LIC-95-0172, Monthly Operating Rept for Aug 1995 for Fort Calhoun Station

Monthly Operating Rept for Aug 1995 for Fort Calhoun Station

ML20092G349
Person / Time
Site:	Fort Calhoun
Issue date:	08/31/1995
From:	Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-95-0172, LIC-95-172, NUDOCS 9509190254
Download: ML20092G349 (7)

Text

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3;; f Omaha Public Power District l 444 South 16th Street Mall l i

Omana. Nebraska 68102-2247 402/636-2000 September 15, 1995 l LIC-95-0172 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

August 1995 Monthly Operating Report (MOR)

Enclosed please find the August 1995 MOR for Fort Calhoun Station (FCS)

Unit No.1 as required by FCS Technical Specification 5.9.1.

If you should have any questions, please contact me.

Sincerely, A 9 w dl .% r O' g c_ N T. L. Pait son Division Manager Nuclear Operations TLP/dll Enclosures c: Winston & Strawn i L. J. Callan, NRC Regional Administrator, Region IV l S. D. Bloom, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector R. T. Pearce, Combustion Engineering R. J. Simon, Westinghouse INP0 Records Center 45 5124 r ;* ' " , *, Employment w:th Equat Oppwtunity

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LIC-95-0172 Enclosure Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 AUGUST 1995 Monthly Operating Report

1. OPERATIONS

SUMMARY

During the month of August, Fort Calhoun Station (FCS) operated at a

nominal 100% power until 1114 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23877e-4 months <br /> on August 24th. At that time, the plant experienced .n automatic reactor trip and associated diesel generator (DG) s art. The trip occurred during the performance of the Diverse Scram Sy.nm Actuation Relay Operability Test, when a licensed operator inadvertently repositioned the incorrect switch from TEST to NORMAL. All systems responded normally to the trip with the exception of the DG-1 accelerating to full speed vice idle speed. After evaluation of the DG-1 electrical system conditions, this OG-1 full speed event was reported on August 28th in accordance with 10 CFR 50.72(b)(1)(ii)(B). The reactor was taken critical at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> on August 26th and was generating at 100% capacity by August 29th. Reactor criticality was delayed because of a failure of the motor brake on one of the Control Rod Drive Motors.

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of August, no Power Operated Relief Valves (PORV) or Primary System safety valve challenges or failures occurred.

3. RESULTS OF LEAK RATE TESTS The Reactor Coolant System (RCS) leak rate was steady until August 26th

when the amount of "Known" leakage increased above its nominal value for the month. This increase corresponded with an ir. crease in Control Element Drive Mechanism (CEDM) #15 temperature. The increase in CEDM #15 temperature was noted when the rod was exercised while performing Technical Specification required surveillance testing following the August 24th reactor trip.

The increased RCS leakage, as seen in the "Known" leak rate, is collected by the Reactor Coolant Drain Tank (RCDT). The RCDT receives leakage from a large number of sources in containment including the CEDM leak-offs.

From inspection activities, the increase in leakage appears to be completely contained in the RCDT with no increase noted in the containment sump or visible signs of leakage in containment. The "Known" leak rate stabilized at a leak rate of approximately 0.32 gpm with a " Total" leak rate of slightly above 0.40 gpm during this report period.

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LIC-95-0172- .

Enclosure

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4. CHANGES. TESTS AND EXPERIMENTS RE0']dRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description None S. -SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF AUGUST 1995

- Installed a temporary modification on Reactor Coolant Temperature Indicator D/T1-122H due to a faulty RTD

- Replaced Raw Water Pump AC-10A with a rebuilt unit

- Replaced the motor brake package on CEDM RC-10-08 ,

• Installed Firmware Upgrade to QSPDS Channels A & B

6. OPERATING DATA REPORT Attachment I ,

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III 4

9. REFUELING INFORMATION. FORT CALHOUN STATION UNIT N0. 1 Attachment IV l

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. .. ATTACHMENT I OPERATING DATA REPORT DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE SEPTEMBER 06,1995 COMPLETED BY D. L. LIPPY OPERATING STATUS TELEPHONE (402) 533-6843

l. Unit Name: FORT CALHOUN STATION

2. Reporting Period: AUGUST 1995 NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

5. Design Elec. Rating (Net MWe): 478 2

6. Max. Dep. Capacity (Gross MWe): 502

7. Max. Dep. Capacity (Net MWe): 478

8. If changes occur in Capacity Ratings (3 through 7) since last report, give reasons:

JL/A

9. Power Level to which restricted, if any (Net MWe): N/A

10. Reasons for restrictions, if any:

N/A THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period........... 744.0 5831.0 192265.0

12. Number of Hours Reactor was Critical 705.0 4361.1 150779.0

13. Reactor Reserve Shutdown Hours...... .6 . 6- 1309.5

14. Hours Generator On-line............. 691.6 4277.2~ 149051.5-

15. Unit Reserve Shutdown Hours......... .6 .0 . 6- l

16. Gross Thermal Energy Generated (MWH) 989936.2 6154493.1 198303193.6 l 65450800.2

17. Gross Elec. Energy Generated (MWH).. 320816.0~ 2045918.0

18. Net Elec. Energy Generated (MWH).... 304623.0~ 1948616.0 62440408.3

19. Unit Service Factor................. 93.0 73.4 77.5 l 20. Unit Availability Factor............ 93.0 73.4 7 7 . 6~

21. Unit Capacity Factor (using MDC Net) 85.7] 69.9 70.2 ,

22. Unit Capacity Factor (using DER Net) 85.7 69.9 68.6 l

23. Unit Forced Outage Rate............. 5.4 5.8 4.1 l

24. Shutdowns scheduled over next 6 months (type, date, and duration of each):

N/A

25. If shut down at end of report period, estimated date of startup:

26. Units in test status (prior to comm. oper.): Forecast Achieved INITIAL CRITICALITY ~

i INITIAL ELECTRICITY N/A COHMERCIAL OPERATION

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ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE SEPTEMBER _ (T6,199 5 COMPLETED B'l D. L. LIPPY

$ TELEPHONE (402) 533-6843 MONTH AUGUST 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,

(MWe-Net) (MWe-Net) ,

1 466 17 466 2 468 18 464 i 3 468 19 463 4 466 20 465 5 465 21 466

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l 6 465 22 466 I 7 467 23 466 i

) 8_ 465 24 209  ;

9 463 25 0 10 463 26 13

11 463 27 98 i 12 462 28 297 i

! 13 461 29 461

! 14 461 30 463

! 15 463 31 465 16 466 INSTRUCTIONS On this-form, list-the average daily unit power level in MWe-Net for each j j day in.the reporting month. Compute to the nearest whole megawatt.

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ATTACHMENT III DOCKET N0. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St. -?

DATE September 7. 1995 -

COMPLETED BY D. L. Liooy TELEPHONE (402) 533-6843 REPORT MONTH August 1995 iNo;; iDatei Typ#:- Duration _Reasorf iMethod3 TLicenseeJ System Component. t Cause & Corrective:

- Action to 7

'(Nours)L . . of ? 1 Event.'  ! Code"- *CodeF Shutting- 1 Report Prevent Recurrence L lDown. . 1 No.

l EReactor 8~

i 95-04 950824 F 39.1 H 3 95-005 ZZ ZZZZZZ At 1114 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23877e-4 months <br /> on August 24, 1995 the plant experienced a reactor trip and associated diesel generator (DG) start. The trip occurred during the performance of the Diverse Scram System Actuation Relay Operability Test, when a licensed operator inadvertently repositioned the incorrect switch from TEST to NORMAL. All systems responded normally to

( the trip with the exception of DG-1 going to full speed vice idle speed. Corrective action includes l

institutionalizing the use of peer checking for switch manipulations that could immediately cause a reactor trip. The reactor was taken critical at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> on August 26th.

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l 1 2 3 4 F: Forced Reason Method: Exhibit F - Instructions

$: Scheduled A-Equi ment 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-0161)

D-Regulatory Restri ction 4-Other (Explain)

E-Operator Training & License Examination F-Administrative 5 H-Other (Explain) Exhibit H - Same Source (9/77) 1

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Attachment IV Refueling Information Fort Calhoun Station - Unit No. 1 Report for the month ending Auaust 31. 1995

1. Scheduled date for next refueling shutdown. September 21. 1996

2. Scheduled date for restart following refueling. November 2. 1996

3. Will refueling or resumption of operations thereafter require a technical specification change or other license amendment? No

a. If answer is yes, what, in general, will these be? N/A

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

c. If no such review has taken place, when is it scheduled? Prior to November 1996

4. Scheduled date(s) for submitting proposed licensing action and support information. No submittal planned

5. Important licensing considerations associated i with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures. N/A

! 6. The number of fuel assemblies:

a) in the core 133 Assemblies b) in the spent fuel pool 618 Assemblies c) spent fuel pool storage capacity 1083 Assemblies

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the 4 present licensed capacity. 2007 Outaae Prepared by Chu Date 4 - a - 9 s'

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