ML20077K438

Monthly Operating Rept for Dec 1982

ML20077K438
Person / Time
Site:	Summer
Issue date:	01/05/1983
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20077K435	List: ML20077K432 ML20077K438
References
NUDOCS 8301130035
Download: ML20077K438 (4)

Text

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Director, Office of Management and Program Analysis Monthly Operating Report Page 2 January 10, 1983 ATTACilMENT I

~ AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO. 50 /395 I

UNIT v.c. summer I DATE 01-05-83 COMPLETED BY c.J. Tavlor TELEPHONE (803) 345-5209 I

l I

l MONTH DECEMBER 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 0 17 216 1

0 2

I 18 167 0

3 39 238 195 20 l

4 396 194 21 5

136 I93 22 6

7 198 23 308 l

4I1 8

196 24 9

197 25 409 409 202 26 10 408 252 g

gg I43 12 350 28 0

13 384 29 14 383 30 141 15 187 31 409 16 400 l

8301130035 830110 PDR ADOCK 05000395 i

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PDR

3 Director, Office of Management and Program Analysis Monthly Operating Report ATTACHMENT II Page 3 OPERATING DATA REPORT January 10, 1983 DOCKET NO.

50/395 UNIT V.C. Summer T 01-05-83 DATE G.J. Tavlor COMPLETED BY (803) 345-5209 TELEPHONE OPERATING STATUS 744

t. REPORTING PERIOD:

N CP'9FR 10R' GROSS HOURS IN REPORTING PERIOO:

2775 MAX. DEPEND. CAPACITY (MWo. Net): N/A

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):

DESIGN ELECTRICAL RATING (MWe-Net):

900 NA (50% MWth)

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

4. REASONS FOR RESTRICTION (IF ANY):

The Operating License allows operations to 50%

TuiS MONTw yR To oATE CUMULATIVE MWth for power operations testing.

651.1 1306.8 1306.8

5. NUMBER OF HOURS REACTOR WAS CRITICAL 0

0 0

6. REACTOR RESERVE SHUTDOWN HOURS 569.0 761.3 761.3-

7. HOURS GENERATOR ON LINE O

O O

8. UNIT RESERVE SHUTDOWN HOURS

........... 651,071 795,873 795,873 l

9. GROSS THERMAL ENERGY GENER ATED (MWH) 185.650 216.217 216.217 l

10. GROSS ELECTRICAL ENERGY GENERATED (MWH).............

)

106.357 lo1.196 191 106 l

11. NET ELECTRICAL ENERGY GENERATED (MWH)

12. REACTOR SERVICE FACTOR..................

l

13. REACTOR AVAILABILITY FACTOR.....................

N/A N/A N/A

14. UNIT SERVICE F ACTOR N/A N/A N/A

15. UNIT AVAILABILITY F ACTOR N/A N/A

16. UNIT CAPACITY FACTOR (Using MDC) '.'.

N/A N/A N/A

17. UNIT CAPACITY F ACTOR (Using Design MWel A

WA

18. UNIT FORCED OUTAGE RATE

19. SHUTOOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND OURATION OF EACH):

D-3 Steam Generator Modification - March, 1983, thru May, 1983.

N/A M. IF SHUT DOWN AT END OF REPORT PERIOD ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION):

FORECAST ACHIEVED 10-20-82 10-22-82 INITI AL CRITICALITY 11-17-82 11-16-82 INITIAL ELECTRICITY COMMERCI AL OPER ATION

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Director, Office of Management and TTACHMENT III DOCKET NO. 50/395 Program Analysis Monthly Operating Report UNIT SituTDOWNS AND POWER REDUCTIONS UNIT N AME V.c. summer I i

Page 4 I.) ATE 01-05-81 January 10, 1983 COMPLETED BY G.

3. Tavlor TELEPilONE (803) 345-s209 REPORT MONTi{

DFCEMBFR 1982 METHOD OF TYPE SHUTTING DOWN F: FORCED OURATION THE REACTOR OR NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER (2)

CORRECTIVE ACTIONS / COMMENTS 6

821129 F

46.7 G

3

6) Reactor trip due to low-low level in "B" Steam Generator while performing Steam Generator level test.

7 821217 F

62 5 G

3

7) Reactor trip due to hi-hi Feedwater lleater level, which caused turbine /

reactor trip.

8 821222 F

14.6 G

3

8) Reactor trip due to low-low level in Steam Generator "C", due to loss of Feedwater (Low Feedwater pressure signal).

9 821228 F

51.2 G

3

9) Reactor trip due to returning to service from a test, of the Solid State Protection System Multiplexer.

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's Director, Office of Management and Program ?.nalysis Monthly Operating Report Page 5 January 10, 1983 ATTACHMENT IV NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Virgil C.

Summer Nuclear Station Unit No. 1, has been in the process of continuing the power ascension test program to a 50%

MWth power level.

A 50% MWth power level was attained at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, December 12, 1982.

At 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />, December 1, 1982, the unit tripped from a 2% power level.

The trip was due to a low-low level in Steam Generator "A"

while on emergency feedwater and attempting to raise power to 5% with the Main Steam Isolation Valves closed.

A reactor trip occurred at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, December 1, 1982, from 0%

power.

The trip was due to a steam flow feed flow mismatch with a low level in Steam Generator "C".

A reactor trip occurred at 1326 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.04543e-4 months <br />, December 17, 1982, from 50% power.

The trip was due to a Hi-H1 level in 6 A Feedwater Heater, which caused a turbine / reactor trip.

Work 'was being performed on the level controller, which caused a level deviation.

A reactor trip occurred at 0851 hours0.00985 days <br />0.236 hours <br />0.00141 weeks <br />3.238055e-4 months <br />, December 22, 1982, from a 50% power level.

The trip was due to a low-low level in Steam i'

Generator "C".

This low-low level was caused by low feedwater flow.

Coincident with this reactor trip, pressurizer pressure indicated low which closed the pressurizer spray valves and energized the pressurizer heaters.

This, combined with control rods being in manual, caused actual pressurizer pressure and level to increase so that the pressurizer Power Operated Relief Valves cycled several times.

The event was caused by de-energization of the reactivity computer, which was monitoring points connected to the process control racks.

l A reactor trip occurred at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br />, December 28, 1982, f rom a l

50% power level.

The trip was caused by returning Train "A" of j

the Solid State Protection System multiplexer switch to the "A and B" position with B train reactor trip bypass breaker closed.

This gave a General Warning alarm on both " A" and "B"

trains of l

the Solid State Protection System, which in turn caused the i

reactor trip.

t Virgil C.

Summer Nuclear Station is presently operating at 50%

power and continuing the power ascension test program.

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