ML20070Q770

Monthly Operating Rept for Nov 1982

ML20070Q770
Person / Time
Site:	Summer
Issue date:	12/08/1982
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20070Q749	List: ML20070Q746 ML20070Q770
References
NUDOCS 8301270164
Download: ML20070Q770 (5)

Text

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Director, Office of Management and Program Analysis Page 2

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De: ember 8, 1982 ATTACHMEfff I AIERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50/395 UNIT v.c.5 mmer I DATE 12-08-82 COMPLETED BY G.J Tavior TELEPHONE (803) 345-5209 MONTH NOVEMBER 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Ne:)

1 0

17 29 2

0 13,

n l

l 3

n jg iA l

0 3

5 4

0 2

l 5

M

(

0 30 6

22 0

91 l

7 g

O 123 8

, 24 0

115 9

2?

0 M2 10 26 11 0

gy 143 0

170 12 28 13 0

29

-156 0

0

- 14 y

0

.N/A gg 3

14_

5 8301270164 821208 PDR ADOCK 05000395 R

PDR g

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Director, Office of Managemer c and Program Aialysis Page 3 December 8, 1982 ATTACHMENT II OPERATING DATA REPORT DOCKET NO.

50/395 V.C. Summer I UNIT e

12-08-82 DATE G.J. Taylor ~ ~

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COMPLETED BY (803) 345-5209 TELEPHONE OPERATING STATUS 720 IIOVEMBER 1982 Gross HOURS IN RhPORTING PE81tOO:

1. REPORTING PERIOD:

N/A 2775 MAX. DEPEND. CAPACITY (MWerNet):

2. CUM ENTLY AUTHORIZED POWER LEVEL (MWti:

DES! JN ELECTRICAL RATING (MWo.Neel:

9 0 0.,,,,,

N/A (50% MWt)

3. POWER LEVC.TO WHICH RESTRICTED (IF ANY) (MhNet):

4. REASONS FOR RESTRICTION llF ANYl:

The Operating License allows operations to mis MONTH YR TO DATE CUMULATIVE

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50% MWt fer power operations testing.

484.3 655.7 655.7

5. NUMBER OF HOURS REACTOR VEAS CRITICAL 0

0 0

4. REACTOR RESERVE SHUTOOWr4 HOURS...................

192.3 192.3 192.3

7. HOURS GENER ATOR ON LINE..........................

0 0

0 S. UNIT RESERVE SHUTDOWN HOURS......................

9. GROSS THERMAL ENERGY GENERATED (MWH).............

143.789 144,802_

144,802 30.567 30.567, 30,567

10. GROSS ELECTRICAL ENERGY GENERATED (MWHI.............

24.839 24.839 24,839

11. NEY ELECTRICAL ENERGY GENERATID (MWH)

N/A N/A N/A

12. REACTOR SERVICE F ACTOR...........................

• N/A.

N/A N/A

13. REACTOR AVAILABIllTY F ACTOR.......................

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 N/A

16. UNIT CAPACITY FACTOR (using MDC) 7....................

N/A N/A N/A

17. UNIT CAPACITY FACTOR (Using Design MWel.................

N/A

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N/A N/A

18. UNIT FORCED OUTAGE R ATE..........................

19. SHUTDOWN 4 SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACHl:

(

i D-3 Steam Cenerator Modification -- March 1983, through May,1983 M/A

20. iF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPGRATION):

FORECAST ACHIEVED 10-20-82 10-22-82 INITIAL CRITICALITY l1-l7-82_ 11-16-82 INITIAL ELECTRICITY I

COMMERCIAL OPERATION l

Director, Office of Management and Program Analysis ATTACHMENT III DOCKET NO. 50/395 Page 4 December 8, 1982 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME V. c. S u==ar i I) ATE 19 nn n?

COMPLETED BY _G J. Tavlor REPORT MONTil NOVEMBER 1982 TELEPHONE (803) m-mo METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR GR NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER (2)

CORRECTIVE ACTION 0mENTS

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N/A 821116 S

382.0 H

4 Initial Plant Start-up Testing I'

82?l17 F

54.7 G

3

1) Reactor trip due to low-low level in Steam Generator "B".

2 d21119 S

14.0 H

2

2) Tripped reactor while performing control room evacuation test.

3 (821120 F

19.3 G

3

3) Reactor trip due to low-low la"al. it all Steam Generators.

4 821121 S

12.3 H

4

4) Tripped reactor while performing Station Blackout Test.

5 821122 F

18.5 C

3

5) Reactor trip due to low level in Deaerator tank, caused main feen-water pumps to trip causing turbine to trip, in turn tripping reactor.

6 821129 F

26.9 G

3

6) Reactor trip due to low-low level in g

B Steam Generator while performing i

Steam Generator level test.

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Director, Office ~ofcManagement and-Program Analysiv Page15 December 8, 1982 ATTACHMENT IV NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 4

1The Nuclear Regulatory Commission granted Virgil C.

Summer Nuclear Station Unit No. 1 permission to allow teating and operations to a 50% MWth power level at 1821 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.928905e-4 months <br /> November 12, 1982.

Immediately thereaf ter, commencement of the power ascension. testing program took ' place.

At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> November 16, 1982, Virgil ~C.

Summer Nuclear Station was syncronized to the grid at a 10%. power level and produced its first electricity.

A reactor trip occurred ' at 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />' November 4,1982, from 0%

power.

The trip was due to a low-low-level in Steam Generator "B" while-in manual control.

On. November 11, 1982-at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, problems were encountered in

'the. operation-of Main Feedwater Isolation Valve "A".

Then the Plant was-subsequently shut down for corrective action.. It was

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determined later that a redundant solenoid was faulty. -It was replaced, and th'e valve was put back into service.

The valve was considered to have been Technical Specification operable during the duration of -this condition.

c A reactor - trip occurred Iat 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> November 13,1982, Efran 2%

power.

The trip was due to low feedwater flow to "C" Steam Generator.

This occurred due to a. steam flow noise spike on Steam Generator "C" steam flow instrumentation, while testing N-41 Nuclear Instrumentation.

A reactor trip occurred at 2011 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.651855e-4 months <br /> November 13,1982, from 2%

power.

This trip was due to low-low level in Steam Generator "C".

Feedwater was in manual control, and feedwater was isolated due to-high flow through the feedwater bypass valve.

Steam Generator level decreased before operator could recover.

i A reactor trip occurred at 1444 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.49442e-4 months <br /> November 17, 1982, from 2%

. power.

The trip was due,to low-low level in Steam Generator "B"

. hile transferring emergency feedwater flow to main feedwater w

flow.

A reactor trip occurred at 2138 hours0.0247 days <br />0.594 hours <br />0.00354 weeks <br />8.13509e-4 months <br /> November 17,1982, from 35 power.

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

A reac. tor trip' occurred at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> November 19,1982, from 6%

. power.

The trip was due to low-low level in Steam Generator "C".

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- Director, Office - of. Management and Program Anal'ysis-Page 6 December'8, 1982/

ATTACHMENT IV Continued At.2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> November 19, 1982, a control room evacuation test.

was conducted which resulted in a manual trip of. the plant.-

' Control.of-the - plant was satisfactorily maintained while away

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from the Control Room.

A reactor trip occurred at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> November 20,1982, 'from 2%

power.

The trip, which was due to Steam Generator Low-Low Level,

. occurred.while ettempting to transfer feedwater flow from emergency to main feedwater flow.

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A ' reactor trip occurredLat 1626 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.18693e-4 months <br /> November 20,1982, from 12%

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power.

The trip was_due to low-low level in all steam generators.

Feedwater Isolation Valves A, B, and C tripped when feedwater temperature dropped belor: 225 F.

The feedwater temperature decrease was due to a flow transient in the deaerator tank which caused a cooldown in feedwater.

A reactor trip occurred at 0457 hours0.00529 days <br />0.127 hours <br />7.556217e-4 weeks <br />1.738885e-4 months <br /> November 21,1982, from 1%

power.

The trip,.which was due to Steam Generator Low-Low Level,

. occurred while warming up main feedwater lines and transferring feedwater flow ' f rom emergency to main feedwater flow.

At 1419 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.399295e-4 months <br /> November 21, 1982, a Station Blackout Test was conducted which resulted in a plant trip.

The plant performed as expected, and the test was satisfactorily completed.

F A reactor trip occurred at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br /> November 22, 1982, from 21%

power..The trip was a result of a feedwater pump trip due to low-low deaerator tank level, while attempting to transfer to main feedwater valves.

The feedwater booster pump and feedwater pumps tripped from low level in the deaerator storage tank.

This i

caused the main turbine to trip, subsequently causing the reactor to trip' when power level is greater than 10%.

A reactor trip occurred at 2008 hours0.0232 days <br />0.558 hours <br />0.00332 weeks <br />7.64044e-4 months <br /> November 29,1982, from 30%

' power.

The trip was due tp low-low level in Steam Generator "b".

The trip occurred while pefforming a Steam Generator level test due to a sticking feedwater regulator valve.

Virgil C.

Summer Nuclear Station is presently continuing power ascension testing to a 50% MWth powcr level.

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