LIC-96-0152, Monthly Operating Rept for Sept 1996 for Fort Calhoun Station Unit 1

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

ML20129C414
Person / Time
Site:	Fort Calhoun
Issue date:	09/30/1996
From:	Edwards M, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-96-0152, LIC-96-152, NUDOCS 9610240018
Download: ML20129C414 (7)

Text

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$DDR Omaha PublicPowerDistrict 444 South 16th Street Mall Omaha NE68102-2247 \

l October 14, 1996  !

LIC-96-0152 j i

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

Reference:

Docket No. 50-285

SUBJECT:

September 1996 Monthly Operating Report (MOR) f Enclosed please find the September 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.

Sincerely, i

Id$I T. L. Patterson Division Manager Nuclear Operations

TLP/mle Enclosures [bOk I c: Winston & Strawn L. J. Callan, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector R. J. Simon, Westinghouse INP0 Records Center

.aAGO 9610240018 960930 PDR ADOCK 05000285 R PDR g 45 5124 Employment with Equal Opportunity

. LIC-96-0152 Enclosure Page 1 l OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1

SEPTEMBER 1996 4

Monthly Operating Report i -1. OPERATIONS

SUMMARY

L i During the first half of September, Fort Calhoun Station (FCS) operated at a

, nominal 100% power level . On September 20 at 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br />, a power reduction

was commenced. Power was slowly reduced over a two day period stabilizing around the 70% level where it was maintained until September 28. A second i

power reduction began on September 28 at 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br />, with the power level

reduced to approximately 45% by September 29. These power reductions were l performed to minimize fission gas releases to containment and dose to s personnel for the upcoming refueling outage in October. Normal plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed during the month.

There are 66 incore nuclear detectors failed, rendering 18 of the 28 detector strings inoperable. Preparations have been made to replace all 28.incore detector strings during this refueling outage.

2. SAFETY VALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED During the month of September, no power operated relief ' valves (PORV) or primary system safety valve challenges or failures occurred.  ;

3. RESULTS OF LEAK RATE TESTS .

1 The reactor coolant system (RCS) leak rate was steady throughout the month continuing the trend of minimal RCS leakage following the March 96 maintenance _ outage. September daily leak rates were constant at slightly above 0.1 gpm except for several daily increases caused by charging pump i packing leaks. No degrading trends were noted.

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i LIC-96-0152 Enclosure Page 2

4. CHANGES. TESTS AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZATION PURSUANT TO 10CFR50.59 Amendment No. Description 175 The Amendment changes Sections 2.3 and 2.4 of the  !

Technical Specifications to require additional restrictions on the component cooling water system heat exchangers.

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF SEPTEMBER 1996

)

Replaced worn carbon bushing, pump housing and shaft for Charging Pump CH-1-C ,

- Replaced high voltage shutdown card on 125V Battery Charger No. 2 l

- Rewired limit switches on operators for Containment Isolation Valves l HCV-1560A/B i

- Replaced circuit breakers in Cubicles MCC-3A2-801 and MCC-3A2-F04 l Replaced optics lamp on Toxic Gas Monitor YIT-6288A I l

- Several General Electric (GE) Model CR120A relays were replaced with GE Model CR120AD relays l Adjusted terminal lug to ensure proper cleerance for the moveable contact on 86B/CSAS relay

6. OPERATING DATA REPORT Attachment I

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III

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

Attachment IV

. ATTACHMENT I OPERATING DATA REPORT l

DOCKET NO. 50-285 --~

UNIT TdRT CALHDON SYATIdR DATE UCTOBER 07,1996 COMPLETED BY M. L. EDWARDS ,

OPERATING STATUS TELEPHONE (402) 533-6929  !

l. Unit Name: FORT CALHOUN STATION

2. Reporting Period: SEPTEMBER 1996 NOTES

3. Licensed Thermal Power (MWt): 1500

4. Nameplate Rating (Gross MWe): 502

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5. Design Elec. Rating (Net MWe): 4 75~  !

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

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

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

N/A ,

l

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 6575.0 201769.0

12. Number of Hours Reactor was Critical 720.0 6002.8 -159710.8

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

14. Hours Generator On-line............. 720.0 5961.9 157942.4

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

16. Gross Thermal Energy Generated (MWH) 959739.6 8645297.4 211331605.7

17. Gross Elec. Energy Generated (MWH).. 317016.0 2893197.9 69826923.1

18. Net Elec. Energy Generated (MWH).... 300824.8 2757694.5 66615063.3

19. Unit Service Factor................. 100.0 90.7 78.3

20. Unit Availability Factor............ 10_0.0 90.7 78.3

21. Unit Capacity Factor (using MDC Net) 87.4 87.7 71.3

22. Unit Capacity Factor (using DER Net) 87.4 87.7 69.7

23. Unit Forced Outage Rate............. .0 6.1 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 44 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

ATTACHMENT II AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT FORT CALHOUN STATION DATE OCTOBER 07,1996 COMPLETED PY M. L. EDWARDS TELEPHONE (402) 533-6929 MONTH SEPTEMBER 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 470 17 478 2 470 18 479 3 470 19 479 4 470 20 480 5 470 21 433 6 469 22 326 7 470 23 319 8 471 24 319 9 472 25 319 10 472 26 320 11 473 27 321 12 473 28 313 13 475 29 205 14 477 30 188 15 477 16 477 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.

l

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

DATE October 7. 1996 i COMPLETED BY M. L. Edwards TELEPHONE (402) 533-6929 REPORT MONTH September 1996 j Csuse;& Corrective!

s No/ ;_ Date ; l Type: ; Ddration/ :LReason? 1 Method'60 (iiLicensee.f :L Sysiems LComponentf 13 '  ;(Hours)g

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r 2 :;

i:; Shutting] _ JEvedti_ hCodey [ Code' . .. :: Action'tb7

[ Down:f.. ::. Report No/ iPrevent' Recurrence ?

7  ? Reactor'!:

96-04 960921 S 0 H 4 N/A ZZ ZZZZZZ On September 20 at 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br />, a power reduction was commenced.

96-05 960928 S 0 H 4 N/A ZZ ZZZZZZ Power was slowly reduced over a two day period stabilizing around the 70% level where it was maintained until September 28. A second power reduction began on September 28 at 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br />, with the power level reduced to approximately 45% by September 29. These power reductions were performed to minimize fission gas releases to containment and dose to personnel for the upcoming refueling outage in October.

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)

g

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Attachment IV l

Refueling Information Fort Calhoun Station Unit No.1 Report for the month ending: September 30. 1996

1. Scheduled date for next refueling shutdown. October 5, 1996 1 2. Scheduled date for restart following refueling. November 17, 1996

! 3. Will refueling or resumption of operations j thereafter require a technical specification Yes

change or other license amendment?

! a. If answer is yes, what, in general, will these 1) Allow use of source material i be? for fuel assemblies.

i 2) Allow use of ZIRLO' fuel l cladding.

} b. If answer is no, has the reload fuel design i

and core configuration been reviewed by your N/A Plant Safety Review Committee to determine i

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 1) Source material change was i licensing action and support information. submitted August 23, 1996. i'

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

l

5. Important licensing considerations associated  !

with refueling, e.g., new or different fuel For Cycle 17, the new fuel batch design or supplier, unreviewed design or will contain mid-grid design performance analysis methods, significant changes changes to mitigate future grid-to-in fuel design, new operating procedures. rod fretting failures.

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 1083 Assemblies capacity

7. The projected date of tt last refueling that car, be discharged to the sr W fuel pool assuming the 2007 Outage present licensed capacity.

Prepared by: ( Date: /o//o/i/e

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