LIC-95-0233, Monthly Operating Rept for Nov 1995 for FCS Unit 1

Monthly Operating Rept for Nov 1995 for FCS Unit 1

ML20095F521
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1995
From:	Lippy D, Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-95-0233, LIC-95-233, NUDOCS 9512190062
Download: ML20095F521 (7)

Text

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Omaha Public Power District 444 South 16th Street Mall '

Omaha, Nebraska 68102-2247 402/636-2000 December 13, 1995 LIC-95-0233 i

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

Reference:

Docket No. 50-285

SUBJECT:

November 1995 Monthly Operating Report (MOR) l Enclosed please find the November 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, T. L. Patterson Division Manager Nuclear Operations TLP/dll Enclosures 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 9512190062 951130 '/

PDR ADOCK 05000285 $

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45 5124 Employment with Equal Opportunity \g

LIC-95-0233 l Enclosure 1

,Page 1 OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 NOVEMBER 1995 Monthly Operating Report

1. OPERATIONS

SUMMARY

During the month of November, Fort Calhoun Station (FCS) operated at a nominal 100% power with the exception of a reduction to 99.3% for two days to allow a Chemical and Volume Control System Ion Exchanger to be placed in service. Normal plant maintenance, surveillance, equipment rotation activities and scheduled on-line modifications were performed during the month. Monitoring of a minor Control Element Drive Mechanism (CEDM) mechanical seal leak continued.

On November 8,1995, a one-hour non-emergency notification was made to the NRC pur suant to 10CFR50.72(b)(1)(ii)(B) and (C) regarding the potential for the 480VAC breaker trip devices to inadvertently operate due to electrical noise in the presence of a post-accident harsh environment.

Interim guidance for operating the breakers will remain in an Operations Memorandum until the devices are replaced.

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

3. RESULTS OF LEAK RATE TESTS Although above normal, the November Reactor Coolant System (RCS) leak rate was steady at approximately 0.3 to 0.4 gpm throughout the month. This leak rate remained relatively 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 Coolant Drain Tank (RCDT). The leakage source has been attributed to seal leakage from CEDM #15. The "Known" leak rate stabilized at approximately 0.25 gpm. The remainder of the leakage has been classified as " Unknown" leakage.

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LIC-95-0233

Enclosure 1

. 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 NOVEMBER 1995 Replaced the module for the Reactor Coolant (RC) Loop 2A cold leg temperature channel C/TT-122C due to fluctuating DC output Replaced the circuit board on static inverter B to correct a bypass / transfer control problem

- Replaced a current overload relay for the blowdown tank transfer pump FW-34B

- Rebuilt the recirculation relief valve VA-287 for containment hydrogen purge fan VA-80A

6. OPERATING DATA REPORT Attachment I

7. AVERAGE DAILY UNIT POWER LEVEL Attachment II 1

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment III

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

l

. ATTACHMENT I  ;

OPERATING DATA REPORT I i

DOCKET NO. 50-285 UNIT FORT CALHOUN STATION j DATE DECEMBER 06,1995 )

COMPLETED BY D. L. LIPPY l OPERATING STATUS TELEPHONE (402) 533-6B43 1

l. Unit Name: FORT CALHOUN STATION

2. Reporting Peri 63: NOVEMBER 1995 NOTES l

3. Licensed Thermal Power (MWt): 1500 1 40 Nameplate Rating (Gross MWe): 502-

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

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

7. Max. Dep. Capacity (Net MWe): 478 80 If changes occur in Capacity Ratings (3 through 7) since last report, give reasons:

N/A I

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

10. Reasons for restrictions, if any:

N/A 1

THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period........... 720.0 8016.0 194450.0

12. Number of' Hours Reactor was Critical 720.0 6546.1 152964.0 13.-Reactor Reserve Shutdown Hours...... .0 .0 1309.5~

14. Hours Generator On-line............. 720.0 6462.2 1512f675 15.- Unit Reserve Shutdown Hours......... .0 . D~ .0~

16. Gross Thermal Energy Generated (MWH) 1077059.9 9424320.5 20157302iTd~

17. Gross Elec. Energy Generated (MNH).. 3T6505. 0

~-

~3T49411TO 66554293.2 7002871.1

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18. Net Elec. Energy Generated (MWH).... 35dT71TT ~634T4663T F~~

19. Unit Service Factor................. 100.0 80.6" 77 78 80.6'

~-

20. Unit Availability Factor............ 100.0 77'.~8~

21. Unit Capacity Factor (using MDC Net) 102.0 78.4 7 0 . d~

22. Unit Capacity Factor (using DER Net) 102.0 78.4 69.0

23. Unit Forced Outage Rate............. .0 4.1 4.0

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

A MAINTENANCE OUTAGE IS SCHEDULED TO OCCUR FROM MARCH 16-23, 1996 TO_RE-PAIR / REPLACE DEGRADING CEDM MECHANICAL SEALS.

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 DECEMBERZ 0Clyi5 COMPLETED BY D. L. LIPPY TELEPHONE (402) S W 6843 MONTH NOVEMBER 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 487 17 487 2 486 18 488 3 486 19 488' _

I 4 487 _ 20 487 5 488 21 487 6 488 22 487 7 487 23 487 8 485 24 487 9 486 25 488 10 487 26 488 11 488 27 488 12 488 28 488 13 488 29 488 14 487 30 488 15 488 31 N/A ,

16 488 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each l day in the reporting month. Compute to the nearest whole megawatt. l

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l ATTACHMENT III DOCKET N0. 50-285

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l UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Fort Calhoun St.

DATE December 6. 1995 l

COMPLETED BY D. L. Lippy TELEPHONE (402) 533-6843 ,

REPORT MONTH November 1995 4No; LDate:: Tyfe' - iDuration iteAsd IMethed:! ilLicensee? iLSp tem';! (ComponenO [CausAYUorrehdve': '

. .. j;(. Action tej . . .

~

4 1(Nours)/ . . . .[of:s . .. Event :i 5 Cod ( i:: Code 4 lShuttiog? Report ^

jPrevent Becurrence)

Down L- . iNon' '

4 Rea: tor8::

GNE 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)  ;

4-Other (Explain)

D-Regulatory Restriction  ;

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

Attachment IV Refueling Information Fort Calhoun Station - Unit No. 1 Report for the month ending November 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 scent these be? fuel racks is to be increased to at least 4.5 w/o from 4.2 w/o. This is i necessary based uoan the oreliminary Cycle 17 core nattern develooment.

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 spent 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:

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

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. 2007 Outaae Prepared by iM Date n. - t . 9 r

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