ML19257B798

Monthly Operating Rept for Dec 1979

ML19257B798
Person / Time
Site:	Fort Calhoun
Issue date:	01/10/1980
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19257B797	List: ML19257B796 ML19257B798 ML19257B799
References
NUDOCS 8001180357
Download: ML19257B798 (8)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE January 10, 1980 COMPLETED BY B. J. Hickle TELEPIIONE h02-536 kh13 MONT11 December, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AEERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net)

I hhl.h 17 0.0 2 hh5.4 18 0.0 3 hhh.4 19 0.0 4 hhh 9 20 0.0 5 hhh.8 21 153.1 6 hhh 1 22 396.2 7 hhh 5 23 418 7 8 hh1.2 24 h10.0 9 hh3.7 25 h20.1 to hh3.5 26 425.9 Ig h44.8 27 h36.3-12 hhh.9 28 hhl.5 hhh.3 29 hhh.6

{3 34 hh3.4 30 ,

4h2.2 15 hh2.9 3 hhl.2 16 130 0 INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute in the nearest whole megawatt.

1770 330 8001180 3 5 7

OPERATING DATA REPORT DOCKET NO. 50-285 DATE January 10, 1980 C05tPLETED BY B. J. Hickle TELEPil0NE 402-536-4413 OPERATING STATUS Fort Calhoun Station Unit No. 1 N tes

1. Uni Name:

2. Reporting Period: December 1079

3. Licenwd Thermal Power (51Wt): 1420

4. Nameplate Rating (Gross 51We): 502 ,

S. Design Electrical Rating (Net SlWe): N57

6. Stasimum Dependable Capacity (Gross 51We): NO1

7. 51asimum Dependable Capacity (Net SlWe): SI

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

n/A

9. Power Lesel To Which Restricted. If Any (Net 51We): N/A

10. Reasons For Restrictions.lf Any: N/A This 51onth Yr.-to-Date Cumulative

11. Ilours in Reporting Period 744.0 8,760.0 54,937.0

12. Number Of flours Reactor Was Critical 633.8 8,436.6 44,401.6

13. Reactor Reserve Shutdown flours 0.0 173.5 1,309.5

14. Ilours Generator On-Line 628.3 8,385.0 43,451.1

15. Unit Resene Shutdown flours 0.0 0.O ~0.0

16. Gross Thermal Energy Generated (31Wil) 856,079.1 11,586,606.0 53,235,029 3 .

17. Gross Electrical Energy Generated (StWil) 283,702.0 3,855,967.9 17,660,229.6 18: Net Electrical Energy Generated (51Wil) 269,575.0 3,666,114.1 16,687,519.e

19. Unit Senice Factor ON N 95 7 79 1

20. Unit Availability Factor OO N 95 7 79 1

21. Unit Capacity Factor (Using 51DC Net) 79 3 91.6 67.0

22. Unit Capacity Factor (Using DER Net) 79.3 91.6 66.5

23. Unit Forced Outage Rate 15.6 2.3 4.5

24. Shutdowns Scheduled Oser Nest 6 31onths (Type. Date,and Duration of Each):

Refueling Outage, January 18, 8 Week Duration

25. If Shut Down At End Of Report Period. Estimated Date of Startup: N/A

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY INIIIA L ELECTRICITY C01151ERCIA L OPER All0N 1770 331 (9/77 ) ,

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKETNO.50-28s UNIT NAME Fort Calhoun #1 DATE January 10, 1960 COMPLETED BY B. J. llickle REPORT MONTil Deca"ba" 1979 TELEPilONE 402-530-4413

- E E No. Date g

.$ ? 3i; $23

,g g 5 Licensee Eg [*. Cause & Corrective 3g Event g? n.3 Action tu

$5 5 Ji gjj =!

e Report a mO O

!U Prevent Recurren.c 6

79-06 791216 F 115.7 A 1 N/A Reactor shutdown to conduct RC'P seal replacement.

I 2 3 4

- F: Forced Reason: Method: Exhibit G-Instructions y S: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data y B-Maintenance of Test ,

2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LER) File (NUREG.

o D-Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & License Examination F-Administrative 5 U G-Operational Error (Explain) Exhibit I - Same Source N - (9/77) 11-Ot her ( E xplain)

Refueling Information Fort Calhoun - Unit No.1 .

Pcport for the month ending December 31, 19,7_9 Scheduled date for next refueling shutdown. . January 18, 1980 1.

Scheduled date for restart following refueling. March 15, 1980 2.

3. Will refueling or resumption of operation thereaf ter require a technical specificaticn change or other Yes license arrendment?

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

Stretching power to 1500 MWth is planned in conjunction with the change in fuel supplier to Exxon.

b. If answer is no, has the reload fuel design and core configuration been revievied by your Plant Safety Review Comnittee to deter-mine whether any unreviewed safety questions are associated with the core reload,

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

Stretch Power Application

4. Scheduled date(s) for subntitting proposed licensing -Site Related Information, action and support information. Julv. 1979 - Submitted

-Core Related Analysis

5. Important licensing considerations associated with and Tech. Spec. Changes, refueling, e.g. , new or different fuel design or November, 1979 - Submitted supplier, unreviewed design or performance analysis nothods, significant changes in fuel design, new

operating procedures.

First use of Exxon fuel in Fort Calhoun.

Stretching power from 1420 MWth to 1500 MWth.- 1770 bb

6. The nirrber of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 157 c) spent fuel pool "

storage capacity 483 d) planned spent fuel pool "

storage capacity 483

7. The projected date of the last refueling that can be discharged to the spent fuel pool assuning the present licensed capacity. 1985 Prepared by Date January 2, 1980 y

OMAHA PU3LIC POWER DISTRICT Fort Calhc un Station Unit To.1 December 1979 Monthly Operations Report I. OPERATIO:IS SU:&ARY The plant operation continued at approximately 100", power during December with the exception of a short outage to replace reactor coolant pump seals .

The requirements of iUREG-0578 vere implemented on December 3,1979, as required.

All operations were normal during December.

A. PERFORMA' ICE CHARACTERISTICS LER Tumber De fic ie ncy Hone

3. CHAITGES IIT OPERATI:!G FETHODS None C. RESULTS OF SURVIILIA: ICE TESTS A:iD INSPECTIO:IS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix 3, were performed in accordance with the annual surveillance test schedule. The following is a su--nry of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident De fic ie ncy OI-881 ST-ENV-2 Thermal "'"~a easurements not co=pleted.

OI-882 ST-ESF-6 Diesel Generator DG-1 fail to start on primary air.

D. CHANGES, TESTS A'ID EXPERISENTS CARRIED OUI WITHOUT COMMISSIO:'

APPROVAL De sc ription

-Prece dure 1770 334 EEAR 79-23 CQE Storage areas - completed as designed.

M.C. 10388 Install clothes dryer and provide h80V power in laundry - completed per design.

Monthly Operations Report December 1979 Page Two D. CHANGES, TESTS A'ID EXPERI E::TS CARRIED OUT '4ITHOUT CO MSSION APPROVAL (Continued)

Procedure Dasc ription M.O. 17251 Installation of Variators on HCV-2877A/B, HCV-2878A/B and HCV-2879A/B completed as designed.

SP-RPS-5 11 79 - Excore Detector Sy=etric Offset Recalibration - all channels within tolerance ,

no calibration necessary.

SP-RPS-5 12-26 Excore Detector Sy=etric Offset Recalibration - all channels within tolerance, no recalibration necessary.

SP-CONT-2 Containment Purge Supply and Exhaust Penetration Type C Leak Rate Test - test results acceptable.

E. RESULTS OF LEAK RATE TESTS SP-CO:iT-2 completed on containment purge valves:

Results acceptable.

F. CHANGES I i PLA:IT OPEP.ATING STAFF

Tone G. TRAINI:TO Training for December consisted of Radiation Protection refresher for 1979 for all blue and red badge holders, fuel receipt, refuel-ing procedures and radiation protection classes for new contract people needed for refueling.

H. CHANGES, TESTS AND EXPERIE:ITS REQUIRING NUCLEAR REGULATORY C0!O!ISSION AUTHORIZATION PURSUANT TO 10CFR50.59 None 1770 335

/ ') .

7

/

/,/ s ., ,/-

Approved By c M m / lb

? .'.adager-Fort Calhoun Station

Menthly Cperations Reper:

Dece=ber 1979 page Three II. MAIUTEUA'!!E (Significant Safety Related) 1 M. O. < l Cate i Cescrirtion I Correc tiv ? A::icn i

2837 11-21-79 Pipe support ACH-195 needs to be Per approved procedure i strengthened as per I.E. Bulletin l 1 79-1h.  !

i 2879 11-27-79 Fabricate SIS-52A per I.E. Bulletin Per approved procedure l , 79-1h.

I I I 2836 11-21-79! Support ACH-19h needs to be Per approved procedure strengthened per I.E. Bulletin 79-14 ,

2796 11-20-79 Strengthened pipe support ACS-199 Per approved procedure per I.E. Bulletin 79-1h .

2794 11 79 ACS-208 requires additional support Per approved procedure per I.E. Bulletin 79-lh.

2686 11-10-79 Field inspection performed per Per approved procedure I.E. Bulletin 79-lh found non-con-fo rmance . Later ar.alysis reccc-mended retro-fit to precludes over-

. tressing of support.

2877 11-29-79 Fabricate new support '4LH-8a per Per approved procedure reccc=endation of I.E. Bulletin 79-lh.

2h37 11 79 SIS-32 Ancher Bolts / Shells found Installed bolts per procedure installed incorrectly per I.E.

Bulletin 79-02.

2h65 11-1-79 SIS-27A Anchor Bolts / Shells found Installed boltsper procedure installed incorrectly per I.E.

Bulletin 79-02.

28hh 11-27-79 ACH-236 needs modification per Completed per procedure I.E. Bulletin 79-14, 28h3 11-28-79 ACH-229 needs modification per Completed per procedure I.E. Bulletin 79-14.

2857 11-26-79 RPS - A Channel - TM/LP Calculator. Recalibrated 2886 29-79 Diesel Fire Pump - flange the lower Completed 1770 336 part of the recirculation line of the Diesel Fire Pump.

2825 11-21-79 Diesel Generator fuel oil filters - Completed change.

Monthly Operations Report December 1979 Page Four II. MAI: TE:LCICE (Significan: Safety Related) l . O .

• l Date i Des ription I Corrective A::icn d 2931 12 h-79 CH-1B Charging Pump - replace Completed

!. packing on dishcarge valves.

l. 2831 12-h-79 Ilev Fuel Inspection Stand - rebuild Completed brackets for a more secure arrange-me nt .

2936 12-3-79 T1A-3 secondary Lov Volt Alarm on Replaced AC voltage sensor CB-20 alarming spuriously. 27-Th/TlA-3 EEVAR.

2458 11-3-79 Perform ultrasonic inspection of Completed per SP-FW-1 hot feedwater piping per SP-FW-1.

2496 11 79 Perform radiograph of RC-2A and Completed per SP-FWRG-1 RC-2B =11n feedvater nozzle to safe end welds and safe end to piping velds per I.E. Bulletin 79-13 Rev.2.

1860 11-16-79 Inspect Diesel Generator Lube oil Confirmed that tube sheet is coolers for cracks around the outer soldered; however, no crack periphecy of the tube sheets as problem evident.

per I.E. Information :iotice 79-23 1770 337

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