ML20147B718

Monthly Oper Rept for Sept 1978

ML20147B718
Person / Time
Site:	Rancho Seco
Issue date:	10/03/1978
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20147B716	List: ML20147B711 ML20147B718
References
NUDOCS 7810110126
Download: ML20147B718 (6)

Text

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, AVERAGE DAILY UNIT POWER LEVEL

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• DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 78-09-30 COMPLETED BY R. W. Colombo TELEPilONE _(916) 452-3211 MONTil September .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j Othe-Net) (MWe-Net )

l 885 37 871 2 885 gg 894 3 688 39 891 4 663 892 20 5 889 21

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892 6 891 889 22 7 890 23 887 8

895 24 883 9 894 25 880 10 266 26 887 33 867 891 27 .

12 884 886 28 13 886 885, 29 14 886 884 30 IS 457 3g 16 0 l

INSTRUCTIONS .

On this format.hst the aver.rge daily unit power inel in MWe Net for each da) in the reporting month. Compute to the nearest whole megawatt.

J (9/77)

} .] 8 lh

UNITSHUTDOWNS AND POWER REDUCTIONS w DOCKET NO. 50-117 UNIT NA3f E Rancho Seco Unit 1 DATE 78-09-30 COMPLETED BY R. W. Colombo REPORT M0ffTil SEPTFlfBER TELEPflONE (916) 452-3211.

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_ E c No.

-, ,$? 3 $Y5 Licensee $g j% Cause & Corrective D.ste 3 3g 4 2g5 Event gg o-3 Action to H

$E 5 5@cg Report a mU u

!O Pievent Recurrence O

16 78,0903 F 2.9 G 3 N/A HA MECFUN While removing cover on turbine

" auto-stop control block" for training purposes, the gasket caught on a linkage rod and tripped unit.

17 7'80910 S 11.7 B 1 N/A CB MOTORX Shutdown to facilitate adding oil to RCP "C" motor-upper bearing, and in-specting'RCP stuffing box flanges.

18 780915 F 31.8 A 1 N/A RB CRDRVE Dropped Rod No. 3 Group 7. Shutdown manually to replace CRD Statdr.

4, I 2 3 4 F: Forced Reason: . p Method: Exhibit G - Instructions S; Schn!uled A Equipment Failure (Explain) 1-Manual for Preparation of Data ll-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee -

C-Refueling 3-Automatic Scram. Event Report (LE R) File (NUREG-D-Regulatory Restriction 4-01her (Explain) 0161)

E-Operator Training & License Examination F Adrnimstrative y 5 G Operational Esroi (Explain) Exhibit I - Same Source (9/77) -

II Other (lixplain)

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OPERATING DATA REPORT DOCKEINO. 50-312 DATE 78-09-30 COMPLETED .BY R. W. Colombo TELEPlf0NE -(916 ) 452-3211 OPERATING STATUS l

1. Unit Name: Pnncho h r' n Uni'- 1 Notes

2. Reporting Period: fetw ber 1978  !

3. Licensed Tiurrnal Power (SDVti: 2772

4. NamepLte Ratia;IGro>s 31Wel: 963

5. Des?;n Electrical RatinpNet 31We): 918

6. Sluimum Dependable Capacity (Gross MWen 917 g )

7. Sfaximum Dependable Capacity (Net MWer 873

8. If Changes Occur in Capacity Ratigs 11tems Number 3 Through 7) Since Last Report. Gise Reasons:

N/A {

9. Power Lese! To which Restricted,if Anv (Net 31We): NONE

10. Reasons Fer Restrictions,if Any: N/A This 5!onth Yr. to.Date Cumulative II. Hours in Reporting Period 720 6.551 30.288

12. Number Of flours Reactor Was Critical 689.8 5,919.7 17,695.9

13. Reactor Re<ene Shutdown Hours 0 0 2.417.4

14. Ilour> Gcaerator On.Line _ 673.6 5,724.6 16,838.1

15. Unit Re3ene Shutdown Houn 0 0 10.8

16. Gross Thermal Energy Generated (51% H) 1.828.062 12.466.199 41.597.922

17. Gross Electric ! Energy GenerateJ IMWili 600,528 4,142,135 14,081,385 e 18. Net Electrica! Ener;y Generated (5thH) _.

574,322 3,873,564 13,284,773

19. Unit Senice Factor 93.6 8 7 . 4_, 55.6

20. Unit Asai! ability Factor 93.6 87.4 55.6

21. Unit Car:reity Fa:ror iU>in; MDC Net) 91.4 67.7 50.2

22. Unit Capacity Factor iU3ing DER Net) 86.9 64.4 47.8

23. Unit Forced Outage Rate 4.8 10.0 37.4 2.r. Shutdowns ScheJuleJ Oser Nest 6.s oaths (T)pe. Date.:nd Duration of Eacht:

Refueling shutdown November 16, 1978, approximately 37 days.

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

26. Unin in Test Statu> iPrior to Conmere:al OperationI: Forecast Achiesed INITIAL CRIT!C 1LITY _ N/A N/A INITIAL ELECTitlCITY __N/A N/A CO\!MERCl \L OP:.R ATION N/A ~ N/A

~

(u/77)

L .r

NARRATIVE

SUMMARY

OF PLANT OPERATIONS 1 Date 9-1 Plant operating.at 100% full power.

l 9-3 (1839) Turbine / Generator and Reactor Trip. (While removing cover on " Turbine.

Auto Stop Control Block", for training purposes, gasket caught on  !

control linkage'and unit tripped.)

(2026) Reactor critical.

(2040) Latched and rolled turbine.

(2130) Closed OC3's.

9-4 1 (0718) . Reactor at 87% full power. j (1015) Reactor at 100% full power. l 1

9-10 (0400) Commenced plant shutdown, reduced load @'10 MWe/ min.

(0528) Opened OCB's. ,

(0645) Reactor at 108 amps. )

(1240) Started to increase reactor power. l (1610) Latched and rolled turbine. I (1709) Closed OCB's.

(1955) ' Reactor at 50% full power.

(2323) Reactor at 87% full power.

9-11 (0515) Reactor at'100% full power. -

9-15 1 (1042) Received "Assynetric Rod" alarm Group 7 Rod No. 3.

(1045) ICS runback.

(1108) Reactor at 55% full power.

(1327). Started-decreasing reactor power.

(1411) Opened OCB's.

(1524) Reactor 10~8 amps and being taken subcritical.

9-16 (1950) Peactor critical.

(2200) Closed OCB's.

9-17 (0025) Reactor at 87% full power.

(0618) Reactor at 100% full power.

PERSONNEL CHANGES REQUIRING REPORTING No personnel changes that require reporting in accordance with Technical Specifications, Figures 6.2-2 were made in September 1978.

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MAJOR ITEMS OF' SAFETY RELATED MAINTENANCE h 1.) Changed gears lLn motor operator for SFV-26006 Decay Heat Loop.B

. building isolation valve.

2) Replaced bolts on diesel driven fire pump coupling (LER 78-9).

3.) Replaced failed solenoid for FV-99809, CO2 storage tank outlet valve (LER 78-12).

4.) Replaced bellows in FT-23807, HPI flow transmitter (LER 78-13).

SUMMARY

OF CHANCES MADE IN ACCORDANCE WITH 10CFR 50.59(b)

No changes, tests, or experiments were completed in August 1978 which constituted a change in a Safety Analysis Report description.  !

l a64 h

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• REFUELING INFORMATION REQUEST

1. Name of Facility - Rancho Seco Unit 1

2. Scheduled date for next refueling shutdown - November 16, 1978

3. Scheduled date.for restart following refueling - December 23, 1978

4. Technical Specification change or other license amendment required -

a.) Change to Rod Index vs. Power Level Curve (T.S. 3.5.2) b.) Change to Core Imbalance vs. Power Level Curve (T.S. 3.5.2) c.) Tilt Limits (T.S. 3.5.2) d.) Safety Equipment Testing (T.S. 3.3.3)

5. Scheduled date(s) for submitting proposed licensing action. - September 11, 1978

6. Import?nt licensing considerations associated with refueling - None o

7. Number of fuel assemblies (a) In the core - 177 (b) In the Spent Fuel Pool - 56 spent; 56 new

8. Present licensed spent fuel capacity - 579 '

9. Projected date of the last refueling that can be discharged to the Spent Fuel Pool - g i

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