ML19274D176

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Monthly Operating Rept for Dec 1978
ML19274D176
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/09/1979
From: Hickle B
OMAHA PUBLIC POWER DISTRICT
To:
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ML19274D175 List:
References
NUDOCS 7901150127
Download: ML19274D176 (13)
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285 UNIT Fort Calhoun #1 DATE January 9. 1979 COMPLETED BY B. J. Hickle TELEPIIONE 402-536 kh13 MONTig December. 1078 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

O. O g7 0,0 g

2 0.O gg 0.0 3

0.0 39 0.0 0.0 20 0.0 4

0.0 21 0.0 5

6 0.0 22 0.0 0.0 23 0.0 7

8 0.0 24 12.3 9

0. 0 25 124.9 10 0. 0 26 165.6 II 0.0 27 170.6 12 0.0 2g 176.3 13 0.0 29 159.2 34 0.0 - 30 288.8 15 00 31 289.3 16 0.0 INSTRUCTIONS On this format. list the average daily unit pewer levelin MWe Net for each day in the reporting inonth. Comp.ae io the nearest whole rnegawatt.

(9/71a 7 90115 0lV!4

OPERATING DATA REPORT ,

DOCKET NO. 50-285 DATE January 9, 1979 COMPLETED BY B J._ll ekle TELEPilONE 402-536-ah13 OPERATING STATUS Fort Calhoun Station Unit No. 1 Notes

1. Unit Name:
2. Reporting P.riod: December, 1078
3. Licensed Thennal Power (MWt): 1h20
4. Nameplate Rating (Gross MWe): W2
5. Design Electrical Ra:ing (Net MWep: h57 ,
6. Maximum Dependable Capacity (Gross MWe): 481
7. Maximum Dependable Capacity (Net MWe): 457
8. If Changes Occur in Capacity Ratings (items Num'ser 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.lf Any: N/A This Month Yr. to-Date Cumulative
11. Ilours In Reporting Period Thh.0 8,760.0 h6,117.0
12. Number Of flours Reactor Was Critical 269.7 6,701.7 35,965.0
13. Reactor Resene Shutdown flours 0.0 0.0 1,136.0
14. Ilours Generator On Line 178.5 6,582.2 35,066'.1
15. Unit Resene Shutdown llours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWil) 113,663.1 8,985,901.0 41,648,h21.3 .
17. Gross Electrical Energy Generated (MWill 39,190.0 2,998,923.7 13,804,261.7
18. Net Electrical Energy Generated (MWil) 35,686.1 2,849,436.7 13,021,405.7
19. Unit Senice Factor 24.0 75.1 75 9
20. Unit Availability Factor 24.0 75.1 7 5. <'
21. Unit Capacity Factor iUsing MDC Net) 10.5 1. 3 62.3
22. Unit Capacity Factor (Using DER Net) 10.5 71.2 61.7
23. Unit Forced Outage Rate 0.0 3.8 5.0
24. Shutdowas Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):

N/A _

25. If Shut Down Aa End Of Report Period. Estimated Date of Startup: N/A
26. Unit In Tev Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

s ,1 I

UNITSHUTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-285 UNIT NAME Fort Calhotm #1 DATE January o. 1o79 COMPLETED BY B. J. "iekle REPORT MONTil December, 1978

  • TELEPilONE h o2-5 %-4413 e c. .3: -

g *,

Sa

. E _e E Licensee c. Cause & Currective .

No. Date g 3g  ;; ,gy 7 .c ~4 Event u? 83 Action to

  • $E 5 jisg ReporIar <N 0 jU Prevent Recurrence 6

78-04 78112 S 565,5 C 1 N/A N/A N/A N/A i 2 3 4 F: Forced Reason: Method: Exhibit G Instruci!ons S: Sct eduled 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) 01611 E Operator Training & License Examination F-Adminis:rative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) II Other (Explain)

-Refueling Information -

..Jbrt Calhoun - Unit No.1

. Report for the rnonth ending December 31, 1978 January 1. 1980

1. Scheduled date for next refueling r.hutdown.

March 1. 1980

2. Scheduled date for restart following refueling.
3. Will refueling or resu: ption of operation thereafter require a technical specification change or other 'Yes license anendment? .
a. If answer is yes, what, in general, will tMse be?

Stretching power to 1500 MWth and increasing primary system pressure to 2250 psia is planned in conjunction with the change in fuel supplier to Exxon.

b. If answer is no, has the reload fuel design '

ard core configuration been reviewed by '

your Plant Safety Review Co::nittee to deter-mine whether any unreviewed safety questions are associated with the core reload.

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

System Pres re

4. Scheduled date(s) for submitting proposed licensing en n inna E]n$ an,f ysis and action and support infonration.

Tech. Spec. Changes -

Inportant licensing conaiderations associated with October, 1979

5. -

refueling, e.g., nea or different fuel design or supplier, unrevie.w.d design or perfonnance analysis nnthods, significantcchanges in fuel design, nea operating procedures.

First use of Exxon fuel in Fort Calhoun. Increasing primary system pressure from 2100 psia to 2250 psia.

Stretching power from 1420 MWth to 1500 MWth-133 assernblies

6. 'Ihe number of fuel assentlies:b) a) in in the the spent core fuel pool 157 c) spent fuel pool "

storage capacity 483 d) planned spent fuel pool "

storage capacity 483

7. '[he projected date of the last refueling trait can be discharged to the spent fuel pcol assuming the present 1985 licensed capacity.

Date January 8, 1979 Prcpared by -

CMAHA PUBLIC POWER DISTRICT Fort Calhoun Station Unit No. 1 December 1978 Monthly Operations Report I. OPERATIONS SU: NARY Plant start up operations for Cycle 5 were ccaducted during the month of December.

Lov power physics were completed satisfactorily with all measured parameters agreeing closely with predicted values.

The plant was placed in a cold shutdown condition after completion of 1cv power physics to recouple control rod drive mechanism 31.

The plant was returned to hot standby on December 23 and the turbine generator was sychronized on December 2h.

The required testing at h6% reactor power was completed and power raised to 66% in preparation for continued power ascension testing.

All normal / refueling outage surveillance tests were completed.

A. PERFORMAUCE CHARACTERISTICS LER Number Deficiency 78-035 During testing of the VIAS (Ventillation Isolation Actuation Signal), prior to a radioactive gas release, lockout 8631/ VIAS did not trip.- The relay was t==ediately retested and tripped nommally. The VIAS relays are checked prior to each gas re-lease and monthly by Surveillance Test.78-037 During the 1978 refueling all Limitorque valves were inspected for proper staking of the lock nut on this design motor operator.

The inspection of the motor operators revealed that 30 operators were not staked in accordance with the manufacturers reccamendations. In-spection was conducted as a result of com-munication with Combustion Engineering who informed OPPD that Arkansas (ANO-2) had found several operators unstaked. In an unstaked condition the lock nut could backout due to vibration and cause the stem nut to move axially and disengage the splines resulting in loss of drive to the valve stem.

Monthly Operations Report Dec ember -1978 Page Two A. PERFORMA' ICE CHARACTERISTICS (Continued)

LER Number Deficienev 78-038 During preoperational testing of the new off-site power lov system, Diesel Generator No.

2 failed to auto close onto the' bus. Breaker mode switch contacts27-27C failed to make contact .78-039 During the annual calibration of steam generator RC-2A level instrunentation, it was found that the level transmitter for "C" channel (C/LT-901) was not within specifications. The remaining three channels were found to be eithin tolerance thus providing adequate operable steam generatcr level instrumentation.

78-Oh0 During the performance of the type 3 and C Con-tainment leak rate tests during the 1978 refueling outage, it was noted that the total leakage ex-ceeded the 0.6 La limit of 62,951 scem.78-041 Air flow rate through charcoal filter units VA-26A, VA-263 and VA-66 were found to be less than the minimum required by Technical Epecifications Table 3-5 In additi n, the halide removal test for VA-66 indicated that the maximum permissible leakage was exceeded. The District has analyzed these problems and concludes that the safe oper-ation of the plant is not compromised.

78-Oh2 During the performance of shutdown cooling inter-lock test (ST-SDC-1) it was discovered that PC-1053 was not operating. Further investigation showed relay 94-347/3h8 (the valve closing relay) was not vired to PC-1053 and was inoperable since the 1977 Refueling Outage. The edundant shut-down cooling interlock PC-10) was operable during this period.

78-Oh3 While inspecting discherged fuel assemblies as requir2d by Tech. Spec. 3 2, Table 3-5, Item 12, a sin.:;1e fuel pin was observed to have failed in a manner that vculd allow fission fragment re-lease to the reactor coolant. This instance was the only cladding failure o' 2erved during visual inspections of kh dischargea fuel assemblies and 8 reload assemblies.

Monthly Operations Report Decenber 1978 Page Three A. PERFORMANCE CHARACTERISTICS (Continued)

LER Nmnber Deficiency 78-Ohh During the 1978 Refueling Outage certain surveillance tests required by Section 3 0 and Appendix 3 of the Fort Calhoun Station Technical Specifications were not performed as scheduled because of the refueling shutdown condition (Operating Mode 5) of the plant.

Facility License Change No. 77-11 was subnitted to the NRC on September 9, 1977 and again on November 9, 1978. The approval of this FLC would delete the requirements to perform these surveillance tests when the plant is in the refueling shutdown condition.

78-Ch5 During plant leatup an operator noted that ene pressure channel for the FORV system was not responding. Technician troubleshooting the problem pulled recorder fuses which caused both PORV's to open. The operator closed bcth PORV isolation valves to terminate the transient.

Both PORV's were returned to service 15 minutes later.

78-Oh6 Weld leak occurred on charging pump CH-1A; (To ba submitted) crack was ground cut and revelded using certified procedure. Modification currently in progress to reduce vibration in the CVCS system.78-005 (Supplement / New valve block received and installed in CH-IC Update report-to be charging pump.

submitted)78-012 (Supplement / New valve block received and installed in CH-13 Update report-to be charging pump submitted)

3. CHANGES IN OPERATING METHODS Uone

Monthly Operating Report December,1978 Page Four C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3 0 and Appendix B, were performed in accordance with the annual surveillance test schedule. The following is a su= mary of the surveillance tests which resulted in Operations Incidents and are not reported elsewhere in the report:

Operations Incident Deficiency OI-714 ST-ENV-3 Lagoon discharge pH value did not fall within the 6.0 - 9 0 limit. Actual pH - 5 7 D. CHANGES, TESTS AND EXPERIM?RTS CARRIED OUT WITHOUT COMMISSION APPROVAL Procedure pascriution EEAR FC-78-25 Replaced FW-.182, FJ-183 vith new type manual valves (non-class modification)

EEAR FC-78-69 Installed a check valve in H2 gas supply DC0 78-51 to VCT to prevent backflow of VCT gas space. Installed as designed.

EEAR FC-78-93 Install lifting eyes for PCV-Th2 A, B, C, D DC0 78-36 actuator. Install "0" Ring seal cartridges SRDC0 78-31 for PCV-Th2 A, B, C, D. Installed as designed.

0-Ring cartridges supplied by manufacturer had to be machined 5 mils to ensure proper fit.

DCh 77-25 Battery powered smoke detectors in Control Room panels. Irstalled as designed in accordance with Fire Protection program committment.

DCR 77-h Battery Room Ventilation-ventilation portion of the modification completed; air monitor not re-ceived from vandor-OPPD has requested change in Fire Protection ec=mittment date to April 1, 1979 SP-FAUD-1 Fuel Assembly Uplift Condition Detection. All vessel b.p's are within the uplift specifications.

SP-RPS-5 Incore/Excore recalibration pro:edure. All re-sults satisfactory.

Monthly Operations Report December.1978 Page Five E. RESULTS OF LEAK RATE TESTS The Refueling Leak Rate Testing Program continued this month in accordance with ST-CONT-2 and 3 A follow up report will be submitted within 90 days of the completion of the Leak Rate Testing Program conducted during the 1978 Refueling Outage.

F. CHANGES IN PLANT OPERATING STAFF None G. TRAINING During December, procedural review and on the job training were conducted for maintenance personnel. Major activities performed during the overhaul vere reviewed prior to starting by the crafts involved. Operations personnel and licensed station supervisors attended requalifications training on Cycle V reactivity parameters, Technical Specification changes, modifications to plant design and changes in emergency and normal operating procedures.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING NUCLEAR REGULATORY CC:04ISSION AUTHORIZATION PURSUANT TO 10CFR50 59

1) Changes to Operating License DPR h0
a. Amendment No. 43 dated November 30, 1978 The amendment approved the Fort Calhoun Staticn site security plan and added its requirements to the Operating license.
b. Ar er.iment No. h3 dated December 5,1978 The amendment amended Technical Specifications to pemit Cycle 5 operation.
2) Modffication designated in NRC safety evaluation report for fire protection program at Fort Calhoun S.stion designated to be completed in December 1978, were conpleted, except where specific relief was requested of Commission.

Monthly Operations Report December 1978 Page Six H. CHANGES, TESTS AND EXPERISE.TS REQ,UIRI'IG NUCLEAR REGULATCRY COMMISSION AUTHORIZATIONS PURSUANT TO 10CFR50 59

3) Modification completed to emergency power system as
  • authori::ed by Amendment No. kl.

Approved by Manager-Fort Calhoun Station

I

. . I I

l Monthly ope-ations Rr.po-t December 1978 Page Seven

!!. MAI:. L2;ANCI (Significan; Safety Related)

M .C.

  • l- Oate i Dese-1J:lon Co rectiveletion ..

18823 12-1-78 Ind '. cation of Rod 19 appears in- Replaced limit switch per MP-RC correct 7 19560 12-5-78 Lubrication on Main Steam Isol. Valve Replaced nipple.

' has bent nipple. I 196h3 12-7-78 Spent Pu ification Filters Changed filter per MP-CH-17 l 1968h 12-6-78 Re=ove #3 Crossaround Relief Valve Refue'ing Maintenance.

and send to factor / for setcing 19837 10-30-78 Select and functio,n11v test 10 Tested per ST-HSS h (F.1).

snubbers while reactor in shutdown cond.

199h7 12-7-78 Seismic support CVCS-lh9 instaned Reinstalled support in correct incorrectly position.

2003h 11-2k-78 RC-136, Loop 1 sample root valve has Replaced packing per PRC procedure ,

Packing leak approx. 0 5 gpm.

20075 10-2h-78 Reactor Coc'. ant Pump RC-3A seal Replaced seal per MP-RC-3A&B.

leaking 2007T 11-27-78 Reactor Coolant Pump RC-3C seal Replaced seal per MP. U -5A&B.

leakirg 20282 12-6-78 C/PIC-902 Sigma failed causing half Repaired Si maneter E per MP-SIGMA-trip of SGLS 2.

20357 11-17-78 Penetration (HCV-383-4) leaking sealed leak with Devcon. .

approx. 150 cc/ min. -

20359 11-20-78 Penetration M-97 leaking 72. SCFM Valves HCV-HO7A/B repaired.

20386 H-30-78 Penetration.M-kT leaking 1.0 SCFM Replaced d'aphragm in PCV-7k2G.

20k28 H-30-78 Snubber stem broken CHS-20h9-1 Replaced snubber in kind.

20429 12-6-78 ,

W-16h Valve installed improperly Removed, rotated 90 and reinstalled.

20611 12-5-78 Pipe restraint on HPSI line Aligned restraint 3-HPH-12-9-PR.

instaHed improperly 20612 11-8-78 Safety loop C/PT-102 transmitter Replaced force motor and fluctuating calibrated.

20613 12-2-78 Transmitter PT-103X vin not Replaced transmitter and calibrate calibrated.

20628 H-23-78 Steam Generator (RC-2A) tube Plugged three tubes per special degradation procedure RC-2-1 206k2 H-18-78 Component Cooling Water Heat Cleaned tubes per MP-AC-1 Exchanger cleaning.

20663 H-29-78 Upper pump shaft bearing on FP-1B Replaced shaft sleeve and stufff.2g diesel fire pu=p, will not hold box bearings and repacked.

ptching.

20689 11-2h-78 Nuchar detector well cooling SIGMA Replaced trim resistor and cal-Non-Linear / Span Resistor needs re- ibrated placing.

20768 12-5-78 High Pressure safety injection pump Repair SI-HCV-2928 2A discharge Isol. viv. vill not open 208k6 11-27-78 Amplifier PT-105'is erratic Replaced amplifier and transmitter and recalibrated 20851 H-22-78 Heat tracing point 12 TAR 2 vithin Found vatt pack voltage adjustment 5 of miniram broken, replaced a,d adjusted for proper voltage

t Mcnthly Operations Repo-t _

i December 1978 Page Eight

!!. M C TINANCE (Significa= Safety Related) _. Z -_ -

M.;0-

  • I Date Dese :mion Corrective Action 20852 12-1-78 Main steen isol. viv. HCV-10h1 A '

Repairsdrockshaft bearing flange packing leaking surface and replaced gaskets per _

~

PRC approved procedure ~

20853 12-1-78 Main steem isol. viv. HCV-10h2B Repair-gasket surfaces per PRC packing leaking approved. procedure Replaceil seal per PRC approved ~ ~

~~

20887 ~ ~ 12-h-78 Reactor coolant pump RC-3B seal'

~

leaking procedure _ ~

Repacited root valves ~

~~

12-6-78

~

20899 Reactor coolant root valves RC-157, 105, 135, 124, 132, 130, 100, 128, --

and 163 packing leaking. ~

20900 11-26-78 Fission chamber on RPS "B" mannel Replaced chamber per MP-PR/WRD-1 needs replacing 20930 n-30-78 Spent fuel handling area . charcoal Cleansd filters in VA-66 per PRC filter unit appears to be partially approved procedure' plugged 20954 11-29.-78_ Containment Purge Isol. Valves PCV- Adjusted retaining ' screws until .

Th2C&D leaking leak' stopped 20972 _ n-30-78 Rad Monitor RM-051 failed sur- Repair broken wire and c,alibrated~

~ ~

veillance test ST-RM-2 20975 n-30-78 RM-050's alarm board needs balancing Balanced board 21034 12-k-78 RM050 spiking Recalibrated monitor 20995 12-2-78 RM-050 comes to trip alars early Realigned board & cleaned balaneg8 21038 12 h-78 RM-055 alarms early cleaned detector P 21001 12-2-78 RM-055 vin not calibrate Cleaned water switch 21060 12-6-78 Capillary line to emergency diesel Repaired line and returned to tgenerator fuel tank broken service

'12-7-78 Handvheel to RC-250 "B" RCP controne 21072 l Replaced handv~ieel .

bleed-off vent valve missing 2138k 12-29-78 Pressurizer spray control valve Furmanite process applied to PCV-leaking at bonnet flanges 103-2 to stop leak 21353 12-27-78 Filter cannister on RM061 has hole Replaced cannister in it 213h7 12-27-78 RM-055 requires cleaning Refueling Maintenance.

21201 12-19-78 Indication light for CEDM 19 does Replaced lamp socket

-~ ~

not operate 20659 H-9-78 Diesel Gen. Fuel Oil tank level Repaired broken- lines and returned ~to se rice indicator not working 21088 12-18-78 Area monitor chart recorder not Zepaired loose connection printing properly 21230 12-lh-78 RPS matrix power supply PS-13 voltage Replaced power supply and tested dropped to 17 volts 21171 12-14-78 RM-061 alarm unable to be cleared Replaced broken puup belt 21100 12-8-78 Check safety injection valves ECV-3n Limits set according to specifi-312, 314, 315, 317, 318, 320, 321, cations 327, 329, 331, and 333 for proper close limits -

Menthly Operations Report December 1978 Page Nine II. .N'TCE (Significa= Safety Related)

P M . ~; . - i Date t Descri r:;1cn ._. . ____ Corrective Action 21141 12-10-78 Breaker for "C" RC Pump vill not Found bad coil on Th relay. Re-reset. placed relay and returned to service 21086 12-9-78 LPSI and HPSI trouble alarm vill not Found and tightened loose connection clear 21207 12-13-78 Reed Svitch indication for CEDM 43 Connected cables properly.

does not work because of improper connections 21172 12-12-78 Replace valve seats in instrument Replaced viv seats in instru=ent manifolds for SI t e b . manifolds for SI-6A, B, C & D 2n08 12-9-78 Pressurizer spray control valve Instaned different E/P and ran blowing air excessively air line directly to solenoid from regulator 210h1 12-13-78 Diaphram on HCV-h2TC, "C" SI tank Applied RTV to joint and leak leakage cooler, is blowing air. stopped.

21036 12-13-78 HPSI pump 2A inlet valve, HCV-2927, Cycled valve and returned to ser-vill not travel full open. vice.

21102 12-8-78 SI tank 6A lov level magnatrol Replaced mirco switch and returned vill not clear to service 2n65 12-13-78 Reactor coolant PI-A/dpI-11hX reauing Replaced transmitter and high for plant conditions calibrated 15077 11-17-78 Ccmponent . cooling water heat ex- Cleaned heat exchanger per PRC changer tubes need cleaning approved procedure 2nT3 12-11-78 Reactor coolant system root valves Tightened packing RC-H2, 115, 119, 124, 138, 117, 12'J, n 3, loh, 105, 106, 107, 155, 156,

<109, 15h and 158 have packing leaks 21132 12-10-78 Upper ma:reay on "D" safety injection Installed new gasket.

tank leaking 2C877 12-6-78 Exhausted filters in containment Replaced filters per MP-VA-6-3.

charcoal filter unit VA-6A vest 18838 H-22-78 Safety injection tank 6D discharge Replaced pecking on HCV-297h per isolation valve has packing leak PRC approved procedure.

180h9 12-10-78 Replace hydrogen purge system char- Changed filters per MP-VA-82 coal filters.

20617. H-7-78 Change oil frca DTE 797 to Mobil Changed oil per NRC IE Circular vaportec light on turbine driven No. 78-02 aux. feedvater punp.

19h65 n-30-78 Replaced old style 3ergen-Paterson Replaced 21 external piping snubbers with rebuilt snubbers frcm snubbers with manifold model per Aux. Steam system. PRC approved procedure.

2031h 12/5/78 Reactor Coolant System RTD (3-1220) RID sensor found open-calibrated failed high per CP-B-122C.

2n68 12/13/78 Replace channel "B" Reactor Protectiv e Replaced trip unit, perfor=ed System bistable trip unit #2. calibraticn procedure and applicab Le section of surveillance test.

21355 12/25/78 RM-505 in constant VIAS (ventilation Changed stepoints per the Technica L isolation) Data Book.

20982 ' 12/7/78 Run plateau checks on RFS channel "D" Plateau checks performed per cali-vide range detector bration check proc. CCP-D/ NI-004.

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