ML20125E050

Monthly Operating Rept for Nov 1992 for Fcs,Unit 1

ML20125E050
Person / Time
Site:	Fort Calhoun
Issue date:	11/30/1992
From:	Cavanaugh G OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20125E049	List: ML20125E047 ML20125E050 ML20125E053
References
NUDOCS 9212160163
Download: ML20125E050 (6)

Text

. .

. l' ,

ENCLOSURE 1 OMAHA PUBLIC POWER DISTRICT fort Calhoun Station Unit No. 1 November 1992 Monthly Operating Report

1. OPERATIONS

SUMMARY

Du ing November 1992, Fort Calhoun Station operated at a nominal 100%

power, in ths October 1992 Monthly Operating Report, OPPD reported that operational restrictions were in place as a result of the exchange of the two control channels with two safety channels of nuclear instrumentati'an.

These restrictions currently limit the station to an "all rods-out" l :onfiguration. The restriction will remain in place until fMher testing or analysis is completed which supports operation in a rodded configuration.

Annual licensed operator requalification examinations were completed in November.

Repair work has been ongoing for the travelling screens in the Intake Structure. Monitoring of turbine control valves continued during November with minor valve movement noted on several occasions.

The following NRC inspections were completed during November 1992:

14.Mg.,. Title 92-29 Honthly Resident Inspection 92-31 Plant Procedures The following voluntary LER was submitted during November 1992:

LER No. LER Date Description 92-029 11/06/92 Intake of Radioactive Material

2. LA.1 /ALVES OR PORV CHALLENGES OR FAILURES WHICH OCCURRED There ere no PORV or relief valve challenges or failures during November.

3. I M LTS OF LEAK RATE 0 1S Total _ RCS leakage during the month averaged less than 0.2 gpm with no significant changes throughout the month. The Icakage was composed of approximately 75% "Known" leakage to the Reactor Coolant Drain Tank (RCDT) and 25% ' Unknown" leakage. "Un',.nown" leakage is the arithmetic difference between Known leakage and Total 1(akage. The RCS leakage rate appears to be steady with no adverse trends noted.

9212160163 921214 PDR ADOCK 05000295 R PDH

Month 1'y Operating Report November 1992 Page 2 l

4. C Ah G[S. T [S"S AND 1 XPERIMEN"5 REQUIRING NUCLEAR REGULATORY COMMISSION A.TF0 llZAT: 0h PURSlJAiT 10 100 :R50.59 ,

Amendment No. Description 148 This amendment revised the Technical Specifications (TS) to change the limitations associated with the regulated control element asseinbly insertion limits duri hot standby and power o for TS 2.10.2 4?b, 2.10.2i;7)2and c.

2.10.2(7)perations The amendment also mod ftes TS 2. ;,0. i to achieve consistency with the CombustionE(9) in)eering Standard TS as contained in NUREG 0212, R ision 2.

5. SIGNIFICANT SAFETY RELATED MAINTENANCE FOR THE MONTH OF NOVEMBER 1912 e Component cooling water pump AC-3C was rebuilt.

• The diaphragm was replaced on the boric acid makeup valve operator FCV-269 0.

• Power supplies for the SIRWT level indication 'oop instruments LQ-381 & LQ 382 were replaced.

6. OPERATING DATA REPORT Attachment !

7. AVERAGE DAILY UNIT POWER LEVEL Attachment !!

8. UNIT SHUTDOWNS AND POWER REDUCTIONS Attachment 111

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

. _ - = . . _ _ . _-

ATTACHMENTI OPERATING DATA REPORT DOCKET No. 50-285

-T UNIT FDRT CALHOUN 5~TK~TUD DATE btttM52R 6~9 1792 COMPLETED BY ~G. R.~~CAVANAUGR OPERATING STATUS TELEPHONE (402) 636-fD 4

l. Unit Names FORT CALHOUN STATION

2. Reporting Period NOVfR6ElfT9T2~ NOTES

- 3. Licensed Thermal Power (MWt): 1500 j 4. Nameplate Rating (Gross MWe): 56T I- 5. Design Elec. Rating (Net MWe) DiT l 6. Max. Dep. Capacity (Gross MWe): ~~~502_

1 7. Max. Dep. Capacity (Net MWe): 478 j 8. If changes occur in Capacity Ratings (3 through 7) since last report, j give reasons:

NA i

1

9. Power Level to which restricted, if any (Net MWe): NA i -

l 10. Reasons for restrictions, if anyt j NA 4

THIS MONTH YR-TO-DATE CUMULATIVE:

I 11. Hours in Reporting Period........... 720.0 8040.0 168170.0:

i 12. Number of Hours Reactor was Critical 720.0 SDT7X 12Mi6D

13. Reactor Reserve Shutdown Hours...... .0 .0 D09. 5 =

14.. Hours Generator On-line............. "D O . 0 4942.1 1283T9 2-

15. Unit Reserve Shutdown Hours......... .0 .0 .6:

16. Gross Thermal Energy Generated (MWH) ~~1T7 6 0 0 8 . 3 6829 5T4'~f 168453299.9

17. Gross Elec. Energy Generated (MWH).. 364954.0 2286521.0 ~Tf4 6 2647. 2 :

18. Net Elec. Energy Generated (NWH).... 349446.6 ~ TDT 3T33 5290909f.~9:

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

~

100.6 61. f 76.3!

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

~~

100.0 61.5 76.3

21. Unit Capacity Factor (using MDC Net) 101.6 56.f 68.4'

22. Unit Capacity Factor (using DER Net)

~

101.6 56 T 66.6

23. Unit Forced Outage Rate............. .0 15~f 4.4.

l 1 24. Shutdowns scheduled over next-6 months (type, date, and duration 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

L

ATTACHMENT 11

. AVERAGE DAILY UNZT POWER LEVEL 4

DOCKET NO. 50-285 ~

UNIT YdRT dKL~HDtlif STATION DATE DECEMBER 09 1992 COMPLETED BY G. R. CAVANAUGh TELEPHONE TW2 ) 636-2474 MONTH NOVEMBER 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe* +' (MWe-Net) 1 48g 17 485 2 485 18 485 3 485 _

19 485 4 486 20 485 5 486 21 485 6 486 22 485 7 486 23 485 8 485 24 486 9 485 25 486 10 485 26 485 11 485 27 485 12 485 28 485 13 485 29 485 14 486 30 485 15 486 31 NA 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 FoW Calhoun St.

DATE December 9. 1992 COMPLETED BY G. R. Cavanaugh' TELEPHONE (402) 636-2474 REPORT MONTH November 1992 No. Date Type' Duratana Reme.m* Method of Ucenace Symem conement Caune & Conective (Hours) Shaumg Eveva Code' Code' Action in Dmes Reactor

• Report # Prevent Recurwace None - - - - - - - - During Neember 1992. the piers operated at a monunal 100% p wer.

I I

i I

1 2 3 4 F: Forced Reame: Method: Exhibst G - Instructicas 5: Scheduled A-Equipment Failure (Explain) 1-Manual fw Preparation of Data B-Mairmenance or Tem 2-Marmaal Scram. Entry Sheets for Ucensee C-Refueling 1-Awdc Scram. Eves Report (LER) File (NUREG4161)

D Regulatory Restriction 4-Other (Explain)

E44wrator Training & Uceme Examination F-Administrative G4)perations! Enw (Explain) ExLibit 1 - Same Source H4)ther (Explain)

(9@

l .

ATTACHMENT IV Refueling Information

, fort Calhoun - Unit No. 1 Report for the month ending November 1992

1. Scheduled dated for next refueling shutdown. .Sfplember 1993

2. Scheduled date for restart following refueling. November 1993

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

a. If answer is yes, what, in general, will I these be?

Incorporate specific 1 requirements resulting from reload safety analysis.

l b. If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to 4

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.Scheduleddate(s)forsubmitttnformation.

licensing action and support in proposed June 1993

5. Important licensing considerations associated with refueling, e.g., new o~ different fuel design or supplier unreviewed design or performance analysis melhods, significa:1t chan design, new operating proctdures. ges in fuel None Planned

6. The number of fuel assemblies: a) in the core _133 Assemb'ies in the spent 529 Assemb' ies b) fuel pool c) spent fuel pool storage capacity 729 Assemblies d) planned spent Planned to be fuel pool increased with high storage capacity density spent fuel racks.

4

7. The )rojected date of the last refueling that can be disclarged to the spent fuel pool assuming the present licensed capacity. 1995*

• Capability of full core offload of 133 assemblies lost. Reracking to be performed between the 1993 and 1995 Refueling Outages.

Prepared by d" M Date \ v 6 <V

_,