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

- . _ . .. . . . . _ _ _ ._.

k.

n' ?

Director, Office of Management and Program Analysis

+- Page 2 De: ember 8, 1982 ATTACHMEfff I

" ~

~

AIERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50/395 UNIT v.c.5 mmer I DATE 12-08-82 COMPLETED BY G.J Tavior

- TELEPHONE (803) 345-5209 NOVEMBER 1982 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

! (MWe-Net) _

(MWe-Ne:)

1 0 17 29 0 13 , n -

2 .,

l 3 n jg iA l

0 3 5 l 4 5

0 M 2 l

(

0 22 30 6

0 g 91 l 7 O 123 8 _.

, 24 ,,

0 2?

115 9

10 0 26 M2 11 0 gy 143 0 170 12 28 13 0 29 -156 0 y 0

- 14 ,

gg 0 .N/A

_ 3 14_ 5 8301270164 821208 PDR ADOCK 05000395 PDR R

g ., y, -r, - - - - - -

Director, Office of Managemer c and Program Aialysis Page 3 December 8, 1982 ATTACHMENT II OPERATING DATA REPORT DOCKET NO. 50/395 UNIT V.C. Summer I e

DATE 12-08-82

~

G.J. Taylor ~ ~

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

1. REPORTING PERIOD:

2775 MAX. DEPEND. CAPACITY (MWerNet):

N/A

2. CUM ENTLY AUTHORIZED POWER LEVEL (MWti: 9 0 0 .,,,,,

DES! JN ELECTRICAL RATING (MWo.Neel:

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 50% MWt fer power operations testing. 655.7 655.7 484.3

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 ......................

143.789 144,802_ 144,802

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

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

~

N/A N/A

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

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

(

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

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

FORECAST ACHIEVED

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

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

~

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.

18.5 5 821122 F 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.

t

n l' .

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 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"

.w hile transferring emergency feedwater flow to main feedwater 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".

l

,v; < -

- 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

~

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.

?

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%

~

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 i

pumps tripped from low level in the deaerator storage tank. This 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.

__,