ML19253B407

Monthly Operating Rept for Sept 1979

ML19253B407
Person / Time
Site:	Rancho Seco
Issue date:	09/30/1979
From:	Columbo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML19253B402	List: ML19253B401 ML19253B407
References
NUDOCS 7910150507
Download: ML19253B407 (6)

Text

.

NARRATIVE

SUMMARY

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

Perfo rmed thru routine surveillance and preventive maintenance items.

9-11 9-12 (1539)

Turbine Overspeed Protection control transmitter malfunction causeo Turbine Generator trip and corresponding Reactor trip.

Plant went to hot shutdown following trip.

(1940)

Commenced Reactor Startup.

(2029)

Reactor critical.

-8 (2045)

Reactor at 10 amps.

(2154)

Reactor at 5% power.

(2300)

Reactor at 10% power.

(2350)

Reactor at 13% power.

~

9-13 (0124)

Generator on line (closed OCB's 220 and 230).

(0131)

Increasing to 50% full power.

(0154)

Reactor trip on power / flow / imbalance on Reactor Protection System, Channels "A" and "D".

(0412)

,eactor critical.

(0511)

Reactor at 15% power.

(0848)

Generator on line.

(OCB's 220 and 230 closed.)

(1153)

Reactor at 50% full power.

(1250)

Began increasing power to 92%.

(1600)

Reactor at 88% full power for 2-hour hold (%790 MWe).

(1801)

Raising Reactor power to 100% at 5% per hour.

(2008)

Reactor at 100% full power (905 MWe).

9-14 (1209)

"A" Main Feed Pump tripped on overspeed.

Instrument Control System runback to 55%.

Replaced fuse on "A" Main Feed Pump and began increasing power to 72%.

(1300)

Reactor at 72% (%651 MWe).

},[2 h}h (1325)

Increasing power to 92%.

7910150 Q~

. 9-14 (1405)

Reactor at 88% (%794 MWe) - started 2-hour hold.

(1520)

Reactor at 92% (m840 MWe) for 2-hour hold.

(1605)

Increasing power to 100%.

(1720)

Reactor at 100% full power.

9-23 (1630)

Reduced power to 96% from N905 MFe to s870 MWe due to high motor thrust bearing temperature on "C" Main Circulating Water Pump (P-402C).

9-24 (0014)

Raising power to 100%.

(0200)

Reactor at 100%.

Pj'SONNEL CHANGES REOUIRING REPORTING No oersonnel changes that require reporting in accordance with Technical Specifications Figure 6.9-2 were made in September, 1979.

MAJOR ITEMS OF SAFETY-RELATED MAINTENANCE 1.

Continued inspection / testing of pipe supports; repaired or replaced as necessary to meet the new criteria covered in Bulletin 79-02.

2.

Performed maintenance (replaced contacts) on Motor Driver Fire Pump breaker.

SUMMARY

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

No changes, tests, or experiments were completed in September,1979, which constituted a change in a safety analysis report description.

i, :.~

017

l FIFUELING I. TOPS.ATIO: REqEST Pancho Seco Unit 1 1.

Name of Facility:

January, 1980 2.

Scheduled date for next refueling shutdown:

March, 1980 3.

Scheduled date for restart following refueling:

Technical Speci fication change or other license acendment requi' red:

4:

a) Change to Rod Inde:: vs. Power Level Curve (TS 3.5.2) b) Change to Corc I= balance vs. Power Level Curve (TS 3.5.2)

'c) Tilt Limits (TS 3'.5.2) d) Safety Equipment Testing (TS 3.3.3)

December, 1979 Scheduica date(s) for submitting proposed licensing action:

5.

~

N ne 6.

Important licensing considerations associated with refueling:

7.

Nu,cber of fuel asser.blies:

177 a) In the core:

b) In the Spent Fuel Fool:

112 S.

Present licensed spent' fuel capacity:

579 Projteted date of the lant refueling that can be discharged 9.

to the Spent Fuel Fool:

log 7 I:

^

018 "m*m m==

l

AVERAGE DAILY L* NIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco_ypit 1

~

DATE 79-09-30 R. W. Colombo COMPLETED BY TELEPh[ONE (916) 452-3211 MONTil Sep tem';er DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA!LY POWER LEVEL (MWe-Net 1 (MWe-Net) g 865 17 860 863 2

830 18 863 3

860 39 861 4

20 860 858 861 21

'6.

855 861 22 857 7

23 848 858 8

_856 24 861 864 9

~'

858 10 864 2(

II 855 861 77 541 12 E

M 367 13 860 29 853 14 30 858 848 g5

~~

31 850 INSTRL'CTIONS On tha forma.!ist the nerage daily unit power lesel in MWe Net for each day in the report ty m,inth.Compure to i

the nearest whoie tr.epwatt-(9/77 )

O r3 4 O 6 j

OPERATING DATA REPOPT

-4 DOCKET NO.

50-312 DATE 79-09-30 COSIPLETED BY R. W.

Colombo TELEPHONE (91M 452-3211 OPERATING STATUS Rancho Seco Unit 1

1. Unit Name:.

Notes

2. Reporting Pet.d:

September 1979

3. Licensed Thermal Power (31Wtp:

2772

4. Nar. ate Rating (Gross.\\lWe):

OM

5. P

,n Electrical Rating (Net.\\lWe):

918

6. 1.

<imum Dependable Capacit3-(Gross.\\lWe):

917

7. Afaximum Dependable Capacity (Net 31We):

371

8. If Changes Occur in Capacity Ratings qltems Number 3 Ti. rough 7) Since Last Report. Give Reasons:

N/A

9. Power Level To Which Restrictes'..f Any (Net 31We):

N/A

~

10. Reasons For Restrict' ins. If Any:

N/A This ifonth Yr..to.Date Cumul$tise

11. Hours In Reporting Period 720 6,551 39,048

12. Number Of Hours Reactor Was Critical 712.9 4,856.3 23,927.1

13. Reactor Reserve Shutdown Hours 4.8 1,524.0 3,941.4

14. Hours Generator On-Line 701.4 4_774.o 99_gqg_1

15. Unit Reserve Shutdown Hours 0

1.199.3 1.210.2

16. Gross Thermal Energy Generated (31WH) 1,932,177 12,906,100 57,979,256

17. Gross Electrical Energy Generated #31WH) 620,429 4,21.7,709 19,480,509

18. Net Electra! Energy Generated t.ith H) 588,881 4,001,171 18,400,061

19. Unit Service Factor 97.7 72.1 58.6

20. Unit Availability Factor 97.7 90.4 61.7

21. Unit Capacity Factor iUsing SIDC Net) 93.7 70.0 54.0

22. Unit Capacity Factor (Using DER Net) 89.1 66.5 51.3

23. Unit Farced Outage Rate 2.3 5.4 33.7

24. Shutdowns Scheduled Oser Nest 6 Stonths (Type. Date,and Duration of Each):

Refueling: January, 1980; duration approximately 60 days.

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

/A

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

Forecast Achiesed INITIA L CRITICA LITY N/A INITIAL ELFrTRICITY N/A _

N/A N/A COM3IERCI A L OPERATION N/A

l/ A 1

n 10/77)

>,x 020

[

t DOCKET NO. 50-312 b

UNIT SilUTDOWNS AND POV'ER REDUCTIONS UNI T NAME Rancho Seco Unit 1 DA1E 79-09-10 COMPI.T i ED itY R. W.

Colombo REPORT MONTil ~ September T El.E Pil0 N E (91 0 457-1711 N

CD N

~

t, )

jg 3

'8 Licensee

[ g,

'o Cause A Corrective No.

Date F

~?

s

.3 E $

Event

?

n-8 Action to S

j$

3dc Report a d'0

$U Prevent Recurrence e

o a

11 79-09-12 F

8.4 A

3 N/A N/A N/A Turbine / reactor trip on turbine over-speed protection control transmitter failure.

12 79-09-13 F

8.3 A

3 N/A N/A N/A Reactor trip on power / flow / imbalance on reactor protection system, channels "A" and "D".

I 2

3 4

F: Forced Reason:

!!ethod:

Exhibit G - Inst ructions S: Scheduled A Ei;uipment Failure (Explain)

Manuel for Prepar.ition of Data B. Maintenance of Test

-Manual Scram.

Entr> Sheets for Licensee C. Refueling

.Autinnatic Scrant.

Event Report (1.L R: file (NUREG-D Regulatory Restriction

. -Other (Explain) 0161)

I'.-Operator Training & l.icense Examination I Adr::inist rativt' r;-Oper.otona' I) tor (I splain)

I slitbit I - Same Source

('7/77) 11 Other (1 xplain)