ML20093G757

Monthly Operating Rept for Sept 1995 for Fort Calhoun Station Unit 1

ML20093G757
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1995
From:	Lippy D OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20093G743	List: LIC-95-0196, Forwards Monthly Operating Rept for Sept 1995 for Fort Calhoun Station Unit 1 & Corrected Pages to Monthly Operating Rept for Aug 1995 ML20093G757 ML20093G783
References
NUDOCS 9510190223
Download: ML20093G757 (7)

Text

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LIC-95-0196 Enclosure 1 Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 SEPTEMBER 1995 Monthly Operating Report

1. OPERATIONS

SUMMARY

During the month of September, Fort Calhoun Station operated at a nominal 100% power. Normal plant maintenance, surveillance and equipment rotation activities occurred during the month, in addition to scheduled on-line modification activities. Monitoring of the leaking Control Element Drive Mechanism (CEDM) mechanical seal continued.

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of September, no Power Operated Relief Valve (PORV) or  ;

Primary System Safety Valve challenges or failures occurred. i l

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3. RESULTS OF LEAK RATE TESTS Although above normal, the September Reactor Coolant System (RCS) leak rate was steady at approximately 0.4 gpm throughout the month. This leak rate remained steady following the reactor trip and resultant surveillance testing of the CEDMs on August 26, 1995.

The major contributor to the increase in RCS leakage has been classified as "Known" leakage. This leakage is being collected in the Reactor CoolantDrainTank(RCDT). The apparent leakage source was CEDM #15. The "Known" leak rate stabilized at 0.280 gpm.

The remainder of the leakage has been classified as " Unknown" leakage. l The " Unknown" leak rate varied from 0.1 to 0.25 gpm. The identified sources of " Unknown" leakage were Chemical and Volume Control System valves (located in the Auxiliary Building) leaking through or minor Charging System packing leaks.

9510190223 951013 PDR ADOCK 05000285

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LIC-95-0196 Enclosure'1 Page 2 i

4. . CHANGES. TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT ~TO 10CFR50.59 Amendment No. Description ,

No.-170 This amendment revised the Technical Specifications (TS) to relocate the axial power distribution limits to the Core.0perating Limits Report (COLR). ,

No. 171 This amendment changed several sections ir. the TS in accordance with the guidance of Generic Letter 93-05, "Line Item Technical Specifications Improvements ~ to Reduce Surveillance Requirements .for Testing During Power Operation."

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF SEPTEMBER 1995

. - Rebuilt packing cooling pump for Charging Pump CH-1A

- Replaced packing cooling pump for Charging Pump CH-1C due to lack of discharge pressure

- Replaced Raw Water Pump AC-10C due to normal wear  !

- Rebuilt Charging Pump CH-1A due to excessive leakage

- Replaced relay 41C for Emergency Diesel Generator #2 due to field flash failure

6. OPERATING DATA REPORT Attachment I 1

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II

8. UNIT SHUTDOWNS AND POWER REDUCTIONS )

i Attachment III

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

-Attachment IV t

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ATTACHMENT 7 '

OPERATING DATA REPORT

- DOCKET NO. 50-285 UNIT FORT CALHOUN STATION I DATE OCTOBER 06,1995 COMPLETED BY D. L. LIPPY OPERATING STATUS TELEPHONE (402) 513-6843

l. Unit Name: FORT CALHOUN STATION

2. Reporting Periodi 5EPTEMBER 1995 NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

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

6. Max. Dep. Capacity (Gross MWe): 50_2_

7. Max. Dep. Capacity (Net MWe): 478 4

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........... 720.0 6551.0 192985.0

12. Number of Hours Reactor was Critical 720.0 5081.1 151499.0

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

14. Hours Generator On-line............. 720.0 4997.2 149771.5

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

16. Gross Thermal Energy Generated (MWH) 1077617.7 7232110.8 199380811.3  ;

17. Gross Elec. Energy Generated (MWH).. -~159274.0 f405192.0

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65810074.2

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18. Net Elec. Energy Generated (MWH).... 342887.4 2291503.4 6278T29sT7-

19. Unit Service Factor................. 100.0 76.3~

77.6

20. Unit Availability Factor............ 100.0 76".3 77.6

21. Unit Capacity Factor (using MDC Net) 99.6

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73.2 70.4 ,

22. Unit Capacity Factor (using DER Net) 99.6 73.2 ~6 0. 7 l

23. Unit Forced Outage Rate............. .0 5.3 4.0 l

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

NONE.

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 ~~~~ l ~~_ T l

! ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL

- DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE- _ OCTOBER 06,1995 COMPLETED.BY D. L. LIPPY TELEPHONE (402) 533-6843 )

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MONTH SEPTEMBER 1995 i DAY  : AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 467 17 476 2 469 18 474 3 469 19 476 4 468 20 478 5 468 21 481 6 ~469 22 482 7 471 23 484 8 472 24 484 9 475 25 484 10 475 26 484 l l

11 476 27 483 j l

12 477 28 482 l l

13 476 29 480 l

14 475 30 480 l 15 475 31 N/A l

16 476 INSTRUCTIONS

.On this form, list the average daily unit power level in MWe-Net for each 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 October 6. 1995 COMPLETED BY D. L. Lipov' TELEPHONE (402) 533-6843 REPORT MONTH September 1995

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tNo; *Datel Typ/ Duration Reased . Method} SOcesseeL iSystem'  : Component s [Cause& Corrective.

(Hours)1 ..(off lEventj  :: Code *. . :CodeF J Action to u '

'Shuttingi ;Reporti Prevent Recurrencev

' Down l. . . VNo.

Reactor3 :

None.

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-0perator Training & License Examination F-Administrative 5 H-0ther (Explain) Exhibit H - Same Source l Z

(9/77)

Attachment IV Refueling Information Fort Calhoun Station - Unit No. 1 Report for the month ending September 30. 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? Yes

a. If answer is yes, what, in general, will Enrichment limit of spent these be? fuel racks is to be increased to at least 4.5 w/o from 4.2 w/o. This is necessary based upon the preliminary Cycle 17 core pattern development.

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. N/A

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

4. Scheduled date(s) for submitting proposed January 1996 (for soent licensing action and support information, fuel rack enrichment limit chanae)

5. Important licensing considerations associated 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: I a) in the core 133 Assemblies b) in the spent fuel pool 618 Assemblies c) spent fuel pool storage capacity 1083 Assemblies l

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the ,

present licensed capacity. 2007 Outaae i Prepared by M cdddU Date to-80-es' i i

4 l LIC-95-D196 Enclosure 2 .

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OMAHA PUBLIC POWER DISTRICT i FORT CALHOUN STATION UNIT N0. 1

" CORRECTED PAGES TO THE AUGUST 1995 MONTHLY OPERATING REPORT" I

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