ML20107A693

Rev 1 to Monthly Operating Rept for Dec 1984

ML20107A693
Person / Time
Site:	Summer
Issue date:	12/31/1984
From:	Loignon G SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20107A679	List: ML20107A693 ML20107A703
References
NUDOCS 8502200079
Download: ML20107A693 (5)

Text

-

Director, Office of Resource Management December-Monthly Operating. Report January-14, 1985 ATTACHMENT I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50/395 UNIT V.

C. SUMMER I

.DATE 01/11/85 COMPLETED BY G.

A. Loignon TELEPHONE (803) 345-5209 MONTH

' DECEMBER 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

~(MWe-Net) 1.

-14 17.

-32 2.

-12 18.

-33 3

-14 19

-32 4.

-17 20.

40 5

-13 21.

226 6.

-14 22.

388 7

-28 23 510 8.

-28 24.

645 9

-36 25.

592 10.

-19 26.

658 11.

-16 27.

329 12.

-18 28.

322 4

13

-35 29 644 14.

-35 30.

648 15

-34 31.

651 16.

-32 1

pgj22OOO79850130 ADOCK 05000395 R

PDR

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- Director,l Office _of Besource Management

' December Monthly: Operating Report-

'Page 2-

~

-January:14,11985

-ATfACIMENT <II OPERATING: DATA REPORT DOCKEP NO. 50/395 UNIT V. C. SLNMER I -

DATE 01/11/85-COMPIETED BY G. A. Loignon TELEPHONE (803)'345-5209

OPERATING STA'1US i ~

1. Reporting Period:

DECEMBER 1984 Gross Hours in Reporting Period: 744

2. Currently Authorized Power Level (MWt):

2775 Max. Depend. Capacity (MWe-Net): '

885 Design Electrical-Rating (MWe-Net):

.900

3. Power Level to which restricted-(If Any)(lWe-Net): N/A-4.~ Reasons for Restrictions (If Any): N/A 3.

THIS lON11I YR TO DA'IE CUMULATIVE

5. Nunber of Hours Reactor Was Critical 299.9 5,553,4 5,553.4 i

6. Reactor Reserve Shutdown Hours 0-0 0

7. Hours Generator on Line 270.1 5,365.7 5,365.7

8. Unit Reserve Shutdown Hours 0

0 0

9. Gross 7hermal Energy Generated (MWH)

10. Gross Electrical Energy Generated (MWH).

455,882 13,332,586 13,332,586 145,810 4,432,149 4,432,149

11. Net Electrical Energy Generated (MWH) 124,707 4,192,0 %

4,192,096

12. Reactor Service Factor 40 3 63 2~

63 2

13. Reactor Availability Factor 40 3 63.2 63 2

.l

14. Unit Service Factor.

36 3 61.1 61.1

15. Unit Availability Pactor 36 3 61.1 61.1

16. Unit Capacity Factor (Using MDC) 18.9 53 9 53 9

17. Unit Capacity Factor (Using Design MWe) 18.6 53.0 53 0

18. Unit Fbeced Outage Rate 2.2 10.8 10.8

19. Shutdowns-Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A

20. If Shut Down at End of Report Period, Estimated Date of Startup: N/A

21. Units in Test Status (Prior to Ccanerical~ 0peration):

FORECAST ACHIEVED t-Initial Criticality N/A 10-22-82 Initial Electricity N/A 11-16-82 4

Connercial Operation N/A 01-01,

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Director,-Office of Resource-Management D:cember Monthly Operating ~ Report-Page'3 January 14, 1985-

. ATTACHMENT III' UNIT SHUTDOWNS AND. POWER REDUCTIONS

-DOCKET NO.

50/395 UNIT V.

C.~ SUMMER I-DATE 01/11/65 COMPLETED BY G.

A.

Loignon

-TELEPHONE (803) 345-5209 (1)

METHOD OF (2)

L TYPE-SHUTTING-DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE ACTIONS /-

NO.

DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER COMMENTS 11.

840928 S

467 5 C

4

11) Refueling, Testing "B" Reactor Coolant ~

Pump Breaker.

12 841220 S

0.3 B.

1

12) Turbine'Overspeed Test.

13 841227 F

6.1 G

3

13) Reactor Trip Caused By Improper Connection-Of Test

. Instrumentation.

f a

t r

' Director, Of fice-of Resource Management

~

- December Monthly Operating Report Page.4 January 14, 1985 i

i

. ATTACHMENT IV NARRATIVE

SUMMARY

.OF OPERATING EXPERIENCE The Virgil C.

Summer Nuclear Station, Unit No.1, remained shut down for refueling at the beginning of December, 1984.

On December 4, 1984, at 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br />, with the Plant in Mode 5,-the Residual Heat Removal-System Letdown. Flow Control Valve. failed.

closed as a result of the loss of.its associated 120V.AC power source.

Residual Heat Removal (RHR) suction relief valves opened at least twice.

Pressurizer Power Operated Relief Valves (PORV)-

were manually opened to maintain 'the system depressurized.

Letdown was restored in approximately twenty minutes, i

On December 15, 1984,.at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, with the Plant in Mode 3, Pressurizer Spray Valve PCV-444D failed open when placed in automatic and would not close in manual control. -Reactor coolant pumps " A" and " C" were secured.

Air to PCV-444D was secured and the valve was closed.- Lowest system pressure was approximately 1985 psig.

As pressure increased the rate sensitive PORV PCV-444B opened momentarily at 2245 psig.

Alternate spray was used to control pressure and " A" a nd " C" reactor coolant pumps were restarted.

On December 18, 1984, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, the reactor was taken critical to begin Core Cycle 2 low power physics testing.

On December 19, 1984, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, the Plant was placed in Mode 3 for reactor coolant pump breaker testing.

At 1736 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.60548e-4 months <br />, a 120V AC inverter failed resulting in loss of its associated 120V AC Instrument Bus.

This resulted in an actuation of the Solid State Protection System due to loss of power - to the affected Nuclear Instrumentation Channels.

Power was returned to the panel at 1750 4

hours on December 19, 1984.

i Subsequent to the Refueling Outage on December 20, 1984, at 1723 hours0.0199 days <br />0.479 hours <br />0.00285 weeks <br />6.556015e-4 months <br />, the generator was. synchronized to the grid.

On December 25, 1984, at 0648 hours0.0075 days <br />0.18 hours <br />0.00107 weeks <br />2.46564e-4 months <br />, with the unit at 75% power the

" A" ' Condensate Pump tripped.

Power was' reduced to below 50% and i

"C" Condensate Pump was used to control the transient.

i On December 27, 1984, at 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br /> and 75% power, an error in i

installing test equipment caused the feedwater regulating valves to close.

A steam generator low level signal coincident with a

[

steam / feed mismatch caused the reactor to trip.

On December 31,-.1984, the-Plant was' operating at 75% power.

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i..

OFFSITE DOSE CALCULATION MANUAL

SUMMARY

OF CHANGES REVISION 7 Title, Pages 1, ii, and.iii:

Clerical changes to reflect thi.s revision and increased distribution of the'Offsite Dose Calculation Manual (ODCM).

Pages~1.0-13:

This change allows greater operational freedom without affecting.the manner in which setpoints are determined nor in the way dose is calculated. 131e ODCM is no less conservative'in any of-its calculations or in its ability to support such releases.

The absolute approbation was previously included-because of the potential for large. calculated doses if no dilution is available (see equation 31, Page 1.0-28).

Pages 1.0-28, 1.0-34, and 2.0-11:

Change corrects typographical errors.

t i

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