LIC-96-0113, Monthly Operating Rept for Jul 1996 for Fort Calhoun Station Unit 1

Monthly Operating Rept for Jul 1996 for Fort Calhoun Station Unit 1

ML20116M142
Person / Time
Site:	Fort Calhoun
Issue date:	07/31/1996
From:	Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0113, LIC-96-113, NUDOCS 9608200048
Download: ML20116M142 (7)

Text

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Omaha Public PowerDistrict 1 444 South 16th Street Mall Omaha NE 68102-2247 l

August 15, 1996 I LIC-96-0113 l

l U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

Reference:

Docket No. 50-285

SUBJECT:

July 1996 Monthly Operating Report (MOR) i Enclosed please find the July 1996 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.

l Sincerely, l

4. 5.

! T. L. Patterson Division Manager Nuclear Operations  ;/

l l TLP/dll i I

Enclosures

[6b]f \

c: Winstor, & Strawn L. J. Callan, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager i W. C. Walker, NRC Senior Resident Inspector 1 R. J. Simon, Westinghouse

INPO Records Center 9608200048 960731 PDR ADOCK 05000285 R PDR

, 45 5124 Ernployrrent with Equal Orponunty

LIC-96-0113 Enclosure Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 July 1996 Monthly Operating Report i

1. ~ OPERATIONS

SUMMARY

l During the month of July 1996, the Fort Calhoun Station (FCS) operated at '

a nominal 100% power. Normal plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed during the month.

On July 17th at 0949 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.610945e-4 months <br />, a 1-hour non-emergency notification was made l to the NRC pursuant to 10 CFR 50.72(b)(1)(v), Lost Emergency Notification System (ENS), due to spurious intermittent ringing of the ENS phone. The

operability of the ENS phone was not affected, thus, the notification was made using the ENS phone. AT&T is troubleshooting the problem.

Three additional incore nuclear detectors failed in July 1996, rendering  ;

sixteen of the twenty-eight detectors strings inoperable. All failures  ;

l have occurred in detectors that were installed during the 1995 Refueling l Outage. The failed detectors are scheduled for replacement during the _ i i 1996 R2 fueling Outage.

In order to reduce fission gas releases to Containment and minimize doses received during outage activities, the 42-day 1996 Refueling Outage which was scheduled to connence on September 21, 1996 is now scheduled to begin on October 5, 1996. Around September 20th, it is planned that reactor power will be slowly reduced to take advantage of radioactive decay and continue the cleanup of the Reactor Coolant System (RCS).

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED 1

< During the month of July, no power operated relief valve (PORV) or primary I system safety valve challenges or failures occurred. l I

3. RESULTS OF LEAK RATE TESTS l 1

i The RCS leak rate was relatively steady throughout the month. The trend of minimal RCS leakage following the March 1996 outage continued. The July ' daily leak rates were constant at slightly above 0.1 gpm. No de-l grading trends'were noted this month.

LIC-96-0113 ,

Enclosure Page 2

4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description None

5. SIGNIFICANT SAFETY-RELATED MAINTENANCE FOR THE MONTH OF JULY 1996 Performed electrical work in the electrical control panel, fixed lube oil leaks and replaced thermostatic elements in tempcrature control valves for Emergency Diesel Generator DG-1.

Repaired a leaking weld on the Demineralized Water inlet to Charging Pump CH-1B Discharge Isolation Valve CH-364.

Replaced the solenoids on the Raw Water inlet / outlet valves HCV-2882A/B and HCV-2883A/B for the Component Cooling Water (CCW)

Heat Exchangers AC-1C and AC-1D, respectively.

Made a setpoint change to the Containment Noble Gas Radiation Monitor Remote Ratemeter RM-051 per the Technical Data Book.

Replaced breaker 1838-4 for CCW Pump Motor AC-3A-M Repaired Raw Water Strainer Motor RC-12A-M to correct oil seepage.

6. OPERATING DATA REPORT Attachment I

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III l

9. REFUELING INFORMATION. FORT CALHOUN STATION UNIT NO. I 1

l Attachment IV I

e ATTACHMENT I OPERATING DATA REPORT DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE AUGUST 05,1996 COMPLETED BY D. L. LIPPY OPERATING STATUS TELEPHONE (402) 533-6843

l. Unit Name: FORT CALHOUN STATION

2. Reporting Period: JULY 1996 NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): Sif

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

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:

N/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 5111.0 200305.0

12. Number of Hours Reactor was Critical 744.0 4538.8 ~T5Vif6.8

13. Reactor Reserve Shutdown Hours...... .0 .0 1309.5

14. Hours Generator On-line............. 744.0 4497.9 f56478.4

15. Unit Reserve Shutdown Hours......... .0 .0 .0

16. Gross Thermal Energy Generated (MWH) 1113012.0 6572933.0 209259241.3

17. Gross Elec. Energy Generated (MWH).. 3656'74.0 2210878.0 69144603.2

18. Net Elec. Energy Generated (MWH).... 348443.5 2108754.3 65966123.1

19. Unit Service Factor................. 100.0 88.0 78.1

20. Unit Availability Factor............ 100.0 88.0 78.1

21. Unit Capacity Factor (using MDC Net) 98.0 86.3 71.1

22. Unit Capacity Facror (using DER Net) 98.6~~ 86.3 69.6

23. Unit Forced Outage Rate............. .0 7.9 4.1

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

REFUELING OUTAGE SCHEDULED TO COMMENCE ON OCTOBER 5, 1996 WITH A PLANNED DURATION OF 42 DAYS.

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 -~

INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

' i ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 l UNIT FORT CALHOUN STATION -

L DATE AUGUST 05,1996 COMPLETED-BY 'D. L. LIPPY TELEPHONE (402) 533-6843 MONTH JULY 1996 I l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVE'.,  !

(MWe-Met) (MWe-Net)  !

1 463 17 470  ;

l 2 463 18 469 l f

l 3 466 19 466 i

i 4 468 20 464 -

5 470 21 466 6 470 22 468 7 468 23 468  ;

8 469 24 466

' t, 9 469 25 466 I 10 471 ,

26 467  ;

11 472 27 468 l

12 472 28 470 1 13 473 29 468

, 14 472 30 467 i

l

15 471 31 468 I

i 16 470 i

I i INSTRUCTIONS

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

i 4 i 4

I i, ,_ . - --. _. ... .. - . - - . _

1

t ATTACHMENT III DOCKET NO. 50-285 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St. ,,

DATE Auaust 6. 1996 COMPLETED BY D. L. Lippy ~

TELEPHONE (402) 533-6843 REPORT MONTH July 1996

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luds.= 7eani $M.o icifatn., e;fliessN$ $5Etiodi idceasee) $Osten? $CSuposeet -

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, Report < , PreventLeecsrrence . _

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1. Reactoh i ' ,

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. 1 2 3 4 ,

F: Forced Reason: Method: Exhibit F - 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-0161)

D-Regulatory Restriction 4-Other (Explain)

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

___- _ _ _ _ **w4 ^--.4 n " W"'** 8 ed *-- - -- - _ _ _ _ . _ . _ _ . _ - m.___.__ ___- _ . _ _ _ _ _

~

. Attachment IV

,, ., Refueling Information Fort Calhoun Station Unit No. 1 Report for the month ending: July 31.1996

1. Scheduled date for next refueling shutdown. October 5,1996

2. Scheduled date for restart following refueling. November 15, 1996

3. Will refueling or resumption of operations thereafter

! require a technical specification change or other Yes license amendment?

a. If answer is yes, what, in general, will these be? 1) Enrichment limit of spent fuel racks increased to at least 4.5 w/o from 4.2 w/o.

2) Allow use of ZIRLO' fuel cladding.

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

c. If no such review has taken place, when is it scheduled? N/A

4. Scheduled date(s) for submitting proposed licensing 1) Spent fuel rack enrichment

, action and support information. limit change was NRC approved l July 30,1996.

2) ZIRLO' change was submitted July 15, 1996.

5. Important licensing considerations associated with  ;

refueling, e.g., new or different fuel design or N/A supplier, unreviewed design or performance analysis .

methods, significant changes in fuel design, new l operating procedures.

I

6. The number of fuel assemblies:

a) in the core 133 Assemblies l 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 i l

discharged to the spent fuel pool assuming the 2007 Outage present licensed capacity.

Prepared by: Date: 8/#/4c-

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