LIC-93-0075, Monthly Operating Rept for Jan 1993 for Fcs,Unit 1

Monthly Operating Rept for Jan 1993 for Fcs,Unit 1

ML20128K653
Person / Time
Site:	Fort Calhoun
Issue date:	01/31/1993
From:	Edwards M, Gates W OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-93-0075, LIC-93-75, NUDOCS 9302180235
Download: ML20128K653 (7)

Text

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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 s

February 12, 1993 LIC-93-0075 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station PI-137 Washington, DC 20555

REFERENCE:

Docket No. 50-285 Gentlemen:

SUBJECT:

January 1993 Monthly Operating Report (MOR)

Enclosed is the January 1993 MOR for Fort Calhoun Station (FCS) Unit No. I as required by FCS Technical Specification Section 5.9.1.

if you should have any questions, please contact me.

Sincerely, W. N. W n

W G. Gates Vice President WGG/sel Enclosure c:

LeBoeuf, Lamb, Leiby & MacRae J. L. Milhoan, NRC Regional Administrator, Region IV R. P. Mullikin, NRC Senior Resident inspector S. D. Bloom, NRC Project Manager R. T. Pearce, Combustion Engineering R. J. Simon, Westinghouse NRC Office of Management & Program Analysis (2)

INP0 Records Center American Nuclear Insurers i

9302180235 430131

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OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 January 1993 Monthly Operating Report 1.

OPERATIONS

SUMMARY

During January 1993, Fort Calhoun Station operated at 100% power.

An operational restriction on control element assembly (CEA) movement which was in place since October 1992 as a result of the exchange of two control channels with two safety channels of nuclear instrumentation has been lifted. The analyses to support operation in a rodded configuration have i

been completed which allowed lifting of the restriction.

In January 1993, modification work on the switchgear halon system j

continued and a component cooling water (CCW) heat exchanger was cleaned.

A Technical Specification (TS) surveillance issue relative to boric acid storage tank (BAST) level instrumentation was discovered during the month.

Technical Specifications require a daily check of BAST level via two independent level sensors.

However, it was discovered that the two sources previously used (local & remote level indication)Tygon tubing on were from the same level indicator. A temporary modification installed each tank to provide alternate level indication.

The temporary modification, in conjunction with the existing instruments, returned the system to compliance. Details are contained in LER 93-001 dated February 8, 1993. A modification to permanently correct the problem is planned.

4 The following NRC inspections were completed during January 1993:

IER No.

Title 92-33 Routine Resident Inspection 93-01 Self-Assessment Activities 93-02 Routine Resident Inspection The following LERs were submitted during this reporting period:

LER No.

Descriotion

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92-031 Inoperability of Fire Water Suppression System 92-032 Failure to Satisfy Fire Watch Requirements for Impaired Halon System

-2.

SAFETY VALVES OR PORY CHALLENGES OR FA1 LURES WHICH OCCURRED There were no safety valve or PORV challenges or failures during January 1993.

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Monthly Operating Report January 1993 Page Two 3.

RESULTS OF LEAK RATE TESTS The reactor coolant system (RCS) leak rate averaged less than 0.250 gpm for the month of January. On January 27, "known" leakage to the reactor coolant drain tank (RCDT) increased to 0.396 gpm before decreasing several hours later to approximately 0.168 gpm. With the exception of this single fluctuation, the leak rate remained relatively steady with no degrading trends noted.

4.

CHANGES. T ES"S AND EXPERIMENTS RE0VIRING NUCLEAR REGULATORY COMMISSION AUTHORIZAT; 0B PURSUANT TO 10CFR50.59 Amendment No.

Description 149 This amendment makes changes to Technical Specifications 5.5 and 5.8 to reflect the implementation of a Qualified Reviewer Program for the review and approval of new procedures, and changes thereto, at Fort Calhoun Station.

5.

SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE 60 NTH OF JANUARY 1993 Cleaned and sandblasted CCW Heat Exchanger AC-1. Applied an epoxy coating to the tube sheets.

Rebuilt actuators and replaced springs on CCW Inlet Valves HCV-491A & HCV-491B for Component Cooling Heat Exchanger AC-lt per Engineering Change Notice (ECN 91-450).

Replaced a broken spring on the actuator for Suction Valve HCV-2937 for low Pressure Safety Injection Pump SI-18.

Repaired a pin-hole leak on the CCW Flange to the Oil Cooler and replaced the packing on Charging Pump CH-lC.

Replaced the packing on Spent Fuel Pool Cooling Pump AC-5B 6.

OPERATING DATA REPORT Attachment I 7.

AVERAGE DAILY UNIT POWER LEVEL Attachment II 8.

UNIT SHUTOOWNS AND POWER REDUCTIONS Attachment III 9.

REFUELING INFORMATION. FORT CALHOUN STATION UNIT NO. 1 Attachment IV

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Attachment I l

l OPERATING DATA REPORT DOCKET NO.

50-285 UNIT VD~RT CKfHOUF STKTYDN

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DATE ftEM04RV-~d8 1993 COMPLETED BY M.

L.

EDWARDS TELEPHONE (402) 636-2451 OPERATING STATUS

1. Unit Name:

FORT CALHOUN STATION

2. Reporting Period:

JKSUKNV~fM 3' NOTES

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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):

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 744,0 744.0 169658.0

11. Hours in Reporting Period...........

12. Number of Hours Reactor was Critical

~~~~711TD 714. U' lif354. 3

.0

.0 1309.5

13. Reactor Reserve Shutdown Hours......

14. Hours Generator On-11ne.............

744.0 744.0 129807.2~~

.0

.0

.0

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

16. Gross Thermal Energy Generated (MWH) ffl7001.5 iffl0DFT E7D'677567.8

17. Gross Elec. Energy Generated (MWH)..

378130.0 378130.0 56218930.2

18. Net Elec. Energy Generated (MWE)....

361238.7 361238.7

~ii632f75'TB~

100.0 100.0 76.5~

19. Unit Service Factor.................

~ 47 5 7

100.0 100.0

20. Unit Availability Factor............

21. Unit Capacity Factor (using MDC Net) 101.3 f01.6 68.7

22. Unit Capacity Factor (using DER Net) 101_.6 f01.6 6fTs'

.0

.0 4.3

23. Unit Forced Outage Rate.............

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

..N _MAY_2r 1993, THE PLANT IS SCHEDULED TO BE PLACED IN HOT-SHUTDOWN O

FOR AN 8 DAY MID-CYCLE MAINTENANCE OUTAGE.

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

26. Units in test status (prior to comm. oper.):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY M/A

~~~~

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COMMERCIAL OPERATIOM

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Attachment II

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-285 UNIT FORT CALHOUN STATION DATE F55iiUARY 08 Iff93 COMPLETED BY M. L.

EDWARDF TELEPHONE L4T2f6TB-2451

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MONTH JANUARY 1993 DAY AVERAGE DAILY POWER LEVEL DAY

-AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 486 17 485 l

2 486 18 485 3

486 19 485 4

486 20 485 5

486 21 485 6

486 22 485 7

486 23 485_

8 486 24 485 9

485 25 485 10 486 26-486 11 485 27 485 12 486 28 485 13 486 29 485 14 486 30 485 15

-486 31

'485 16 486 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..

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

DATE Febru*ry 8. 1993 i

COMPLETED BY M. L. Edwards TELEPHONE (402) 636-2451 -

REPORT MONTH January 1993 i

I No.

Date Type' Duratic Reamm' Mettw=1 of Licensee Symem Comr mers Cause & Conective I

f (Houn)

Shuning Event Code' Code' Action to Prevent Recurrence l

Down Reacter' Repors #

None During January 1993, the plant operated at a numanal 100% power.

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2 3

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4 Reason:

Methcut: Exhibit G - lastructions F: Forced A-Equipmers FaDure (Explain)l-Manualfur Preperation of Det:.

S: Scheduled B-Msmienance or Test 2 Manual Scram.Earry Sheets for Ucensee C-Refueling 3-Aetomatic Scram, Event Repart (LER) F4e (NUREG-0161)

D-Regulwory Rewriction 44Mher (Explain)

E4)perator Training & Ucense Examinaike F-Administrative f

G-Operstkmal Enor (Explain) Exhibit 1 - Same Source H4Aher (Explain) f m

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C Attachment IV Refueling Information Fort Calhoun - Unit No.:1.

Report for the month ending January 1993

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1. Scheduled dated for next refueling shutdown.

September 1993

2. Scheduled date for restart following refueling.

November 1993

3. Will refueling or resumption of operations-thereafter require a technical specification change or other license amendment?

Yes

a. If answer 1: yes, what, in general, will' these be?

Incorporate-specific-requirements resulting from-reload -

safety analysis.

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 licensing action and support information.

Aune 1993-

5. Important licensing considerations. associated with refueling, e.g., new-or different fuel design or supplier, unreviewed design or performance analysis methods, significant chan design, new operating procedures. ges in fuel None Planned -

6. The number of fuel assemblies:

al in the-core 133 Assemal" es

b) in the spent 529 Assemal-es-fuel pool c) spent fuel pool

-729 Assemblies d) p1anned spent-storage capacity Planned to be fuel pool-increased with high-storage capacity density

' spent fuel racks.

7. The. )rojected date of the last refueling that can be disclarged to the-spent fuel pool assuming the present licensed capacity.

1995*-

-o Capability of full core offload of 133 assemblies lost. Reracking to'be performed between

the 1993 and 1995 Refuel;ng Outages.

IPreparedby M MN-Date 2 9 l

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