RC-97-0101, Monthly Operating Rept for Apr 1997 for VC Summer Nuclear Station Unit 1

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Monthly Operating Rept for Apr 1997 for VC Summer Nuclear Station Unit 1
ML20141F165
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/30/1997
From: Bell W, Gabe Taylor
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RC-97-0101, RC-97-101, NUDOCS 9705210229
Download: ML20141F165 (5)


Text

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  • Ca olina Electric & @as Company J.
  • f Jenkinsvme.Sc 29065 NLdear Operations l

-c (803) 345 4344 SCFJiG anamacem ,

! I May 15,1997  !

RC-97-0101 l Document Control Desk i U. S. Nuclear Regulatory Commission Washington, DC 20555 1

Attention: Director, Office of Resource Management 1-Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION -

., DOCKET NO. 50/395  :

OPERATING LICENSE NO. NPF-12 APRIL MONTHLY OPERATING REPORT Enclosed is the April 1997 Monthly Operating Report for the Virgil C. Summer .

Nuclear Station Unit No.1. This submittalis made in accordance with the l requirements of Technical Specifications, Section 6.9.1.10.

If there are any questions, please call me at your convenience.

Very truly yours, GIV/ j Gah Tayi y'- j tid i

Attachment

\

c: W. F. Conway B. Lewis l R. R. Mahan (w/o attachment) INPO Records Center R. J. White Marsh & McLennan L.A.Reyes- William G. Wendland (ANI)

A. R. Johnson Pat Haught (Westinghouse) l S. A. Byrne RTS (MON 2000)

R. M. Fowlkes File (818.03-1) i NRC Resident inspector DMS l J. B. Knotts Jr.  !

K. R. Jackson 9705210229 970436

,,,a ggll'l*ll%ll PDR ADOCK 05000395 R PDR NUCLEAR' EXCELLENCE - A SUl@iER TRADITION! l

. ...,f Director, Office of Resource Management

. April Monthly Operating Report ,

Page 1

. ATTACHMENT I .i AVERAGE DAILY UNIT POWER LEVEL 1

DOCKET NO. 50/395

- UNIT V. C. SUMMER I ,

  • DATE 5/ 8/97-COMPLETED BY W. H. BELL l TELEPHONE (803) 345-4389 APRIL 1997  ;

4 DAY AVERAGE DAILY POWER-LEVEL DAY AVERAGE DAILY' POWER LEVEL (MWe-Net) (MWe-Net) 902 I

1. 955 17.
2. 955 18. 954
3. 955 19. 955
4. 955 20. 955
5. 953 21. 955
6. 954 22. 654
7. 955 23. 0 l
8. 954 24. 0
9. 955 25. 21

< 10. .954 26. 146

.11. 955 27. 0

12. 956 28. 1
13. 9117 29. 370 14.. 955 30. .702
15. 95N-l
16. . 955 1

4

7

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l Director, Office of Resource Management

April Monthly Operating Report

. P;ge 2-ATTACHMENT II OPERATING DATA REPORT DOCKET NO. 50/395.

" UNIT. V. C. SUMMER I DATE 5/ 8/97 COMPLETED BY W. H. BELL TELEPHONE (803) 345-4389 OPERATING STATUS o 1. Reporting Period:= . April 1997

) Gross.Hourts in Reporting Period: 719 iL 2. ' Currently Authorized Power Level (MWt): 2900 Max, 04 pend. Capacity (MWe-Net): 945

' Design Electrical Rating (MWe-Net):

~

954 j' 3. Power Level to Which Restricted (If Any)(MWe-Net):- N/A 7 4. Reasons for Restrictions:. N/A CUMULATIVE THIS MONTH YR TO DATE 4
5. Namber of Hrsurs Reactor Critical 615.4 2775.4 95847.0
6. Reactor Rer.erve Shutdown Hours 0.0 0.0 0.0 7 Hours Generator on Line 587.6 2747.6 94359.7
d. Unit Reserve Shutdown Hours 0.0 0.0 0.0
9. Gross Thermal Energy Generated (MWH) 1609409 7856820 248560339

. 10. Gross Electrical Energy (MWH) 546840 2687360 82843009

-11. Net Electrical Energy Generated (MWH) 524420 2582684 78904396

> 12. Reactor Service Factor 85.6 96.4 82.0 13.~ Reactor Availability Factor 85.6 96.4 82.0

14. Unit Service Factor ~ 81.7 95.4 1B0.7
15. Unit Availability Factor 81.7 95.4 80.7

- 16. Unit Capacity Factor (Usir- '.'7C) 77.2 94.9 75.9

. 17. Unit Capacity Factor (Design :(We) 76.5 94.0 75.9

18. Unit Forced Outage Rate '18.3 4.6 4.2
19. Shutdowns. Scheduled Over Next 6 Months (Type, Date & Duration of Each):

REFUELING, OCTOBER 4,1997, 35 DAYS 20..If: Shut Down at End of Report Period, Estimated Date of Startup: N/A

21. Units in Test Status (Prior to Commercial Operation): N/A

b Director, Office of Resource Management .

April Monthly Operating Report' j

-Page 3 j I

J ATTACHMENT III UNIT SHUTDOWNS AND POWER REDUCTIONS 1

DOCKET NO. 50/395' ,.

UNIT .V. C. SUIDEER I l DATE 5/ 8/97 COMPLETED BY W. H. BELL i

! TELEPHONE (803)'345-4389 APRIL 1997 i

NO. .DATE TYPE DURATION REASON METHOD CORRECTIVE ACTION /ColetENTS l

,1 970422 F 73.8 A 2 REPAIRED EHC CONTROL VALVE

'2 970425 F 6.6 A 1 REPAIRED EHC CONTROL VALVE 3 970426 F 51.0 'G 3 TRAINING ENHANCEMENTS R

I 1.0 . REASON A: Equipment Failure B:-~ Maintenance-or Test C: Refueling 4

D: Regulatory Restriction E: Operator Training and License Examination F: Administrative G: Operational Error H: Other (Explain) l l

2.0 METHOD J I

1:. Manual 2: Manual Scram 3: Automatic Scram 4:. Continuation ~.-(Use initial Date)

~ '5: . Power Reduction (Duration O.0)

9. Other (Explain)'

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  • Director, Office of Resource Management April Monthly Operating Report Page 4 A'ITACHMENTIV NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO. 50/395 UNIT V. C. SUMMER I -l

~DATE 5/5/97 COMPLETED BY W. H. BELL  !

TELEPHONE (803) 345-4389 i

APRIL 1997 i

)

During the month of April, the plant operated with a Capacity Factor of '77.2 percent and Availability Factor of 81.7 percent.

On 4/17/97, power was reduced to 90% in order to perform repairs to the second stage reheat and control valve interlock pressure switch IPS 05635. l i

On 4/22/97, at 16:54, the reactor was manually tripped as a conservative measure due to a large l EHC System leak.  ;

On 4/25/97, the reactor went critical at 14:48. The main generator breaker was closed at 18:39 but opened again at 21:12 to repair an additional small EHC System leak. To facilitate the repair, the turbine was manually tripped at 21:14 while maintaining reactor power at 7%. i On 4/26/97, following repairs, the main generator breaker was closed at 03:50. While escalatmg j reactor power, a feedwater system flow transient caused a turbine trip on hi-hi steam generator  ;

level at 20:43 followed by a reactor trip at 20:47 due to 1o-10 steam generator level. l l

On 4/28/97, the reactor went critical at 05:28. The main generator breaker was closed at 23:40  ;

on 4/28/97 At approximately 11:00 on 5/1/97,100% power was reached.  !

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