e-4 months the modo switch was placed in the Run position.

At 1938 hours0.0224 days 0.538 hours 0.0032 weeks 7.37409e-4 months the main turbine warmup began.

At 2109 hours0.0244 days 0.586 hours 0.00349 weeks 8.024745e-4 months the main genera tor was synchronized to the grid.

~

Osckct No. 050-0331 Uni t N co Dunn, Arneld En roy C n t~r Dato 05-15-86 Completed by Bradfard N.

Thomas Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 4/8/66 At 14 06 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a 7 day Limi ting Condi tion f or Opera tion (LCO) was entered when the High Pressure Coolant injection (HPCI) system failed to meet discharge pressure and flow req u i remen ts in accordance w i th the HPCI quarterly ope ra bi l i ty Surveillance Tes t Procedure. Troubleshoot 6ng of the HPCI turbine revealed a turbine speed versus flow Jemand mismatch w i th i n the HPCI turbine governor control system which prevented the HPCI turoine from reaching i ts ra ted flow.

The tu r b i ne con trol circuitry was then reca l i bra ted.

The HPCI system successfully comp l e ted its postumaintenance tes ti ng a t 2255 hours0.0261 days 0.626 hours 0.00373 weeks 8.580275e-4 months on 4 /12/86, and was declared operable thus canceling the 7 day LCO.

(LER 86-010) 4/9/86 At 0950 hours0.011 days 0.264 hours 0.00157 weeks 3.61475e-4 months the

'B' S ta n d by Fil ter Uni t (SFU) was declared inoperable and a 7 day LCO was entered when the system failed a surveillance tes t.

The charcoal bed was changed out and the unit was re tu rn ed to service a f ter successful pos t-ma i n ten a n ce tes ti ng on 4 /12/86 a t 1659 hours0.0192 days 0.461 hours 0.00274 weeks 6.312495e-4 months thus te rmi na ti ng the LCO.

22 Analyzer was declared Inoperable and a 30 day At 1005 hours0.0116 days 0.279 hours 0.00166 weeks 3.824025e-4 months the

'A' H

0 LCO was entered when the hydrogen cells would not respond to ca l i bra ti on.

A new H2 calibra tion cell and regula tor was i n s ta l l ed.

The Analyzer was returned to service at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months on 4/17/86 thus canceling the LCO.

4/10/86 At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months both Offgas H2 Analyzers were found cycling erratically be tween span and zero.

Health Physics was then notifled to obtain the necessary sampling due to the Inoperability of these Analyzers.

I nves tiga tion revealed water in the Analyzer sampling lines.

The water was removed and the s ys tem r e tu r n ed to service on 4/11/86 a t 1104 hours0.0128 days 0.307 hours 0.00183 weeks 4.20072e-4 months .

4/11/86 At 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months th e SBFU deluge sys tem was removed from service for planned maintenance placing the plant in a 14 day LCO.

A defective stop valve was repaired and the sys tem returned to service on 4/23/86 a t 1838 hours0.0213 days 0.511 hours 0.00304 weeks 6.99359e-4 months .

This in turn termi na ted the LCO.

At 2040 hours0.0236 days 0.567 hours 0.00337 weeks 7.7622e-4 months a 30 day LCO was entered when the condensate influent conducti vi ty moni tor was removed from service due to erratic opera tion.

A second monitor was Installed to record conduc ti v i ty.

A plugged filter element was replaced and repairs were still underway at the end of the mon th.

2

Do c ket No. 0 50-0331 Unit N3ao Dunne Arnold Energy C nter Dato 05-15-86 Co m p l e t ed by Bradford N.

Thncos Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 4/18/86 At 1359 hours0.0157 days 0.378 hours 0.00225 weeks 5.170995e-4 months the Reactor Water Cleanup (RWCU) system i so l a ted due to a n e r ro n eo u s signal from the RWCU steam leak detection I n s t r ume n t a t io n.

The Temperature Differential Switch was found to be read ing above the specified se t po i n t.

Operation personnel inspected the area and found no sign of leakage.

The failure is believed to be random based upon operating experience of this Temperature Differential Switch.

The system was returned to service at 2113 hours0.0245 days 0.587 hours 0.00349 weeks 8.039965e-4 months .

(LER 86-012 pending) 4/19/86 At 1551 hours0.018 days 0.431 hours 0.00256 weeks 5.901555e-4 months the RCIC system Isolated during a daily test' procedure which mo n i to r s temperatures and temperature differentials in the RCIC Steam Leak Detect io n System.

An identical iso lat ion occurred on 3/15/86 (See LER 86-07).

The cause of the RCIC i so l a t io n was a short, spurlous signal by placing a Temperature Differential Switch in the READ po s i t io n.

The root cause is design deficiency of the temperature switch.

The RCIC i so l at ion was prompt ly reset at-1555 hours.

As a long term corrective action, the Installation of. a short time delay relay was performed during a maintenance sequence on 4/28/86 (LER 86-013 pending) 4/28/86 At 0535 hours0.00619 days 0.149 hours 8.845899e-4 weeks 2.035675e-4 months the RCIC system was vo l u n t a r i l y r e mo ved from service for planned maintenance evo l ut io n.

This placed the plant in a 7 day LCO.

An emergency Design Change Package (DCP) to help prevent spurious RCIC i so l a t io n s was Installed in response to LER 86-007 and 86-013.

In addition, a flange was Installed in the RCIC test. discharge piping to a l lo w maintenance on a HPCI test discharge valve.

With the flange Instelled, RCIC was returned to service at 2201 hours0.0255 days 0.611 hours 0.00364 weeks 8.374805e-4 months thus canceling the LCO.

(LER 86-014 pending) 4/30/86 At 0447 hours0.00517 days 0.124 hours 7.390873e-4 weeks 1.700835e-4 months the HPCI system was vo l u n ta r i l y removed f ro m service for a planned maintenance evo l ut io n.

An emergency DCP to help prevent spurious HPCI i so l at io ns was Installed in response to LER 86-007, and 86-013 In addition, another flange from that installed on 4/28 was installed in the HPCl test afscharge piping in final preparation for maintenance on a HPCI test discharge valve.

The HPCI system remained in an inoperable mode at the end of the month.

(LER 86-014 pending)

At the end of the month, the plant was in normal po wer operation with 463 MWe (net) being provided to the grid.

The plant was in day 2 of a7 day LCO due to the Inoperability of the HPCI system, and in day 26 of a 30 day LCO due to the Inoperability of a co n d en s a te co n d u c t i v i t y mo n i to r.

Iowa Electric Light and Power Company May 15, 1986 DAEC 0362 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 April, 1986 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for April,1986.

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/BNT/pl*

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 Comission 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 Comission 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 y

/'p Suite 1500 Atlanta, GA 30339 Duane Arnold Energy Center

3277 UAEC lload

Palo, Iowa 52324

319l8517611

ML20205P338

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