ML20212E280

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1986 Annual Operating Rept for South Caralina Electric & Gas
ML20212E280
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 12/31/1986
From: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8703040313
Download: ML20212E280 (13)


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PREFACE The 1986 Annual Operating Report for the Virgil C. Summer Nuclear Station is hereby submitted in accordance with Technical Specifications 6.9.1.4,

!. 6.9.1.5, and Regulatory Guide 1.16 under Docket Number 50/395 and Facility Operating License NPF-12.

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TABLE OF CONTENTS SECTION TITLE PAGE

'1.0 Introduction 1 2.0 Highlights 1 3.0 Scheduled or Forced Power Reduction Summaries 1 4.0 Exposures 7 5.0 Failed fuel 7 ATTACHMENTS I. 1986 Man-Rem Report I .

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1.0 INTRODUCTION

The Virgil C. Summer Nuclear Station utilizes a pressurized water reactor rated at 2775 MWt. The turbine generator is capable of producing approximately 900 MWe net (approximately 936 MWe gross) of electrical power.- The plant is located approximately 26 miles

-northwest of Columbia, South Carolina.

2.0 HIGHLIGHTS For the reporting period of January 1 through December 31, 1986 the plant operated at an average capacity factor of 92.4% and a unit availability of 95.3%. The reactor was critical for a total of 8453.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the generator remained on-line for a total of 8350.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />, and  ;

the total gross electrical energy generated for 1986 was 7,478,800 MWh.

This data demonstrates a positive increase in plant performance from the 1985 report.

3.0 SCHEDULED OR FORCED POWER REDUCTION SUMUtIES

- During the 1986 report period the plarit experienced three scheduled and two forced power reductions of greater than 20% which exceeded four hours in duration. The plant experienced six reactor trips and one safety injection.

A. February 2, 1986, 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br /> - REACTOR TRIP FROM 100% POWER CAUSE - Feedwater Pump Trip DISCUSSION - Maintenance submitted a work package and requested a tag out on the condensate polisher panel. A review of the electrical feeder list and the associated drawings was done; however, both the list and drawings were incorrect. When the panel l was deenergized for the tag out, it caused a condenser polisher by-j pass valve to fail close. This isolated the flow of condensate to the deaerator tank. On low deaerator level the feedwater pumps tripped, which caused a Reactor Trip.

CORRECTIVE ACTION - Corrections to the electrical feeder list and drawing were made.

TIME LOST - See next item.

REACTOR DATE TIME TURBINE DA(E TIME TRIP 02/02/86 2005 TRIP 02/02/86 2005 CRITICAL 02/03/86 0324 TIED TO GRID SEE NEXT ITEM TOTAL TIME NOT TOTAL TIME OFF 07 hrs 19 min SEE NEXT ITEM CRITICAL THE GRID l

PAGE 1 0F 7

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B. February 3, 1986; 0741 hours0.00858 days <br />0.206 hours <br />0.00123 weeks <br />2.819505e-4 months <br /> - REACTOR TRIP / SAFETY' INJECTION FROM' 100% POWER f

CAUSE - Low Steamline Pressure DISCUSSION _- During restart from the previous trip, a Reactor Trip

/ Safety Injection occurred while rolling the main turbine. At approximately 400 RPM, the turbine control system expertenced a malfunction which caused a rapid increase in turbine speed. This sudden increase in speed caused a steam flow increase of approximately 50% of full steam flow and a rapid loss of header pressure. Although the header pressure never reached the low setpoint, the rate of pressure decrease was sufficient to actuate the steamline low pressure protection bistables due to rate compensation.

CORRECTIVE ACTT,0_M - During neither the troubleshooting activities nor the subsequent restart were any problems found with the turbine control system. However, a program of increased system monitoring during subsequent plant start-ups was placed ir,to effect.

TIME LOST - Generator was off line 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> and 5 minutes.

REACTOR. DATE TIME TURBINE DATE TIME TRIP 02/03/86 0741 TRIP SEE PREVIOUS ITEM

!' CRITICAL 02/04/86 1940 TIED TO GRID 02/05/86 0510 TOTAL TIME NOT TOTAL TIME OFF 36 hrs 59 min 57 hrs 05 min CRITICAL THE GRID l

l L C. April 2, 1986, 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br /> - REACTOR TRIP FROM 100% POWER l CAUSE - Turbine Trip DISCUSSION - Worn Alterex brushes caused a loss of excitation to the geterator. This resulted in a turbine trip and reactor trip.

CORRECTIVE ACTION - The Alterex brushes were replaced and an additional brush was added to increase time between changes. In addition, weekly preventive maintenance and a daily inspection of the brushes were added to normal scheduled maintenance.

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TIME LOST - Generator was off line 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 39 minutes.

REACTOR DATE -TIME TURBINE DATE TIME TRIP 04/02/86 1155 TRIP 04/02/86 1155 CRITICAL 04/03/86 0048 TIED TO GRID 04/03/86 0434 TOTAL TIME NOT TOTAL TIME OFF 12 hrs 53 min 16 hrs 39 min CRITICAL THE GRID D. May 31, 1986, 1026 hours0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.90393e-4 months <br /> - REACTOR TRIP FROM 100% POWER CAUSE - OTAT Trip Sigi.al.

DISCUSSION - Maintenance personnel were performing a monthly operational test on one of the four nuclear instrumentation power range channels. A second channel was_ inadvertently placed into test, which resulted in an OTAT Reactor Trip. Safety system responses were normal; however, water hammer during the transient caused some condenser damage.

CORRECTIVE ACTION - Five corrective actions resulted from this trip: ,

1. The involved maintenance personnel were counseled on the need for attention to detail.
2. The maintenance personnel responsible for the trip presented

" Lessons Learned" training to the applicable groups.

3. The nuclear instrumentation drawers will be re-labeled during 1987 to make them more easily identified.
4. The nuclear instrumentation procedures were reviewed from a Human Factors standpoint.
5. The condenser was repaired.

TIME LOST - Generator was off line 136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> and 20 minutes.

REACTOR DATE TIME TURBINE DATE TIME TRIP 05/31/86 1026 TRIP 05/31/86 1026 CRITICAL 06/05/86 0434 TIED TO GRID 06/06/86 0446 TOTAL TIME NOT 114 hrs TOTAL TIME OFF 136 hrs CRITICAL 08 min THE GRID 20 min PAGE 3 0F 7

E. June 29, 1966, 0215-hours - REACTOR TRIP FROM 90% POWER CAUSE - Low Feedwater Flow DISCUSSION - Reactor Power.had been reduced to 90% for turbine valve testing. The trip was the result of a feedwater isolation valve failing closed. The cause was determined to be oxidation on one of the electrical connectors which powered a solenoid on the valve actuator.

CORRECTIVE ACTION - Three specific actions resulted from this trip:

1. The faulty equipment was replaced.
2. Preventive maintenance inspection of these and similar connectors has been scheduled on a refueling basis.
3. A verification of correct field installation of the connectors was made.

TIME LOST - Generator was off line 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> 5 minutes.

REACTOR DATE TIME TURBINE DATE TIME TRIP 06/29/86 0215 TRIP 06/29/86 0215 CRITICAL 07/01/86 0315 TIED TO GRID 07/01/86 1420 TOTAL TIME NOT TOTAL TIME OFF 49 hrs 00 min 60 hrs 05 min CRITICAL THE GRID F. July 27, 1986, 0144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> - REACTOR TRIP FROM 90% POWER E CAUSE - Turbine Trip l

l DISCUSSION - Testing was in progress on turbine control valve #4 l when the reactor tripped. Testing of the #4 valve accounted for i one of the three EHC oil pressure switches being in a tripped state. It was believed that one of the other two switches operated

! spuriously due to vibration induced from the f4 valve going closed.

l This would have accounted for the 2 of 3 logic needed for the trip.

NOTE: See issue H. for September 19, 1986.

CORRECTIVE ACTION - Relocation of the control valve pressure switches has been considered for long term corrective action. In i the interim reactor power was reduced below the Reactor l Trip / Turbine Trip Setpoint (50% Reactor Power) for turbine control valve testing. This power reduction would allow the reactor to remain critical should a turbine trip occur.

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TIME LOST - Generator was off line 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> and 10 minutes.

REACTOR DATE TIME TURBINE DATE TIME TRIP 07/27/86 0144 TRIP 07/27/86 0144 CRITICAL 07/27/86 1135 TIED TO GRID 07/27/86 2034 TOTAL TIME NOT TOTAL TIME OFF CRITICAL 10 hrs 09 min 19 hrs 10 min THE GRID G. August 23, 1986, 0335 hours0.00388 days <br />0.0931 hours <br />5.539021e-4 weeks <br />1.274675e-4 months <br /> - POWER REDUCTION TO 46% POWER CAUSE - Turbine control valve testing.

DISCUSSION - Reactor power was reduced to 46% for control valve testing. Upon completion of testing, reactor power was returned to 100%.

CORRECTIVE ACTION - None TIME LOST - N/A H. September 19, 1986, 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> - POWER REDUCTION TO 46% POWER CAUSE - Turbine control valve testing.

DISCUSSION - Power was decreased for control valve testing. During the test, difficulties were again experienced with an EHC oil pressure switch. Reactor power was held at 46% until repairs on the faulty switch were completed.

CORRECTIVE ACTION - The faulty pressure switch was replaced. It is believed that this pressure switch was the cause of the July 27th trip.

TIME LOST - N/A I. October 7, 1986, 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br /> - FORCED OUTAGE TO 0% POWER CAUSE - The inability to verify that the amount of Reactor Coolant System (RCS) " unidentified" leakage was less than one GPM.

DISCUSSION - On October 7, 1986, at 0410 the licensee entered the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Technical Specification action statement for excess

" unidentified" RCS leakage. At 0530 a controlled shutdown at a rate of 1% per minute was initiated. By 0710 the main generator j had been removed from the grid and at 0810 a notification of unusual event was declared due to the excessive unidentified leakage. At 0935, the reactor was shutdown and repairs commenced on the RCDT relief valve which had failed to seat properly. At

! 1018 the unusual event was terminated after repair teams had '

temporarily repaired the RCDT relief valve, and subsequent accurate leak rate determinations could be accomplished.

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After final repairs were made the plant commenced start-up and at 1010 on October 9 achieved criticality. The generator was tied to the grid at 1520 the same day.

CORRECTIVE ACTION - Maintenance replaced the reactor coolant drain tank relief valve.

l TIME LOST - Generator was off line 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> 10 minutes.

REACTOR DATE TIME TUR8INE DATE TIME L TRIP 10/07/86 0935 TRIP 10/07/86 0710 CRITICAL 10/09/86 1010 TIED TO GRID 10/09/86 1520 TOTAL TIME NOT TOTAL TIME OFF 48 hrs 35 min 56 hrs 10 min CRITICAL THE GRID J. November 7, 1986 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> - POWER REDUCTION TO 2% POWER CAUSE - Feedwater valve packing leak.

DISCUSSION - On November 7, 1986, at 1100, reactor power was reduced due to a feedwater valve packing leak and at 0730 on November 8 the main generator was removed from the grid. Reactor power.was maintained at 2% so that repairs could be carried out.

Upon completion of repairs, power escalation commenced at 0943 on l November 9. Later that day at 1041, the main generator was tied to l

the grid.

l CORRECTIVE ACTION - Maintenance repacked the valve and replaced a faulty feedwater pump speed controller.

TIME LOST - Generator was off line 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> and 11 minutes.

REACTOR DATE TIME TURBINE DATE TIME TRIP N/A TRIP 11/08/86 0730 CRITICAL TIED TO GRID 11/09/86 1041 TOTAL TIME NOT TOTAL TIME OFF 27 hrs 11 min CRITICAL THE GRID l

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K. December 4, 1986, 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> - FORCED OUTAGE CAySE - Reactor Coolant Drain Tank Pump.

DISCUSSION - On December 4, 1986, at 1100, a controlled shutdown was initiated due to problems with a reactor coolant _ drain tank pump. The main generator was removed from the grid at 1325 and the reactor shutdown at 1345 the same day. Upon correction of the problem,:the plant returned to the grid on December'6 at 0100.

CORRECTIVE ACTION - Maintenance replaced one reactor coolant drain tank pump.

TIME LOST - Generator was off line 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> and 35 minutes.

REACTOR DATE TIME TURBINE DATE TIME TRIP 12/04/86 1345 TRIP 12/04/86 1325 CRITICAL ,12/05/86 1945 TIED TO GRID 12/06/86 0100 TOTAL TIME NOT TOTAL TIME OFF 30 hrs 00 min 35 hrs 35 min CRITICAL THE GRID 4.0 EXPOSURES Attachment I consists of tables which list the number of station, utility, and other personnel (including contract personnel) receiving exposures greater than and less than 100 Mrem / Year, and their associated man-rem exposure according to work and job functions.

5.0 FAILED FUEL The Virgil C. Summer Nuclear Station has had no indication of failed fuel.

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ATTACHMENT.I. l

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SOUTH CAROLINA ELECTRIC & CAS COMPANY V. C. SUMMER NUCLEAR STATION 1986 IIAN-REM REPR T l I NUMBER OF PERSONNEL )0 MREMI TOTAL MAN-REM I I I I I I Il0RK & JOS FUNCTION I STATION I UTILITY l CONTRACT I .STATION I UTILITY l CONTRACT I

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_l_ i.__..__ .l_____... .. l ____ _._ g ____ ,g

. i Reacter. Operations & Serveillancel i I I I I I

'l intenance Personnel 1 7 1 0 1 8 i .118 I 8.000 1 0.040 l

-Il~' alth P5ysics Personnel eratina Personnel I 53 1 1 1 30 'l 1.251 l .010 I .332 1 1 19 1 0 1 26 I .710 1 0.000 I i.927 I I Su erviser Personnel -l 3 1 3 1 1 1 .030 I .035 I .002 I I En ineerin Personnel 1 2' I 3 5 .030 I .021 I I Resti e Maint ance l 1 I .998 I I I I l l l l Maintenance Personnel 1 114 1 2 1 68 1 2.357 I .025 1 2.132 I I Operating Personnel I 6 I e I i I .129 1 0.000 I' .005 1 1 Health Pnysics Personnel i 11 l- 0 I 13 l- .248 1 0.000 I .257 I I Supervisory Personnel 1 3 1 3 I i I .015 I .030 1 .005 I.

I Engineering Personnel I 9 l 18 1 9 I .242 I .448 l .125 I I Inservice Inspection i I i 1 I I I-

'l Maintenance Personnel 1 2 i O I 3 I .325 1 0.000 I .920 1 1 Operatina Personnel 1 0 1 0 1 0 1 0.000 l O.008 i 8.00 1 1 nealth PApsics Personnel 1 0 1 0 1 3 1 0.000 1 0.000 1 .I I

- " Ii Su visory Personnel i 0 1 0 1 0 1 0.000 1 0.000 1 0.0 0 I i En insering Personnel I i I i 1 2 I .040 I .035 I .115 I I Speci 1 Maintenance 1 I I I I I L -

1 Maintenance Personnel I 83 1 0 I 43 1 2.270 1 0.000 1 2.099 1 1 .heratig Personnel i 11 1 0 1 3 I .224 1 0.000 I .01 1 I Ifealth Physics Personnel i il 1 0 1- 17 1 .426 1 0.080 I I i i Superviser Personnel I i I 8 1 0 I .005 1 0.000 1

8. 80 1

> 1 Engineerin Personnel l 3 1 13 1 1 1 .875 1 .255 I .01$ i i llaste Process n i I I I I I I T~ Maintenanc orsennel I 7 I I I .19 I .045 1 0.000 1 1. I I Operatina ersonnel 1 0 1 0 1 0 1 0.00t I c.1 Il 1 -c. I I Mealth Physics Personnel  ! 4 1 0 I it i .845 1 0 .1100 I . I I SuperviserP Personnel 1 0 1 I I I I 0.000 1 0.000 1 0.000 1 I Engineering Personnel 1 0 1 0 1 0 1 0.000 1 0.000 1 0.880 l I RefseLine 1 I I I I I I I Manntenance Personnel i I I I i 0 1 0.000 I t.000 1 0.000 I I Operatine Personnel 1 0 1 8 1 0 1 0.000 1 0.000 1 8.000 1 i Health Physics Personnel 1 0 I I 8 1 0.0 0.000 1 0.000 t i Personne i 8 i .I ' i 0 i 8.8.000i 1

.;,,,l.,ereisergneeridPersonnel I 8.000l 8.001 ;i 8.00l

0 0.00 8.00 li I

l ,i l l Maintenance Personnel i 213 2 133 5.115 I .025 l Operatino Personnel 1 1 1 6.166 1 1 I 70 l i I 34 1 1.604 I .til i .352 I i

I l(ealth P5psics Personnel I 44 1 0 1 69 l 1.429 1 0.000 1 3.184 I I Supervisory Personnel I 7 1 6 1 2 I .050 I .065 I .007 i

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Engineering Personnel I 15 l 35 1 17 I 387 I .759 I .353 I l CRAND TOTAL 1 349 i 44 1 255 1 8.585 I .859 l 10.062 1 e

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ATTACHME!TI' I PAGE 2 OF 3-SOUTH CAROLINA ELECTRIC & GAS COMPANY V. C. SUMMER WUCLEAR STATION 1986 MAN-REM REPORT l I NUMBER OF PERSONNEL (100 MREMI

~l TOTAL MAN-REM i i I I Ig WORK & JOB FU.NCTION ig.STATION I UTILITY l CONTRACT I STATION I UTILITY I CONTRACT I

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_i I Reacter Operations & Serveillancel i I I I I I I Maintenance Personnel I 7 1 0 1 I 118 1 0.000 1 Operatino Personnel 0 .

0.000 1 I -

1 52 I i I 30 l 1.135 I .til l .332 I I Mealth P5ysics Personnel i 19 1 0 1 18 1 . 710 1 0.000 I .535 I I Se ereisery Personnel 1 3 1 3 1 1 I . 030 I .035 1 .002 1

~~l En insering Personnel i 2 1 3 1 5 I . 030 I .021 I .998 I I Resti e Maintenance 1 I I I I I l l Maintenance Personnel 1 113 1 2 1 62 1 2.256 I .025 1 1.313 i

I erating Personnel I 6 I 8 1 1 I . 129 1 0.000 I .005 I I alth Physics Personnel 1 10 1 0 1 13 I . 140 1 0.000 I .257 l 1

i I upersisery Personnel 1 3 1 3 1 1 I . 015 I .030 I .005 I

-I Engineering Personnel I 9- l 17 1 9 I . 242 I .283 I .125 1 I Inseroite Inspection - 1 I I I I I l-1 Maintenance Personnel I i i O I 3 I .090 1 0.000 I .420 1

~I Oneratina Personnel 1 0 1 0 1- 0 l I.000 1 0.I00 1 0.000 l I Mealth Physics Personnel I I 1 8 1 3 1 0.000 1 8.100 I .425 I I Se eisery Personnel i I I I 1 I I O.000 1 0.000 1 0.000 1 l' En insering Personnel I i I i i 2 I . 048 i .835 I .115 l i Speci 1 Maintenance i I I I I I I l' Ma ntenance Personnel I 82 1 0 l 39 1 2.168 1 0.000 1 1.439 l-1 Op.oratina Personnel i 11 I I I 3 1 .224 I I.000 I .til i I Health Physics Personnel I 9 1 8 1 17 i . 291 1' O.Itt i .595 1 i Se eiser Personnel I i 1 0 1 I i . 005 1 0.000 I l.000 1 1 - En neerin Personnel 1 3 1 13 I i I . 075 I .255 I .015 I

~"- I Waste recess na i 1. I I I I I l~ M intenance Personnel I 7 1 0 1 13 I . 445 1 1.000 I .595 I

- I eratina Personnel 1 0 I I I I I 0.000 1 0.000 1 0.000 1 I alth P5psics Personnel I 4 I I I 9 I Se,ereiser' Per.nel i i i i i ..845 I .I.000i I ..190 I es,in,Personnei i.

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.....il .... ... j . . .. . ;i li ,m.intkanceM Personnet l . i . i i .... i .... . .... i i atin Personnei i i i i i i 0.. i .8. i .... i i Ith P is I 8 1 0 1 0 I 0.00 1 8.000 I e ereis 1 FerPersonnel i nei i i 1 i .900i 1 .. . i

! En ineerin Personnel I O I O I O I 0.000 1 0.00 1 0.800 i I TOTAL I I I I I I l I Maintenance Personnel i 219 I Operating Personnel l 2 1 117 I 4.669 I .625 1 3.367 i I 69 l 1 1 34 1 1.488 .010 i I Health Pnysics Personnel I 42 1 0 1 68 1 1.186 0.000 1 1.682 352I I I Supersisery Personnel I 7 I 6 1 2 I .050 I .065 I .007 1 1 ~ Engineering Personnel 1 15 I 34 1 17 I .387 I .594 I .353 1 1 .

3.. 3 ] _ l ._ g- l l I GRAllD TOTAL 1 343 1 43 1 230 1 7.780 I .694 1 5.681 1 4

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. ATTACHMENT-I

," PAGE 3 OF 3 SOUTH CAROLINA ELECTRIC & GAS COMPANY V. C. SUMMER NUCLEAR STATION 1996 MAN-REM .EPORT l I NUMBER OF PERSONNEL )i00 MREMI TOTAL MAN-REM i I. .

1 I 1

- 1 If0RK & J0. FUNCTION I STATION I UTILITY I CONTRACT STATION I UTILITY l CONTRACT I l _ _ __ . _. ___.___.g.... l _ __ l_.. .____l_ ___

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- I Keacter Operations & Servei11ancel I' I I I I i I  :"clm:m**  ! !lI  !  ! ,' ':!!! !  :!!2!

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Personnel 1 0  !. I 8. 1 0.000 I I.:.l!!  ! 1.3911 Su ervisory Personnel I I I l ..000 1 0 I

  • I I En ineering Persennel I Resti e Maintenance i 1 .

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I l . .0 00. l1 I

0.0.. l1 .... 00 II I Maintenance Personnel I i O I 6 .l .101 1 0.00 Il .

I h erating Personnel - I .i 1 0 I 1 .00 l- ..819 II l' Health Physics Personnel I i 1 0 1 0 1- 0.000.

.10 1 I 0.00 0. 00 1.

I Supervisory Personnel 1 0 1 0 i O I . 000 0.00 11 0.000 1

I Engineering Personnel I I i 1 0 1 0.000 l .165 1 0. 00 I I inservice Inspection i I I I I I I Maintenance Personnet 1 i 1 . l l . .. 0. I1- .. 0 I I Doeratina Personnel -

1 0 I I l ..235 00 I 0 . l .000 I I Ifealth PEysics Personnel I l . O. l 1 0.00 1 . 0.. 1 0.000 I i S. i i . i i .. .l .0 i .u i lS,efH,e,vaer,Personnet "m l I

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i lieste vis ines,1r.,,Personne Personnel i

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- 'i uten cI orsen-i "1ti't! i i  !  ! 'i i Enaeora,lorsennet, i .i. eroiser,st' i .i. ii . i 1. 111

're'!annet i 1 1.:.111 '..151 1.i !

-i ,Personnet i i . i ..n. n.i ...ii ..n.n i i Refoe ina l l I I I

I Maint4 nance Personnet atina Personnel I I l l l l

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I alth Physics Personnel I l 1 l l

. .. l I e visory Personnel l l .

I I TOTAL En insering Personnel 1

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..... II Maintenant Personnel I 3 1 . I 16 1 .446 i 2.799 i l

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Supervisory Personnel e sensel bI

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Engineering Personnel I i I 0j .165 I .... 1 I CRAN. TOTAL I 6 I i 1 25 - I .805 i .165 1 4.381 1 9

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- - . . -.-___.__J-__ ..,_.-_.l_-_,__.-__--_-_________._____

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, 10 CFR 50.36

,/*, South Candna Electric & Gas Company Den A.Nauman

/- $0umbIaTc 29218 Ec*ie%a$$tions (803) 748 4513 SCE&G

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February 27, 1987 Dr. J. Nelson Grace Regional Administrator U. S. Nuclear Regulatory Commission

-Region II, Suite 2900 101 Marietta Street, N.W.

Atlanta, Georgia 30323

SUBJECT:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Annual Report

Dear Dr. Grace:

Attached is the 1986 Annual Report for the South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Unit No. 1. This report is being submitted in accordance with Technical Specifications 6.9.1.4 and 6.9.1.5.

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

ery ui7)ours,

! N

'\

D. . man MGC: DAN /bjh Attachment cc: 0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts

0. S. Bradham J. G. Connelly, Jr.

D. R. Moore W. A. Williams, Jr.

Group Managers W. R. Baehr C. A. Price W. T. Frady C. L. Ligon (NSRC)

R. M. Campbell K. E. Nodland R. A. Stough G. O. Percival R. L. Prevatte J. B. Knotts, Jr.

I&E Washington NPCF File S6 rI i