ML19296A957

Monthly Operating Rept for Jan 1980

ML19296A957
Person / Time
Site:	Fort Calhoun
Issue date:	02/08/1980
From:	Hickle B OMAHA PUBLIC POWER DISTRICT
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NUDOCS 8002190524
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. f AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE February 8. 1980 COMPLETED BY B. J. Hickle TELEPIIONE h02-536 kh13 MONTil January. 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

I hhl.8 37 h03.3 2 hhl.6 gg 3hh.2 3 hkl.7 g9 0.0 4 hbl.0 20 0.0 _

S hh0.8 21 0.0 m 6 hh0.1 22 0.0 7 h39 h 23 0.0 8 h29.4 24 0.0 9 h22.6 25 0.0 10 h18.7 26 0.O gg h12.9 27 0.0 12 h08.9 28 00 13 h03.h 29 0.O g4 h01.h 30 0.0 15 h02.0 31 0.0 16 h0h.8 INSTRUCTIONS On this format. list the average daily unit power icvelin MWe Net for each day in the reporting month. Coinpute to the nearest whole megawatt.

(9/77) 00 021 90 ScR Y

OPERATING DATA REPORT DOCKET NO. 50-285 DATE February 8, 1980 CO.\lPLETED BY B. J. Hickle TELEPil0NE 402-536-4413 OPER ATING STATUS Notes

1. Unit Name: Fort Calhoun Station Unit No. 1

2. Reporting Period: January, 1980

3. Licensed Thennal Power (.\lWt):

1h20

4. Nameplate Rating (Gross .\tWe): 502

5. Design Electrical Rating (Net 51We): 457

6. Stasimum Dependable Capacity (Gross 51We): 481

7. 51aximum Dependable Capacity (Net 31We): N5I S. 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 31We): N/A

10. Reasons For Restrictions,if Any: N/A This 51onth Yr..t o.Da t e Cumulative

11. Ilours In Reporting Period Thh.0 Thh.0 55,681.0

12. Number Of Ilours Reactor Was Critical h32.9 h32.9 hh,834.5

13. Reactor Resene Shutdown flours 0.0 0.0 1,309.~5

14. Ilours Generator On.Line 430 5 h30 5 43,881'.6_

15. Unit Resene Shutdown llours 0.0 0.0 0.3

16. Gross Thermal Energy Generated (51Wil) 57h,730.9 57h,730.9 53,809,760.2

17. Gross Electrical Energy Generated (.\1Wil) 190,604.0 190,604.0 17,850,833.6 IS. Net Electrical Energy Generated (51Wil) 180,035.1 180,935.1 16,868,h54.9

19. Unit Senice Factor 57.9 57 9 76.8

20. Unit Availability Factor 57 9 ,

57 9 78.8

21. Unit Capacity Factor IUsing 51DC Net) 53.2 53.2 66.8

22. Unit Capacity Factor IUsing DER Net) 53.2 - __ 53.2 66.3

23. Unit Forced Outage 1(ate 0.0 0.0 h.5

24. Shutdowns Scheduled Oser Next 6 Slonths (Type. Date.and Duration of Each):

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: March 15, 1980

26. Units in Test Status tPrior to Conunercial Operation): N/A Forecast Achiesed INill A L CRi flCA LITY INITI A L ELECT RICI FY CO\l\ll.RCI A L OPrit AllON (9/77)

s UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-285 UNIT N etE Fort Calhoun #1 u

DATE February 6, 1980 COMPLETED BY B. J. Hickle REPORT MONTil January. 1980 TELEPilONE h02-596 kh13 e.

- E E

-, .5g 3 4 Y ~' Licensee [g j% Cause & Corrective No. Date g 3g 4 jg5 Event F? o- 3 Action to H j5 5 5gg Report n (E U  !'

O Prevent kecurrence C

80-01 800118 S 313.5 C 1 N/A Reactor shutdown for annual refuel-ing and maintenance outage.

I 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A. Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E. Operator Training & License Examination F Administrative 5 G-Operational Er ror (Explain) Exhibit I-Same Source (9/77) Il-Other ( E xplain )

Refueling Infontation Fort Calhoun - Unit Ib. 1 .

Report for the nonth ending January 31, 1980.

1. Scheduled date for next refueling shutdown. -

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

3. Will refueling or restrr.ption of operation thereaf ter require a technical specification change or other Yes license anendment?

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

Stretching power to 1500 ft4th is planned in conjunction with the change in fuel supplier to Exxon.

b. If aner is no, has the reload fuel design arr3 core configuration been reviewed by your Plant Safety Review Conmittee to deter-mine'dlether any unreviewed safety g estions 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 submitting proposed licensing -Site Related Information, action and support infonration. JulL_ '.979 - Submi tted

-Core delated Analysis

5. Important licensing considerations associated with and Teth. 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 ffWth.

6. The nturix2r of fuel assenblies: a) in the core 133 assemblies b) in the spent fuel pool 157 c) spent fuel 1xx>l "

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 assu;ning the present licensed capacity. 1985 Prepared by_ 6l/>rzfVl Date February 4, 1980 e a

OMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 January 1980 Monthly Operations Peport I. OPERATIONS SCIMARY The reaccor was operated in a coastdown mode until January 13 when shutdown for a scheduled refucling was initiated.

Operations supported many outage activities during January including plant shutdown, CEA uncoupling, and the Type A integraced leak rate test.

One new operator was added to the Fort Calhoun staff during the conth of January.

The normal surveillance tests have been completed and in-service tests required by the outage are in progress.

Requalification tests are being atninistered to all licensed operators.

A. PERFORMANCE CHARACTERISL _ -

LER Number Deficiency LER 79-20, During continuing inspections of accessible Rev. 1 piping being performed in accordance with IE Bulletin 79-02, three additional snubbers on the safety injection system piping vere found to be inopersble because of improper installation of the anchor bolts. :To signifi-cant occurrence took place. The probable consequences vould have been the inability of the snubbers to perform their design functions during a seismic event.

LER 79 22 With the reactor in a cold shutdown condition, all engineered safeguards equipment relating to RM-062 was tested for proper operation prior to a gas release. It was discovered that the 86A/CRHS relay failed to trip when RM-062 was placed in the alarm condition. This also resulted in a failure of the 86Al/ CEES relay to actuate. The redundant channels 86B/ CEES and 86E1/CRES vere operable and did actuate at the time of the 86A/CRES failure.

3. CHNiGES IN GPERATING ME"' HODS None

Monthly Operations Report January 1980 Page Two C. RESULTS OF SURVEILLANCE TESTS A'ID I:!SPECTICIIS Surveillance tests are required by the Technical Specifications Section 3.0 and Appendix 3, vere performed in accordance with the annual surveillance test schedule. The following is a s"--ary of the surveillance tests which results in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency OI-912 (ST-SI/CS-1) ECV-383 L valve failed to shut when the control switch was operated.

OI-911 (ST-EM h) Environ = ental Air Sampler had inoper-able flow totalizer.

OI-91L (ST-MSSV-1) MS-231 set at 1029 psig rather than 1010 psig.

The following are surveillance test where an unusual result occurred:

Surveillance Test No. Descrirtion ST-ESF-1 (F.2) Pressurizer Press. Channel Check -

C/ PIA-102Y tripped at wrong setpoint.

ST-RM k (F.1) Environmental Sampler Checks - Demaged environmental sampler.

ST-EM-2 (F.2) Process Monitor Checks - Incorrect EM-057 setpoints.

ST-ERM-1 (F.1) Environmental Sample Collections -

Enviromnental sampler excessive flow.

ST-ERM-1 (F.3) Environ = ental Sample Collections -

Environmental TLD missing.

D. CRANGES, TESTS AND FTPERI'4I2iTS CARRIZD OUT WITHOUT COMMISSION APPROVAL Procedure Description M.0. 65 PR's in Intake Str - - re.

DCR 78 kl Diesel Fire Pwn, Cooling Watcr.

• 3 Monthly Operations Report January 1980 Page Three D. CRANGES, TESTS AND EVERIMENTS CARRIED CUT WITECUT CC:GISSION APPROVAL (Continued)

Procedure Descrintion DCR 79-10h Leak Rate Rigs in Electrical Penetration Roca and Room 69/ Completed per design.

DCR 23-73 Site Completion Report : Modify Auxiliary Feedvater Pump FW-10 Controls.

SP-FAUD-1 Fuel Assembly Uplift Condition Detection.

Results indicate that the 150 lb. downward force criterion is being met.

SP-SOBS-1 Visual Inspection of welds in Stagnant, Oxygenated, and Borated Systems. No evidence of leakage or boric acid residues were found other than at valve stems , pump seals , or flanges.

DCR FC-79-18 Counting Rcom Air Conditioning /Ccmpleted as designed.

DCR 23-73 Mcdify Auxilia y Feedvater Pump FW-10 Centrols/

Cc=pleted as designed.

DCR 79 h6 N 9 Supply to Electrical Penetration Rocm/

C3mpleted as designed.

DCR FC-79-21 Computer Room Air Conditioning / Completed as designed.

DCR 77 48 Fire Door Modification / Completed as designed.

E. RESULTS OF LEAK RATE TESTS During the month of January, leak rate tests vere done on the majority of penetrations in the plant under Surveillance Tests CONT-2, CONT-3, and CONT-7. In addition to local leak rate tests ,

the containment Integrated Leak Rate Test was performed during the week of January 27, 1980. Reports on all leak rate testing during the 1980 Refueling Outage vill be forthecming when all tests are comple ed.

F. CHANGES IN PLAUT OPI3ATING STAFF Jerry McMahan joined the Fort Calhoun Station staff as an Auxiliary Operator.

Monthly Operations Report January 1980 Page Four G. TRAINI:IG Training for the month of January consisted of n=erous radiation protection classes for contract personnel. Operator training was held in accordance with NUREG 0578 and Operator requalification exam was issued.

H. CHANGES, TESTS AND EIPERI'CITS REQUIRING NUCLEAR REGULATORY CCMMISSION AU"'HCRIZATION PURSUA'iT TO 1CCFR50.59 None 3

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Monthly Cperations Report January 1980 Page Five II. MAI':TI'!;ciCE (Significant Safety Related)

M. O. # Date Descript en Corrective Action 2682 12-5-79 Diesel Gen. #1 trips on overspeed Install check valve between when started in auto for veekly primer and fuel pu=p.

test.

796 11-1-79 ACH-359 Fipe suppcrt for ec=ponent Replaced with certified U-bolt.

cooling water to contain=ent air cooling units in containment not certified.

30hh 12-13-79 RM-057 con 4enser off gas detector - Rebuilt pump.

vacuu: pu=p needs to be rebuilt.

3146 12-19-79 Couple RC-33 Reactor Coolant Pump. Cc=pleted per MF-RC-3-5-A.

31hh 12-19-79 Remove seal cartridge en RC-33. Cc=pleted per MP-RC-3A.

31ho 12-18-79 Remove seal cartridge for RC-3A. Cc=pleted per MP-RC-3A.

3139 12-18-79 Uncouple RC-3A. Completed per MP-RC-3-5-A.

31k3 12-18-79 Unceuple RC-33. Cc=pleted per MF-RC-3-5-E.

2979 12-15-79 Receive, uncrate and inspect new Cc=pleted.

fuel assenblies for Cycle 6.

3158 12-22-79 cc=puter Room A/C in closet leaking reiced and added freen.

water on floor.

3300 12-28-79 CH-1C leak in vest piston. Repaired per MP-CH-1.

3h07 1-2-80 HCV h033 vill not open. Blev down bleedoff port en controllers for HCV h03A L 3.

2551 12-19-79 Repack FCV-1102. Cc=pleted.

3h06 1-2-80 VA-3B breaker tripped. Performed CP-VA-33 and reinstalled breaker.

3169 12-18-79 Install and subsequently remove RV vent rig installed and removed RV vent rig. vithout incident.

2701 12-27-79 RM-05hB bicvdown =enitor spiking Grab sa ple confirmed no activity.

into alert. Performed calibration procedure on =onitor; all voltages and settings within spec.

3090 12-12-79 Degraded fire barrier between Barrier temporarily repaired Roc = 19 and Corrider kB. vith CT23F.

I "cnthly Cperations Repcrt

} January 1980

' Page Six II. MAINTINANCE (Significa-* ca'ety Related) (Continued)

M. O. # Date '

Oescription Corrective Action 3091 12-12-79 Degraded fire barrier between No repair necessary.

Rooms 56 and 57 3157 12-19-79 CCW Pump AC-33 inboard seal blown Replaced seal.

out.

3165 12-20-79 Boric Acid pump CH hB breaker Alar = is supposed to come in only trips whenever pump start is when switch is in pullout. Checke:

attempted. Also, 0FF NCRM.AL alarm coil resistance, tightened all does not then come on. connections, no apparent problem found.

317h 12-21-79 Outer personnel airlock door failed Cleaned excessive grease and dirt surveillance test leakrat e . off seals and surrounding area.

Fluffed both seals and applied light coat of 55M silicone grease.

Door retest was satisfactory.

3292 12-26-79 RPS "D" Channel lcw floe trip Pretrip and trip setpoints found Unit #3 going into spuricus pretrip. okay. Power Supply okay. Trans-mitter D/dpi-llhZ indicating low on C3-1, 2, 3 Eypassed trip unit. Rec 111brated D/dpi-1141 flow transmitter. Calculated aad installed new setpoints for D/TU-3 ST-RPS-3 performed satisfactorily to prove operability.

33h7 1-11-80 DG low level lube oil tank Added oil per required.

alarm.

27 :2 12-28-79 CH-1A Discharge Pressure PT-235 - Tightened all fittings.

fittings leaking.

2h97 11-5-79 CPlA 102Y sigma has burned cut bulb. Replaced bulb.

3228 12-20-79 CPHS - Safeguard Signal keeps Replaced flasher card, alarming.

31hl 12-19-50 Install new seal cartridge fer Ccap'. et ed .

RC-3A per MP-RC-33.

3378 1-10-80 Build stainless steel " Dutchman". Completed.