ML20071F990

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Monthly Oper Rept for Nov 1978
ML20071F990
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/08/1978
From: Hickle B
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20071F989 List:
References
NUDOCS 7812130181
Download: ML20071F990 (14)
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Text

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1

, i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-285

. Fort Calhoun #1  !

UNIT December 8, 197S DATE COMPLETED BY B. J. Hickle TELEPHONE h02-536-kh13 C

I!ovember, 3978 l MON 111 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net)

' 0. 0 0,0 3 37 2 0. 0 18 0.0 f 3 0. 0 39 ,,_

0. 0 4 0. O 20 0.0 S
0. 0 21 0.0 6
0. 0 22 _

O. 0 -

7 0.0 23 0.O 8

0.0 24 0.0 9

0. 0 25 0.0 a 10 0.0 26 00 0.0 27 0,0 11 12 0.0 ;g 0.0
0. 00 i3 29 0.0 30 0.0 14 1 15 0.0 31 16 0. 0 INSTRUCTIONS On this format. list tf ge daily unit power levelin MWe-Net for each day in the reporting inonth. Compute 1o the nearest whole mer . <

(9/771 78121501g[

i

. s OPERATING DATA REPORT ,

DOCKET NO. 50-285 DATE Fort Calhoun #1 COMPLETED BY B. J. Hickle TELEPHONE 402-530-4413 OPERATING STATUS Fort Calhoun Station Unit No. 1 Notes

1. Unit Name: . ,
2. Reporting Period: 'Heverber. 3078
3. Licensed Thermal Power (MW:1: Ih20
4. Nameplate Rating (Gross MWe). 502
5. Design Electrical Rating (Net MWe): 457
6. Maximum Dependable Capacity (Gross MWe): 481
7. Maximum Dependable Capacity (Net MWe):

457

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

N/A

9. Power LevelTo Which Restricted if An (Net MWe):

N/A

10. Reasons For Restrictions.lf Any: N This Month Yr. to-Date Cumulative
11. Hours in Reporting Period 720.0 8,016.0 -h5,h33.0
12. Number Of Hours Reactor Was Critical 0.0 6,432.0 35,695.3
13. Reactor Resene Shutdown flours 0.0 0.0 1,136.0
14. Heurs Generator On Line 0. 0 6,403.7 34,887.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0. 0
16. Gross Thermal Energy Generated IMWH) 0.0 8,872,237.9 hl,53h 760.2 -
17. Gross Electrical Energy Generated (MWil) 0. 0_ _ , ,, 2,959,733 7 13,765,072.7
18. Net Electrical Energy Generated (MWil) O. 0 2,813,750.6 12,985,719.6
19. Unit Senice Factor O.G 79.9 76.8
20. Unit Availability Factor 0.0 79.9 76.8
21. Unit Capacity Factor iUsing MDC Net) 0.0 76.9 63.2
22. Unit Capacity Factor IU>ing DER Net) 0.0 76.8 62.5
33. Unit Forced Outage Rate 0.0 3.9 5.0
24. Shutdowns Scheduled Oier Next 6 Months (Type.Date.and Duration of Eacht:
25. If Shut Down At End Of Report Period. Estimated Date of Startup: December 8, 1978 *
26. Units in Test Status tPrior to Commercial Operation): Forecast Achiewd

- 1 INITIA L CRITICALITY .

INITIAL ELECTRICITY COMMERCI AL OPERATION (9/77) e

~.

DOCKET NO. 50-285 UNITSHUTDOWNS AND POWER REDUCT10NS UNIT NAME Fort Calhotm #1 DATE Dace,bar 6. 1978' -

COMPLETED BY " J "f 41a REPORT MONHi Nova-bar- 1978 TELEril0NE h0? 'i4 Lh11

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,Q Cause & Coirectise E

1p j yy Lic nsee No. Date k 0 53E 'C "8 g: gg Action to 32 M Report a vO g Prevent Recurrence oO 3 23 j 78-O'4 78111 S 720 C 1 N/A N/A N/A N/A 1

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l 3 4 1 2 F: Forced Reason: Method: Exhibit G -Instructions A Equipment Failure (Exrlain) 1 Manual for rieparation of Data 5: Scheduled 2-Manual Scram. Entry Sheets for Licensee R4faintenance of Test C Refueling .t Automatic Scram. Event Repoit tLERI file tNUREG.

D Regulatory Restriction 4 Other (l'xplain)

. Oltill I.' Operator Training & License Examination 5

F Administrative G Opciatunnal 1:nne Il-:xplain) I slutine I .Sanw Sourse (9/77) 11 Other (Explain)

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Refueling Info: nation Ibrt Calhoun - Unit Ib.1 ,

Report for the nonth ending flovember 30,1978 Scheduled date for next refueling shutdcraT1. In proaress 1.

2. Scheduled date for restart follcuing refueling. December 9, 1978
3. . sill refucling or resumption of operation thereafter require a technical specification change or other Yes license amendment?
a. If answer is yes, W at, in general, will these be?

Technical Specifications changes with reload

( . application submitted to f1RC on August 4,1978.

b. If anse r is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cccriittee to deter- -

mine whether any unreviewed safety questions are associated with the c6re reload,

c. If no such review has taken place, wtten is it scheduled?
4. Scheduled date(s) for submitting proposed licensing action and support infornation. q,rhmittorf A g . '

1Q73

5. Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis
  • methods, significant changes in fuel design, new operating procedures.
6. The number of fuel assenblies: a) in the core 133 assentlies 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 assuming the present licensed capacity. 1985 Prepared by M n- Date December 6, 1978

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OMAHA P'J3LIC PO*4ER DISTRICT Fort Calhoun Station Unit No. 1 Nove=ber 1978 Monthly Operations Repert I. OPERATIONS S7J?F.ARY During the month of Nove=ter, Fort Calhoun Station was con-ducting refueling operations.

The actual fuel shuffling was ec=pleted with no significant deficiencies. In service testing and scheduled surveillance testing continued throughout the =cnth.

The engineered safeguards actuation test was ec=pleted successfully after the offsite power undervoltage modification was ec=pleted.

The reactor vessel closure head was replaced and studs tensioned.

Preoperational valve line ups are being performed.

Cycle 5 training for the operations staff was initiated.

A. PERFORMANCE CHARACTERISTICS LER Nt:=ber Deficiency TS-033 While in a hot shutdown condition at the start of the 1978 refueling outage, it was noted that reactor coolant cold les te=perature indicator 3/122C failed high off scale. "'he re=aining cold leg te=perature channels r-*ined operable except for D cu -- = '78-03h Following repeated tripping of the stack particulate process monitor (Pl4-061), a review of Section 2 9 of the Tech. Specs.

and the =enitor set peint calculations was conducted. It was dete=ined that EM-061 was set to trip in accorcance with Table 2.1 at 9.6 x 10 c pCi/sec. rather than the =cre conservative release rate of 2 x 10-3 nci/sec. as specified in Tech.

Spec. 2 9(2)b. No release rates vere ex-ceeded since the =0re restrictive value of 2 X 10-3 pCi/sec. vas used, and has been used, in def.b=ining all max""- ==' ease rates frc= contain=ent.

Monthly Operations Report Nove=ber 1978 Page Two A. PERFORMANCE CHARA G !ISTICS (Continued)

LER Nu=ber Deficiency 78-036 Although no tilting disc chech valves have been identified at the Fort Calhoun Station (Reference II Circular 78-15), another type of check valve which is orientation sensitive was inspected during the 1978 refueling outage.

As a result of the inspection, Auxiliary Feed-water check valve Fii-16h was found to be oriented in the wrong position. Maintenance

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Order 20h29 vas written to re=ove the valve and orient it correctly. Upon disasse=bly of the valve, one of the two valve dise plates was nissing.

B. CHANGES IN OPERATING IETHODS None C. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS Surveillance tests as required by the Technical Specifications Section 3.0 and Appendix B, were perfor=ed in accordance with the annual surveillance test schedule. The following is a su==a / of the su-teillance tests which resulted in Operations {

Incidents and are not reported elsewhere in the report: l Operations Incident # Deficiency OI 678 ST-TiV Che=ical Discharge OI 691 Lagoon discharge pH value did not fall within the 6.0 - 9.0 limit.

Monthly Operations Report Page Three Nove=ber 1978 C. RESULTS OF SURVEILLA"CE TESTS AND INSPECTIONS (Continued)

The following is a list of surveillance tests which could not be performed during the 1978 refueling shutdown condition (Operating Mode 5):

NOTE: FLC 77-11 subsitted previously to the Cc =ission indicates that these surveillance tests need not be perfomed while in a refueling shutdown condition.

Number Title Section ST-CIA-1 Regulating CIA Group:/ Transient F.2 se . .4. 7.,_4 4 . Che ,.,..v.

ST-CIA-1 Regulating CIA Gr ups/Transien: F.3 4, ,

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ST-CIA-1 C:strel Ele =ent Asse=bly Check F.h ST-CIA-1 PDIl, DE7 and SEQ Monitoring Syste= F.5 Test ST-CIA-1 See da-/ CIA ? si-icn In:iicating F.6 Sys.e= FDIL, DE7, CCS and Overlap M itering Syste= Test

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ST-C DI-1 S/G '4ater Iodine-131 C:: centration F.1 ST-CEE4-1 See dary Ple=t 31 vdev: and Le='e=ge F.1 Releases Iso:Opic Activity Anal / sis S!-C E !- l Seconda y Plan: 31 vd:v and leakage F.2 Proper.ica*' C =pesd-a "a- '" d-' -

Analysis and Gross Alpha Ans. lysis S~-3C-1 Diesel Fuel venter / F.1 ST-ET7-1 River Te=perature Menit: ring-Data F.1 Collection

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Menthly Operations Report .Page Four Nove=ber 1978 C. RESULTS OF SURV"ILLANCE p *ESTS AND INSPECTIONS (co'ntinued) 1 N=ber Title Section ST-ETI L Traveling Screen !..pinge=en: F.1 (Nc Required 7ne Circula:crs Are Ocyn)

ST-ITI k Precessing of !=pingement Data F.2 (Data Nc Required when Circulaters

. Are Dev=)

ST-ESF-1 Pressuricer Pressure Cha nel Check F.1 ST-ISF-1 Pressuricer Pressure Channel Chech F.2 ST-ESF-2 Cha==e1 "A" Safety Injection F.1

( Actuatic: Signal Test ST-ESF-2 Cha el "3" Safety I:Jection F.2 Actuation Signal Test ST-ESF-3 Contai==ent Pressure Cha=cel Check F.1 ST-ESF h Chaccel "A" Centai =ent Spray F.1 Actuatics Signal Test ST-ISF h Channel "3" Cc=:ad--==: Spray F.2 Actua:1cn Signal Test ST-ISF-5 Autematic Load Sequencer Chech F.1 ST-ISF-c Diesel Genera:Or Check' F.2

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ST-ESF-3 Safety I:Jec:10: Ta-> Level and F.1

? essure ::s .~=.e:1s Chech ST-ISF-9 Scric Acid Tank Level Check F.1

ST-ESF-11 Stea= Geners
cr ? essure Cha- el F.1

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Check t

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Monthly Operatic:s Reper Page Five Nove=ber 1c78

'C. RESULTS OF SUR7EILLANCE TESTS AND INSPEC'" IONS (Continued)

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ST-!CI-1 Calculatics of Tcta' Integrated F.;

Radial Pe=V' g Fac cr and Total Placar Radial Peaking Fac cr ST-IC -2  : ccre Detec cr Alar = Li=1ts F.1 Verificatic: .

ST-IS!-CVCS-3 C7CS Pu=p Tes: F.1 ST-?L-1 Press =icer Level Cha=e1 Check F.1 5"'-?1-1 Pressuricer Level C'"a- el Check F.2 ST-RA-1 Reactivity Ralance F.1 ST-RA-1 Nor=alicatics of Cc=puted Rcrc F.2 Concentratic: vs. Rurnup Curve ST-RCF-1 Reac:cr Ccciant Syste= Flev Rate 7.1 Deter =inatics ST-RIT-3 Reac cr Coelas: Syste= Leak Rate F.1 Calet.latic: .

ST-?SS-1 Power Range Safety Cha- els Check F.1 ST-?SS-1 Power Range Safety Channel Adjus =ent F.2 5 -?SS-1 Power Range Safety Cha- els Tes  ?.3 S!-?S5-2 *Jide Range icgarith=ic CS-- el F.2

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S"'-?S S-? Reac:cr Cecism: Flow Check F.1 ST-?SS-3 Reae:cr Ccelas: icv Flev Trip Check F.2 ST-?SS L Ther-=' Margin /Lcv Pressee Cha=els F.1 Cw ., >---

ST-?SS h Ther-=' Margin /Lc'.- ? essee Cha=els F.2 Check ST-?SS - Righ Pressuricer Press =e 7:a=els F . '.

Check

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ST-??S-c Scen: C-eners:cr level w'a-- 's Tes: F.2 S-'-?SS-7 Stes: Genera:cr ?ress= e ~hech F.1 S* -??S-T Sces: Ceneracer ?res s"- "'-*--als F.2 "s' re

Monthly Operations Report Paga Six Nove=ber 1978 C. RESULTS OF SURVEILLANCE TESTS AND INSPECTION (Continued)

Nu=ber Title Section ST-PSS-8 Eigh Centai=ent Pressure Cha=els F.1 Check ST-PSS-9 ?rbine Less of Lead Cha=e1 Check F.1 ST-PSS-10 Manual Trip Check F.1 ST-PSS-11 RTS Logic Units Tes: F.1 ST-PSS-12 Axial Power Distribucien Cha=els F.1 Check S"-PSS-12 Axial Power Distribu.icn Cha=els F.2 f Test ST-SCIA?!S-1 Calibratics Secendary CIA ?csitiening F.1 ST-SCIAFIS-1 Calibratics of Secenda:7 CIA F.2

!=tericeks and Alar =s S*-S!/CS-1

  • gineered Safeguards Mechanical Checks F.1 ST-SI/CS-1 SI Tank Check Valre Check F.2 ST ~~4-1 ?rbine R=back Circuit Check F.1 S*-CSIM-1 EM-057 Condenser Air Ijecter Releases F.2 Gross G=-a sed Individual G= =

I=itters Activity Analysis

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o Monthly Operations Report November 1978 Page Seven D. CHANGES, TESTS AND EXPERIMDTS CARRIED OUT WITHOUT COW.ISSION APPROVAL Procedure Descrittion SP-VA-7 Safety Injection Pump Room Temperature Rise Test (vf +.h no ventiliation). Test ec=pleted prr.liminary evaluation temper-ature rise insufficient to have adverse effects on Safety Injection & Cont. spray pumps. Technical Services vill supply final evaluation.

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SP-FE-5 Spent Fuel Inspection Stand Installation SP-FE-8 Eddy Current Testing of Irradiated Fuel Assembly Guide Tubes. Testing revealed no significant guide tube wear.

E. RESULTS OF LEAK RATE TESTS

, The Refueling Leak Rate Testing progra= continued this =cnth and vill continue throughout the outage in accordance with ST-CONT-2 and 3. A follow up report vill be submitted within 90 days of the co pletion of the Leak R.ste Testing Program conducted during the 1978 Refueling Outage.

F. CHANGES IN PLANT OPERATING STAFF The security force at Fort Calhoun was changed from a contract guard force to a District guard force. The security force vill now be under the direct control and supervision of the District.

G. TRAINING November training consisted of procedural review and 0.J.T. during overhaul by both Operations and Maintenance. Major activities per-fo:=ed in the overhaul were reviewed prior to starting by the crafts involved including construction personnel.

H. CHANGES, TESTS AND EXPERIMENTS REQUIRING UUCLEAR REGULATORY CO.TCSSION NJTHORI"ATION PURSUA'IT TO 10 CFR 50.59 Changes to Operating License DPR h0

1) Amendment No. Eh dated Nove=ber 27, 1978 The amendment added Technical Specification requ h ==*s for

, the emergency power system and authori::ed =odification to the emergency power system.

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Approved by Manager-Fort Calhoun Station

I yenthly Opera:1cns Report

!ievenber 1978

. .m.-e, .u..

!!. MA : I IA'ICI (Sie,nificant Safety Rela,ed)

M. C. d I Date i Descri;;ien 1 00 rective A 1cn i 16989 H-22-78 Manual isol. valve for centain=ent Repacked valve SI-178 spray header hard to operate -

17523 n-1-78 Centrol Roc = charecal filter:: Replaced filters per M?-VA-6h

  • 182L6 H-17-78 Internals of rav vater strainer ver: ?rned icver 3 ins. devn and pressed en stainless steel ring 1967h n-12-78 Replace six incere detectors Replaced per S?-IC-5 10690 11-10-78 Perfor= reactor vessel internal Inspected vessel per ISI plan I inspection 20076 11-18-78 "A" RC pu=p seal leaking Rebuilt seal per MP-RC-3-3A&3 20116 n h-78 Rebuilt spare RC punp see.1 Refueling _aintenance 202h6 11-1-78 Radiation surrey of fuel transfer Perfomed survey per Standing canal before =oving fuel Order T-8.

2C272 11-6-78 Radiation survey of fuel transfer Perfomed surrey per Standing canal during fuel =cve=ent Order T-S.

20318 n-13-78 Pin hole leak at penetratien M-93 Repaired leak and : etested.

cf 260 c /=in.

203h8 11-17-78 Sut=arine hull leaking 0 5 SCFM Repaired leak per approved procedure and retested.

203h9 11-6-78 Penetratien M-58 leaking 500 c:/=in. Repaired RC7-88h3 and retested 20369 11-8-78 Spent centai=ent carben filter Changed filters 20382 E-7-78 Penetration RC7-1387A/3 leaking Repaired S/G isci. valves 3800 /=in. and retested 2038h n-17-78 Flange leak en SI-7 V-190 Replaced pressure gaske: a relief

!, gasket i

20h56 11-2-78 Oeter=ine te=peratu e rise in Roc = 21/ Test =pleted per SF-7A-7 22 vith naxi=u available SI & Cent.

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spray flev 20h66 11---78 Inergency feedvater cen r:1 valve f r Repaired vakte ar.d re ested.

5/G 3 leaks thru 20513 11-6-78 Aux. Feedvater inle: check valre for Repaired valre per =aintenan:e S/G A leaks crier

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y.cnthly Operations Reper Nove=ber 1978

? age 31ce

~:. MA-.r.:iA"0I (Significant Safety Related)

M. C . e i Date i Descrit:-1:n Cer e tive Aet en 2051h U-2-78 3ackvash drain isol. valve for "A" Valve replaced.

rav vater strainer badly erroded.

20522 n-1-78 Faulty temp. tra- M tter for c/122R-1 Replacad trans=1tter 2053h U-1-78 Radiation =eniter cut of spec's Recalibrated PR056A 20';h8 n-2-78 Bent actuating a= on h1607 3reaker Reshaped and velded am en Breaker SI-1A (155 11-2-78 Radiation Monitor Out of Spec. Recalibrated log count rate =eter PR-051.

20558 11-3-78 Paper ja=n.d on Radiation Moniter Realigned paper PR-050 20560 11-3-78 Alam board faulty en PR-051 Replaced alam and rate =eter boards 20563 11-7-78 Fivshing valves en south end of rav Cleaned valves and instan ed vater heat exchangers vill not shut new gaskets 20571 11-6-78 Grind veld surface for 17: exa= per Refueling =aintenance 10 year ISI plan 20572 n-3-78 Drain valve on diesel fire pu=p Repair per =aintenance crder

. strainer leaking i

i 20586 11-16-78 Filter paper no =cving cor e: ly Repaired paper take up ren and en Radiation Monitor PR-050 replaced detecter.

20632 11-18-78 leaking incere instru=ent flange Replaced per plant approved procedure 2065h 11-9-78 Pressurizer spray valve failed Replaced relay and -~'"- -s calibration 20658 n-9-78 outer PAL door failed leak tes Cleaned seal and retested.

2C670 11-11-78 3resker 13hA trip setting cut of :nstan ed new IC-1 devi:es and spec. recalibrated 2C677 n-10-7S CM- el "A" Wide Range RPS fluctuating Replaced pcVer supply and recalibrated 20685 11-11-78 Perf:=ed leak Test en Suw - -ine Re e Refueling sintenance 20750 11-15-73 Scratch in cuter reactor vessel "O" 3'.end cut scratch ring grove l

l

  • O Men-hly Operations Repc.~.
Tove=ber 1978 Page Ten

~~. R . MCI (Significan Safe:7 Rela ed)

M. O.

  • I Oate i Descri1n i Cerrective A:::en i 20755 n-1L-78 Packing leak contai==en: 1sola:1cn Tightened ste= packing valve 20758 n-1L-78 Filter fai1=e switch not verting Replaced light and reseated RM-061 capstem 20761 n-16-78 Gouge on seating surface of Machined valve surface per pressurizer safety valve RC-lh2 plant approved precedure p- 76 u-17-78 Gouge en seating surface of Machined valve surface per

( pressurizer safety valve RC-lh1 plant approved procedure 20789 u-17-78 Penetration SI-ECV-383-3 leaking Installed new gasket and 0.h SCFM retested.

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