ML19282B988

Monthly Operating Rept for Feb 1979

ML19282B988
Person / Time
Site:	Fort Calhoun
Issue date:	03/08/1979
From:	Hickle B, Jaworski R OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML19282B985	List: ML19282B984 ML19282B988
References
NUDOCS 7903190213
Download: ML19282B988 (8)

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k AVERAGE DAILY UN!T POWER LEVEL 50-285 DOCKET NO.

UNIT Fort Calhowl #1 DATE March 8, 1979 B. J. Hickle COMPLETED BY TELEP110NE LOP-536 Lh13 MONIll February, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 4'ih. 3 h52.2 3

g7 h52.8 2

453.8 gg 3

453.1 452.0 g9 4

h53.1 20 451.9 453.6 451,5 5

21 h53.5 451.5 6

22 453.2 451.3 7

23 h53. 3 423.0 8

24 434.h 246.0 9

25 10 306.8 0.0 26 436.5 101 0 gg 27 12 h38.5 28 359 7 hh5.h 13 29 bbb 9 14 30 h51.2 15 3,

452.5 16 INS 1 RUCTIONS On this format. list the average daily unit power level m MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

(9/77) 790319OR/3

/

. -~

OPERATING DATA REPORT DOCKET NO. 50-28?

DATE thrch d,1979

-C051PLETED BY B.J.

IIiekle TELEP110NE 402-530-4413 OPERATING STATUS

1. Unit Name:

Fort Calhotm Station Unit IIo. 1 Notes

2. Reporting Period:

Februarr. 1070

3. Licensed Thermal Power (51Wt):

Ih20

4. Nameplate Rating (Gross 51WeI:

502

5. Design Electrical Rating (Net $1We):

h57

6. h!aximum Dependable Capacity (Gross N1We);

h03

7. hiaximum Dependable Capacity (Net 51We):

h57

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

N/A

9. Power Level To Which Restricted. If Any (Net 51We):

II/A

10. Reasons For Restrictions. If Any:

?I/A This h1onth Yr.-to-Date Cumulative II. Ilours in Reporting Period 672.0 1,h16.0 h7,593.0 I? Number OfIlours Reactor Was Critical 661.4 1,405.4 37,370.h

13. Reactor Reserve Shutdown flours 0.0 0.0 1,136.0

14. Ilours Generator On-L:ne 651.3 1,395.3 36,h61.h

15. Unit Reserve Shutdown llours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (.\\1Wil) 856,102.1 1,856,959.0 h3,505,382.3

17. Gross Electrical Energy Generated 151Wil:

288,674.0 628,938.0 lb,433.199.7

18. Net Electrical Energy Generated (5thil) 273,937.L 597,656.0 13,619,061.7

19. Unit Senice Factor 96.0 08.5 76.6

20. Unit Availability Factor 96.9 98.5 76.6

21. Unit Capacity Factor (Using.\\lDC Net) 69.2 92.h 63.2

22. Unit Capacity Factor (Using DER Net) 89.2 92.h 62.6

23. Unit Forced Outage Rate 3.1 1.5 h.9

24. Shutdowns Scheduled Oser Next 6 51onths (Type.Date,and Duration of Each):

N/A

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

II/A

26. Unit > In Test Status (Prior to Commercial Operation):

Forecast Ac'iieved INITIA L CRITICA LITY INITIA L ELECTRICI FY CO%151ERCIAL Ol'ER ATION (9/77)

s DOCKET NO. 50-285 I

UNIT SHUTDOWNS AND POWER REDUC 110NS UNIT NAME Fort Calbo"n #1

rch 8-1070 DATE COMPLETED BY

9. J. ifiekle REPORT MONTil Februarv. 1979 TELEPIIONE 402-530-4*13

.$ ?

"h

).5 Licensee

[ r, Cause & Corrective n

o No.

Date R

38 s

.a s s Event p

pU Action to

$=

3 ;g g Report a mV Prevent Recurrence H

ou g

C 79-01 79253 F

6.1 H

2 N/A Both outages caused by closure of turbine control valve due to 79-02 79256 F

14.6 H

1 N/A blown fuse during pressure trans-mitter replacement.

Pressure transmitters were replaced.

I 2

3 4

r F: Forced P.cason:

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-Administratise 5

G Operational Error (Explain)

Exhibit I Same Source (9/77) 1101her (Explain)

Refueling Information Ibrt Calhoun - Unit 16.1 Pcport for the nonth ending February 28, 1979.

1.

Scheduled date for next refueling shutdown.

January 1, 1980 March 1, 1980 2.

Scheduled date for restart follcuing refueling.

3.

Will refueling or resumption of operation thereaf ter require a technical specification change or other Yes license anendment?

If anse r is yes, what, in general, will a.

these 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 and core configuration been reviewd by your Plant Safety Review Comittee to deter-mine whether any unreviewed safety questions are associated with the core reload.

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

it scheduled?

Primary System Pressure 4.

Scheduled date(s) for submitting proposed licensing Analysis - October, 1979 Core Re1ated Ana1ysis action and support information.

and Tech. Spec. Changes -

5.

Impartant licensing considerations associated wi.th November, 1979 refueling, e.g., ncw or different fuel design or supplier, unreviewed design or performance analysis nethods, significant changes in fuel design, new operating procedures.

First use of Exxon fuel in Fort Calhoun.

Increasing primary system pressure from 2100 psia to 2250 psia.

to 1500 MW Stretching power from 1420 MWth th.

6.

The number of fucl assenblies: a) in the core 133 asserrblies b) in the spent fuel pool 157 c) spent fuel pool storage capacity 483 d) planned spent fuel pool storage capacity 483

• J. The projected date of the last refueling that can be' discharged tc the spent fuel pool assuming the present 1985 licensed capacity.

Prepared by k 'E W

Date March 3. 1979

T CMAHA PUBLIC PC'4ER DISTRICT Fort Calhoun Station Unit No. 1 February 1979 Monthly Operations Report 1.

C.PERATIONS

SUMMARY

Plant power level during the =cnth.of Februa:.y was maintainad at a nominal 99", with the exception of two power reducticus and one unit trip. The two power reductions were efforts to locate suspected condensor tube leakage. The reactor trip was initiated manually by operator action in response to a failure in the turbine supervisory circuit. The total length of the plant outage uo complete repairs to the turbine supervisory centrols and a small reacter ecolant pump blec-doff leet was 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />. Fever escalation was restricted to 70%

for the following 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> due to a failure of a necessary heater drain pump. After maintenance was cc=pleted en the heater drain pu=p power was es calated to a nc=inal 1CC,.

All surveillance tests were completed as scheduled with no =ajor abnor:alities detected. The annual overhaul on emergency diesel generatcr number cne var ac=pleted and the diesel suc.cessfully tested.

All licensed plant operations staff personnel participated in the oper-ator requalificatica exo*ation and in the sixth shift training classes.

One nev renber for the operaticas staff reported during the conth of February.

All required power operations tasks vere perfor=ed with no apparent prcble=s.

A.

PERFOP24ANCE CHARACTERISTICS LER 'Feber Deficiency 79-03

'4hile -m ng containment pressure release CP-79005 the night shift superviser noticed that the readings en the centainment air

=cnitor P240-50/51 vere abner 117 lov.

In-vestigation revealed that the isolation valves (.742 F&H) were closed. This rendered F20-51/52 ineffective for apprcximately h hours. During this time the ventilation valves frc= containment were closed and the pressure relief valves cper.

(9-Ch

• ield leel (0.2 gpm) en Reacter Ccolant Pu=p (yet to be RC-3C centrolled bleed-cff line. Unit was submittedl placed in a hot shutdown condition to effect repair.

f*

4 Monthly Operations Report Page Two February 1979 B.

CHA'IGES I:i CPERATI:IG METHODS Iione C.

RESULTS OF SURVEITJ.A ICE TESTS A:iD I:ISPECTIC:!S Surveillan;;e tests as required by the Technical Specifications Section 3.0 and Appendix 3, were perferred in accordance with the annual surveillance test schedule.

The felleving is a sunmary of the surveillance tests which results in Cperatiens Incidents and are not reported elsewhere in the repert:

Operations Incident Deficiency CI-738 ST-E'IV-3, 2-5-79, :IPDES l ion-Cc pliance -

Lageon discharge p2 out of spec. lov.

0I-748 ST-ETI-3, 2-20-79, :IPDES :Icn-Ccepliance -

Lagcon discharge pH cut of spec. Icv.

D.

CHA:IGES, TESTS A:iD E2?ERI'CITS CARRIED CU" '41TECUT CC'CESSIO:I APPROVAL Precedure Descrittien DCR 76-19 Electrchydraulic Centrol Pressure Transmitters installed with many field changes.

DCR 77-27 Fire Extinguishers installed with 21n12:=

field changes.

DCR 78-38 E-10 cut cut svitch was cenpleted as designed.

SP-CM-22 Opticum Precharge Pressure was cenpleted.

1500 psig was dete._ined to be correct pre-charge pressure fer nernal operation.

DCR 76-9

?rbine Plant Cocling Throttle Valve was cc=pleted as designed.

DCR 76-102 Turbine Plant Cooling Header isolatien for W hA, 3, C, was ccnpleted as designed.

SP-FAUD-1 Fuel Assembly Uplift Ccndition detectien. High values of lecp vessel ac nean greater than 99",

+

assurance that scre than 15 lb. icunvard force exists en the fuel assemblies.

f Monthly Operatiens Report Page Three February 1979 D.

(Continued)

Procedure Description DCR 77-82 Demineraliced ' dater Piping Mcdification at DC0 79-2 Addition Tank. Cc=pleted as designed.

DCR 77-109 Eunarounds for FP-150, FP-151, FP-152, FP-153 SRDC0 78-24 ccepleted as designed.

SRDC0 78-39 E.

RESULTS OF LEAK. RATE TESIS Special Procedure SP-CC:iT-2 was performed on penetration M-87 end M-88 Containment Purge Valves. Leakage was as follovs:

Leakage en M 3500 see:

Leakage on M 1000 sec=

F.

CEA'IGES IN PLANT CPERATING STAFF Mathev '4alker was empicyed as Auxiliary Cperator Nuclear.

G.

TRAINING Training in February included Operator requalification exams and extensive training en the ne's site security.

All badge holders at the Fort Calhcun Station vere required to attend these lectures.

Additic.:al training included at least ene hcur a week for all crafte en plant syste=s and precedures.

H.

CRANGES, TESTS AND EXPERD'I'iTS PEUIRI'IG NUCLEAR REGULATCRY CCDIISSICN AUTHORIZATION PURSUANT 0010CFR50.59 None Approved by Manager-Fort Calhcun Staticn

-o2 Menthly Opera:1cns Repcrt Februa:/ 1979

? age Four i

MA._:.A' 2 (Significant Safety Related)

M 0.

I Cate i

Oescrie:1:n i

Ocrree:1ve Act;en 21655 1-30-79 RPS "D" Channel lov subchannel Repaired coax cable calibrated spiking per SP-RPS-5 21h37 1-5-79 HCV-Th2A, B, C, D Leak Check Perfer=ed leak check per SP-CONT-2 20930 11-30-78 VA Cleaned cell; a'.th Completed cc= pressed air 216h8 1-31 -79 Waste Gas flow orifice record Cc=pleted data for Release Per=it #79001 217hh XCV-871A/B Inlet de=pers stuck open Cleaned ice off da=pers 2169h 2-5-79 Fire alar = bell in wareh'use does Unplugged frocen drain line not alar:

21732 2-6-79 Diesel Generator #1 air ec= pressor Cleened fuel syste=

vill not keep running 21729 2-6-79 CH-lc Charging Pu=p is lenktng cut Repairs ec=pleted of middle pisten 21317 1-24-79 AC-3B Outboard seal leaking Relapped seals 21507 2-26-79

' FP-212 Valve leaking Changed valve and gasket 21783 2-14-79 LG-1 Lov Crankcase oil level Adjusted en S*-F.SF-6 21837 2-16-79 Control Roc = Air Conditiening Unit Lcw limit svitch reset tripped cut 21827 2-16-79 Fire Protection varehouse sprinkler Paddle wheel freed up system alar:

21606 Five Protection jcekey pu=p Packing tightened and leak pachng lee.kage stopped i

.