ML20217C478

Monthly Operating Rept for June 1991 for Fort Calhoun Station Unit 1

ML20217C478
Person / Time
Site:	Fort Calhoun
Issue date:	06/30/1991
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-91-190R, NUDOCS 9107150345
Download: ML20217C478 (8)

Text

- _ - _ _ _ _ _ _

4

.., ~,,... - -

_....,,.._..,_-____._...in.,_.~_

July 12 1991 Omaha Public Power District LIC-91-190R 444 South 16th Street Mal!

Omaha, Nebraska 68102-2247 402/636-2000 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

June Monthly Operating Report (MOR)

Please find enclosed the June 1991 Monthly Operating Report for the Fort Calhoun Station Unit No, I as required by Technical Specification Section 5.9.1.

Also enclosed is a revision to the " Operating Data Report" section of the May 1991 MOR. While preparing the May MOR, an error occurred during data entry which affected results in the Year-To-Date and Cumulative columns.

However, the Monthly calculations were correct. Appropriate corrective actions to

-prevent recurrence have been taken.

If you should have any questions, please contact me.

Sincerely,

v. D. b W. G.

tes Division Manager Nuclear Operations WGG/sel Enclosures c:

LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident Inspector D. K. Sentell, Combustion Engineering R. J. Simon, Westinghouse Office of Management & Program Analysis (2)

'INP0 Records Center American Nuclear Insurers i

~.-

45 5124...

9107130345 910620 myment w.tt res opratan:ty IN M'/-

NN

{DR ADOCK 05000285 PDR llj

fAVERAGE DAILY UNIT POWER LEVEL DOCKET N0.

50-285 UNIT fort Calhoun Station DATE July 8, 1991 COMPLETED BY M.L. Edwards TELEPHONE (402)6J6-2451 MONTH June 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 336 17 449 2

339' 18 448 3

336 19 433 4-336 20 237 5

338 21 423 6

340 22 461

.7-341 23 470 8

341 24 __.

473 9

341 25 471 10 341 26 468 11 337 27 465 12 334 28 463 L

13

-333 29 462 i.

14 334 30 462 15 335 l

16 380 u

l:

l INSTRUCTIONS On this form, !ist the average daily unit power level in MWe-Net for each day in the reporting month. -Compute to the nearest whole megawatt.

~ -.

l OPERATING DATA REPORT DOCKET NO.10-285

!) ATE 07/10/91 COhlPLElED BY 41L _E iwards l

1ELEPil0NE (402)~ G -2451 OPERATING STATUS N"

1. Unit Name: Fort Calhoun Station

2. Reporting Period: _ June 1991

3. Licenwd Thermal Power (htWt): 1500 502 i

4 Nameplate Rating (Gross htWe):

5. Design Electrical Rating (Net Slwel: 478 502

6. 51aximum ikpendabb Capacity (Gross LlWe):

478

7. 51aximum Dependable Capacity (Net 51We):

S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A N/A

9. Power Lesel To which Restricted. If Any (Net 51We):

N/A

10. Reasons For Restrictions. lf Any:

This hionth Yr.-to-Date Cumulatise 720.0 4.343.' _

155,711.0

11. Ilours In Reporting Period

12. Number Of Iloun Reactor Was Critical 720.0 4,163.0 120,951.7

13. Reactor Reserve Shutdown flours 0.0 0.0 1.309.5

14. Ilours Generator On.Line 720.0 4,152.2 119,582.1

15. Unit Rewne Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (51Wil) 912.096.5 4_.874.757.6 156,158.246.9 17 Gross Electrical Energy Gensrated (5tWHi 294,926.0 1.604.632.0 51,354,758.2

18. Net Electrical Energy Generated (N1Wil) 279,012.6 1,514,441.6 48,999,217.9

19. Unit Senice Factor 100.0 95.6 76.8

20. Unit Availability Factor 100.0 95.6 76.8 81.1 73.0 65.8

21. Unit Capacity Factor (Using NIDC Net,

22. Unit C pacity Factor (Using DER Net)

R1_1 73.0 65.8

23. Unit Forced Outage Rate 0.0 4.4 3.6

24. Shutdowns Scheduled Oser Next 6 51onths tType. Date, and Duration of Each t:

None N/A

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

26. Units n Test Status tPrior to Commercial Operation):

Forecast Achiesed INITI AL CRIflCALITY INITIAL ELECTRICirY N/A C051%lERCl4 L OPER ATION I

(9/77 ')

. -~

Refueling Information-Fort Calhoun - Unit No. 1 Report for the month ending June 1991 1.

Scheduled date for next refueling shutdown.

January 31. 1992 2.

Scheduled date for restart following refueling.

May 1. 1992 3.

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

Yes a.

If answer is yes, what, in general, will these be?

Incorporate specific requirements resulting from reload safety analysis.

b.

If answer is no, has the reload fuel design anc core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload.

N/A c.

If no such review Ias taken place, when is it scheduled?

N/A 4.

Scheduled date(s) for submitting propcsed licensing action and support information.

November 1991 5.

Important licensing considerations associrted with refueling, e.g., new or different fuel design or supplier, unreviewed design or perforn.ance analysis methods, significant changes in fuel design, new operating procedures.

New fuel supplier New LOCA Analv11.s 6.

The number of fuel as:;emblies: a) in the core 133 Assemblies b) in the spent fuel pool 477 Assemblies c) spent fuel. pool storage capacity-729 Assemblies d) planned spent fuel pool Planned to be increased storage capacity with higher density spent fuel racks.

7.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

1995

• Capability of full cere offload of 133 assemblies lost.

o Prepareo by.S ~ M Date 7 - 6 't i e

r

-e.---

r-

-,--w-.-

.c me-

DOCKET NO. 50-285 UNIT NAME Fort Calhoun Station DATE July 9, 1991 UNIT SilVIDOWNS AND POWER REDUCTIONS COMPLETED BY M.L. Edwards TELEP110NE f4021 636-24s1 REPORT MONill June 1991 I

~

11 o oS Ucensee E 7 E

Ca;ee & Cerrective s-c_kf g

32 h Event j

k Action to No.

Date

$E E6 Report #

$g y

Prevers Rectriente E

91-03 910619 F

0 A

4 N/A WG VALVEX Power level reduced to 55% to repair condenser waterbox valves.

Repaired a failed shaft coupling and valve seat.

I l

l 1

2 3

4 F-Forced Ressort Methoct Ext @ft G - Instnr.ttons A-Equpment raflure l' xplain) 1-Manual for Preparation of Data r

S-Schedoted D-Maintenance or Test 2-Manual Scram Entry Sheets for Ueenece C-Refueing 3-Automatic Scram Event Report (i.U1) F3e (PFJREG-omt)

D-Reputatory Restriction 4-Other (Erpfaln)

E-Operator Training a Ucense Exarninatico 5

F-Adrrfatstative Exhibit 1 - Sar,e Source G-Operational Error

.ll-other (Expfnin)

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No.1 June 1991 Monthly Operating Report 1.

OPERATIONS

SUMMARY

A.

SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED Fort Calhoun Station operated at 75% power until June 16, 1991., when power was raised to 98% to meet seasonal demand. On June 19, 1991, power was reduced to 55% for repair of condenser waterbox vahas.

Following repairs to these valves on June 20. 1991, a power increase to 100% was initiated.

On June 20, 1991, a gas pressurc switch for house service transformer TIA-4 was tripped due to technician error, locking out 161KV offsite power.

The transfer to the 345KV system occurred without incident.

After investigation of the cause, the switch was reset and 161KV power was restored.

During June 1991, a hot weather test was petformed on emergency diesel generator DG-1.

The test results in conjunction with a detailed system analysis were used to support raising the ambient temperature operating limits on emergency diesel generators DG-1 and DG-2. to 110*F.

The following NRC Inspections took place in June 1991:

IR 91-09 Corrective Action IR 91-16 Resident's Periodic In.;pection IR 91-17 Radiation Protection IR 91-18 Security The following LERs were submitted:

l j

LER-91-04 R1 Offsite Power low Signal Outside Design Basis B.

RESULTS OF LEAK RATE TESTS The results of the reactor coolant leak rate tests for June 1991, indicate the the reactor coolant system (RCS) and chemical and volume l

control system (CVCS) are both relatively ler.k tight.

Total RCS leakage averaged about 0.12 gpm during June.

l l

The maximum leak rate for the month was recorded on June 20, 1991 when l

the total leak rate was 1.824 gpm and the unknown leak rate was 1.757 gpm.

The total leak rate dropped to 0.012 gpm and the unknown leak rate dropped to -0.054 gpm when the test was repeated.

The plant was undergoing power changes on June 20, 1991 which are believed to have sffected leak rate test accuracy.

l I

4.

---r P

~

Monthly Operating Report LIC-91-190R Page 2

+

C.

CHANGES, TCSTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT 10 10CFR50.59

~

Am1Ddment N L Descrintion None D.

SIGNIFICANY SAFETY RELATED hAINTENANCE FOR THE MONTH OF JUNE 1991 The raw water inlet valva (HCV-2883A) for com:onent cooling heat exchanger AC-10 would not shut using either tie control rcom or the local switch. A malfunction of the relay coil due to heat was the apparent cause of failure. The relay coil was replaced, Steam generator RC-28 pressure channel pressure indication controller (A/PIC-905) power supply failed due to the age of the component.

The power supply was replaced.

The component cooling water outlet valve solenoid valve (HCV-478-20) for spent-fuel pool heat exchanger AC-8 developed an air leak.

The possible cause of failure was aging / cyclic fatigue and the solenoid valve was replaced.

Maintenance activities on charging pump CH-10 included:

Replaced plunger alignment parts in the gear box.

Overhauled the hydraulic end of the pump.

Installed new style packing.

Disassembled, cleaned, inspected, replaced beHows gasket:., saa' and disc on the discharge relief valve (CH-181).

Maintenance activities on Diesel Generator #1 included.

Replaced jacket water thermostats and 0-rings.

Replaced the glycol solution with water and rust

< h+Mtor.

Representatives from the furmanite Company were brouaht in to reinject the leaking inlet fIange on pressurizer (RC-4) rii "alve RC-142.

c

,,.._.m

1 s

l OPERATING DATA REPORT L

)

l DOCKET NO. 50-285 l

DATE n7lin/q1

)

COMPLETED BY MIFawnrds l

TELEPHONE t unH nn-2451 OPERATING STATUS

1. Unit Name: Fort Calhoun Station Not'5

2. Reporting Period: May 1991 Revised on July 10, 1991

3. Licensed Thermal Power (MWt). 1500 because of errors in Year-

4. ' Nameplate Rating (Gross MWel:

502 to-date and cumulative 478 columns.

Lines revised are J

5. Design Electrical Rating (Net MWe):

marked by "/".

l

6. Maximum Dependable Capacity (Gross MWe): 502

(!

7. Maximum Dependable Capacity (Net MWe):

478 S. If Changs Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Give Reasons:

N/A

9. Power Level To which Restricted,if Any (Net MWel: N/A

10. Reasons For Restrictions.lf Any:

N/A This Month Yr.-to.Date Cumulative

- II. Ilours in Reporting Period 744.0 3,623.0 154,993.0 /

l

12. Number Of Hours Reactor Was Critical 744.0 3,443.0 120,231.7

/

13. Reactor Reserve Shutdown Hours 0.0 0.0 1,309.5

14. Hours Generator On Line 744.0 3,432.2 118,862.1

/

15. Unit Reserse Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 838.257.3 3,962,661.1 155,246,150.4

/

17. Gross Electrical Energy Generated (MWH) 273,060.0,,_,

1,309,706.0 51,059,832.2

/

18. Net Electrical Energy Generated (MWH) 256,829.8

' 235,429.0

_48,720,205.3

/

19. Unit Service Factor 100.0 94.7 76.7

/

20. Unit Availability Factor 100.0 94.7 76.7

/

21. Unit Capacity Factor (Using MDC Nett 72.2 71.3 65.8

/

22. Unit Capacity Factor (Using DER Neti 72.2 71.3 65.8

/

i -

23. Unit Forced Outage Rate 0.0 5.3 3.6

/

24. Shutdowns Scheduled Over Nest 6 Months IType, Date, and Duration of Each t:

None 25, if Shut Down At End Of Report Period. Estimated Date of Startup:

N/A

26. Units in Test Status (Prior to Commercial Operationi:

Forecast Achieved l

INITI AL CRITICA LITY l

INITIAL ELEC TRICITY N/A COMMERCIAL OPER ATION (9/77)

-