ML20147E199
| ML20147E199 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1987 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8803040324 | |
| Download: ML20147E199 (12) | |
Text
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O 1987 ANNUAL OPERATING REPORT l
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VIRGIL C. SUMMER NUCLEAR STATION l
1 5803040324 871231
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PDR ADOCK 05000395 f.
R DCD
PREFACE 1
The 1987 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 HPF-12.
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TABLE OF CONTENTS
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SECTION TITLE PAGE 1.0 Introduction 1
2.0 Highlights 1
3.0' Scheduled or Forced Power Reduction Sumaries 1
4.0-Exposures 5
5.0 Failed Fuel 5
ATTACHMENTS I.
1987 Man-Rem Report h
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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 885 MWe net (approximately 900 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 31,1987 the plant operated at a capacity factor of 66.5% and a unit availability of 70.1%.
The reactor was critical for a total of 6.222.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the generator remained on-line for a total of 6,136.9 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 1987 was 5,419,990 MWh.
3.0 SCHEDULED OR FORCED POWER REDUCTION SUMMARIES During the 1987 report period the plant experienced one scheduled and seven forced power reductions of greater than 20% which exceeded four hours in duration. The plant experienced five reactor trips.
A.
On January 3,1987, at 0532 hours0.00616 days <br />0.148 hours <br />8.796296e-4 weeks <br />2.02426e-4 months <br />, a forced power redti,t'on from 100% was initiated due to an oil reservoir level alarm on "C"
Reactor Coolant Pump.
Power was stabilized at approximately 15%
(0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />) while oil was added to the reservoir.
The plant was returned to 100% power at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on January 5, 1987.
The power reduction was approximately 57.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in duration.
B.
On March 5, 1987, at 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, the plant commenced a load reduction for entry into the third refueling outage.
The generator breaker was opened at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> on March 6, 1987.
Major activities scheduled for the outage were:
Sludge Lance and Upper Internal Inspection on Steam Generator "C" b.
U-Bend Stress Relief c.
Shot Peening d.
Plug Removal e.
Tube Plugging Sludge lancing and upper internal inspection of Steam Generator "C"
was completed on March 16, 1987.
The upper internals inspection revealed the presence of a light dust (5% blockage)
Page 1 of 5
with an oil film on the lower plate.
The oil residue was from a previously identified lube oil leak on a feedwater pump.
Approximately 24 pounds of sludge was removed following the sludge lancing.
The third inservice eddy current examination of steam generator tubing was performed between the dates of March 17 and April 26, 1987. The results of this inspection, contcined in the following table, were reported in a Special Report (SPR 87-005) dated May 11, 1987.
S/G A S/G B S/G C Total Number of Tubes Plugged Previously 40 199 56 Total Number of Tested Tubes 4634 4475 4618 Number of tubes plugged unnecessarily this 5
0 0
outage Number of plugs removed 0
24 0
Number of tubes plugged for stuck heaters 1
0 2
Number of tubes > 40% indications 102 173 102 Humber of tubes F* applied (including plug 31 73 31 removal tubes)
Number of tubes plugged this outage for ECT 71 118 71 indications i
Number of tubes repaired (i.e. sleeved) 0 0
0 Total Number of tubes now plugged 117 293 129 Total Number plugged - percent (%)
2.5%
6.27%
2.76%
On April 7, 1987, at approximately 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, the preliminary results of the eddy current examination concluded that Technical Specifications Section 3.4.5, "Steam Generators,"
sample l
inspection category C-3 applied, since more than 1% of the inspected tubes were defective.
The entry into this inspection category was reported in LER 87-006 per the requirements of 10CFR50.73(a)(2)(ii).
SCE&G has completed stress relieving of the U-bends of the unplugged row I and 2 tubes and shot peening i
of the tubes in the inlet side tubesheet area of each steam generator.
This corrective action is designed to reduce tensile stress in the steam generators at Virgil C.
Summer Nuclear Station and to reduce the rate of tube degradation.
On March 20, 1987, reactor vessel stud detr.nsioning commenced l
placing the plant in Mode 6.
All fuel issemblies had been l
removed from the reactor vessel by March 28, 1987, and by April 30, 1987 Cycle 4 fuel loading was complete.
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On March 31, 1987, SCE&G was notified by Wyle Laboratories that all three pressurizer safety valves had been tested and the as-found setpoints were outside the Technical Specification limits of 2485 1% psig but less than the safety limit of 2735 psig. On April 1,
1987, the deviation of the pressurizer safety valves setpoints outside the Technical Specification limits was reported per 10CFR50.72(b)(2)(1).
SCE&G considers the use of different testing methods to be the primary contributor to this situation.
These valves were last tested using the hot nitrogen method and setpoints verified for the second operating cycle in April 1984.
The 1987 test at Wyle involved the use of steam.
The correct setpoints were verified during startup when testing was conducted at hot plant conditions using a steam medium and a calibrated pressure assist device, together with a test method which best simulates actual plant conditions.
Complete details are contained in LER 87-005.
On May 12, 1987, a Service Water Screen Wash Pump failed to start during Engineered Safety Feature Loading Sequencer (ESFLS) testing.
Investigation attributed the failure to a defective lug crimp on the internal vendor wiring in the ESFLS panel.
The ESFLS provides sequenced loading of equipment (necessary for accident mitigation) to the Engineered Safety Feature buses.
As a result of wiring discrepancies noted during the investigation, the internal wiring for both ESFLS panels was reworked.
The potential failure of both ESFLS units due to defective lug crimps was reported in LER 87-010.
On May 26,1987, at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, a pressure boundary leak in the reactor coolant system forced the plant into a controlled shutdown and a declaration of a Notification of Unusual Event at 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br />.
On May 27,1987, at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />, cold shutdown (Mode
- 5) condition was established satisfying Technical Specifications.
The cause of this event was a crack originating at the root of the seal injection inlet nozzle weld in the "C"
RCP thermal barrier flange. The weld in the area of the crack was ground out and repaired by welding.
The other Reactor Coolant Pumps (A and B) were inspected in the area of the Thermal Barrier Seal Injection interface by dye penetrant exa11 nation.
These examinations showed no indication of cracks or leaks in this area.
Details of event are addressed in LER 87-013.
Initial criticality was achieved on June 6, 1987, at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />.
The main generator was placed on line at 1102 hours0.0128 days <br />0.306 hours <br />0.00182 weeks <br />4.19311e-4 months <br /> on June 9, 1987.
The refueling outage was approximately 1,666.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> in duration.
C.
On June 16, 1987, at 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br />, a reactor trip occurred from 100% power.
The failure of a capacitor in inverter XIT 5904 caused an output fuse to blow which resulted in the loss of Power Range Nuclear Instrument (HI) 44.
The loss of NI-44 caused the Steam Generator (SG) program level control signal to decrease from full load to no load (38%).
The Feedwater Regulating Valves (FWRVs) reduced flow to decrease actual level to meet the Page 3 of 5
programmed level. When the operator placed the FWRV controls to manual and demanded an open signal, the addition of cooler feedwater (in conjunction with the already lower level) caused "B"
Steam Generator level to shrink below the Low-Low Level Reactor Trip Setpoint.
An alternate inverter was aligned and the reactor taken critical at 1142 hours0.0132 days <br />0.317 hours <br />0.00189 weeks <br />4.34531e-4 months <br /> or. June 17, 1987.
The generator was back on line at 2127 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.093235e-4 months <br /> on June 17.
The forced outage was 25.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in duration.
D.
On July 24,1987, at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />, a forced power reduction from 100% was made to determine the cause of an oil level alarm on "A" Reactor Coolant Pump.
A reactor building entry was made to lower the oil level when the plant reached 22% power level at approximately 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> on July 25, 1987.
During the return to 100% power on July 26, high vibration on one main feedwater pump caused the power escalation to be halted at approximately 87%
power and a subsequent 12% reduction in power to be initiated.
The power reduction was approximately 45.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in duration.
E.
On September 2,
1987, at 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br />, while the plant was operating at 100% power the reactor tripped due to a turbine trip condition above the 50% power P-9 permissive.
A main generator stator ground resulted in an electrical fault which caused a main turbine trip.
A failed main generator bushing was the cause nf the generator stator ground condition.
The failed generator bushing was replaced.
The other generator bushings were inspected, and meggar readings revealed no abnormalities.
A leak in the stator water cooling system was identified as the most likely cause of the bushing failure.
After repair of the bushing, an air leak was discovered in the main condenser boot seal which required replacement in order to draw a condenser vacuum.
The reactor was taken critical on September 12, at 1552 hours0.018 days <br />0.431 hours <br />0.00257 weeks <br />5.90536e-4 months <br />, and the generator was back on line September 13 at 2131 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.108455e-4 months <br />.
The plant returned to 100 percent power at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, on September 15.
The forced outage of approximately 264.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in duration was reported in LER 87-021.
F.
On September 24, 1987, at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br />, the plant tripped from 100%
power.
A control rod drive system redundant power supply was being removed from service for repair.
When the neutral was disconnected, the redundant power supply also lost its neutral which caused 12 control rods to drop.
This resulted in a negative rate reactor trip.
The power supply was restored and the reactor was critical on September 25, 1987, at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />.
The generator was synchronized at 2356 hours0.0273 days <br />0.654 hours <br />0.0039 weeks <br />8.96458e-4 months <br /> on September 25 and the plant was back at 100% power at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />, on September 27.
The forced outage of approximately 25.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> in duration was reported in LER 87-024.
G.
On October 14, 1987, at 2102 hours0.0243 days <br />0.584 hours <br />0.00348 weeks <br />7.99811e-4 months <br />, a power reduction was initiated to 30 percent power to allow access for the performance of surveillance / rework of some Reactor Building Cooling Unit electrical connections.
LER 87-025 was submitted describing the identification of a kerite taped back to back "V" configuration Page 4 of 5
connection not previously tested for environmental qualification.
The plant was returned to 100% at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on October 17.
The forced power reduction was approximately 65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> in duration.
H.
On October 29, 1987, at 0313 hours0.00362 days <br />0.0869 hours <br />5.175265e-4 weeks <br />1.190965e-4 months <br /> with the plant at 100% power, both the primary and backup power supplies to one of the Westinghouse 7300 system process rack panels failed.
This resulted in a loss of various instrumentation and control functions including feedwater controls, pressurizer pressure and level controls, and steam dump controls.
Manual control of the feedwater system was attempted, but due to the nature of the control failures, recovery was not possible.
The plant tripped on low steam generator "C" level coincident with steam flow / feed flow mismatch.
The cause of the event was attributed to a failed capacitor on a steam dump control signal converter card in one of the process rack panels.
This capacitor shorted to ground causing the breakers to both the primary and backup power supplies for the process rack panel to trip.
On October 30,1987, at 0903 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.435915e-4 months <br /> prior to startup (the reactor still subcritical, control rod shutdown banks withdrawn), a power loss to a source range cabinet occurred as a result of a blown fuse.
The shutdown banks inserted when the associated bistable was actuated by the power loss.
This loss of power occurred when the wrong type of light bulb was inserted in both the instrument and control power status indicating lights in one of the source range drawers in the Control Room.
The incorrect light bulbs caused both the instrument and control power fuses to blow when the light bulb holder assembly was reinserted.
Subsequent to making the necessary repairs, the main generator was synchronized at 1658 hours0.0192 days <br />0.461 hours <br />0.00274 weeks <br />6.30869e-4 months <br /> on October 30.
The forced outage was approximately 37.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in duration.
Event details are addressed in LER 87-027 and LER 87-028.
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 FAILE0 FUEL The Virgil C. Summer Nuclear Station has had no significant indication of failed fuel. The specific activity of the primary coolant remained within the limits of Technical Specification 3.4.8, "Specific l
l Activity."
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ATTACHMENT I Pags 1 of 3 l
l SOUTH CAROLINA ELECTRIC & GAS COMPANY V. C. SUMMER NUCLEAR STATION 1987 MAN REM REPORT N'JM8ER OF PERSONNEL >0 MREM TOTAL MAN-REM s
WORK & JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT Reactor Operations & Surveillance Maintenance Personnel 90 0
93 3 046 0.000 2 862 Operating Personnel 75 1
58 8 136 005 1.458 Health Phys;cs Personnel 22 2
118 2.470 270 14 875 Supervisory Personnel 9
3 9
250 080
.101 Engineering Personnel 13 23 25
.515
.709 449 Routine Maintenance Maintenance Personnel 165 2
382 9 269 085 27.146 Operating Personnel 7
0 0
.135 0 000 0 000 Health Physics Personnel 10 2
74 865 020 2 792 Supervisory Personnel 3
0 3
.045 0 000 009 11 27 22
.302 848 1 062 _
Engineering Personnel inservice inspection Maintenance Personnel 48 1
89 4 645 070 6 045 Operating Personnel 19 0
0 492 0 000 0 000 Health Physics Personnel 4
0 63 095 0 000 3 675 Supervisory Personnel 1
0 1
040 0 000 005 Engineering Personnel 5
13 35
.435 2 601 3 795 Special Maintenance Maintenance Personnel 160 1
442 42.566 025 298 843 Operating Personnel 47 0
1 2 660 0 000 025 Health Physics Personnel 11 3
99 1.369 718 55 080 i
Supervisory Personnel 5
2 2
332 055 011 Engineering Personnel 11 22 33 1 820 5.764 8 582 Waste Processing Maintenance Personnel 49 0
56 3 220 0 000 4 605 Operating Personnel 4
0 t
074 0 000 384 Health Phys:cs Personnel 11 1
52 1.300 040 5.183 Supervisory Personnel 0
0 0
0 000 0 000 0 000 Engineering Personnel 1
9 1
040
.172 035 Refueling Maintenance Personnel 49 1
101 10 915 080 23 663 Operating personnel 12 0
0 502 0 000 0 000
~^
Health Physics Personnel 4
0 53 301 0 000 3.385 Supervisory Personnel 2
0 0
350 0 000 0 000 E ngineering Personnel 2
8 26 036 1 315 2 475 TOTAL 5 Maintenance Personnel 561 5
1163 73 661 260 363 165 Operating Personnel 164 1
62 11 999 005 1 867 Health Phys:cs Personnel 62 8
459 6 400 1 048 84 990 Supervisory Personnel 20 5
15 1017 135 126 E ngineering Personnel 43 102 142 3 148 11 409 16 398 G R ANO TOTAL 650 121 1841 96 225 12 857 466 546
ATTACHMENT I Pagt 2 of 3 SOUTH CAROLINA ELECTRIC & GAS COMPANY V. C. 5UMM ER NUCLEAR STATION 1987 MAN. REM REPORT NUM8ER OF PERSONNEL >100 MREM TOTAL MAN-RE M WORK & JO8 FUNCTION STATION UTILITY CON'RACT STATION UTILITY CONTRACT Reactor Operations & Surveil!ance Maintenance Personnel 6
0 6
.925 0.000 1.207 Operating Personnel 34 0
2 6.788 0 000
.435 Health Physics Personnel 8
1 55 2.105 250 12.432 Supervisory Personnel 0
0 0
0 000 0 000 0 000 E ngineering Personnel 2
0 0
335 0 000 0 000 Routine Maintenance Maintenance Personnel 24 0
73 3 912 0 000 17 623 Operating Personnel 0
0 0
0 000 0 000 0 000 Health Physics Personnel 2
0 2
625 0 000 284 Supervisory Personnel 0
0 0
0 000 0 000 0 000 Engineering Personnel 1
2 2
.105 279 495 Inservice Inspection Ma'ntenance Personnel 13 0
19 3.580 0.000 4 324 Operatmg Personnel 0
0 0
0 000 0 000 0 000 Health Phys cs Personnel 0
0 11 0 000 0 000 1 863 Supervisory Personnel 0
0 0
0 000 0 000 0 000 Engineering Personnel 1
6 12 355 2 430 2 920 Special Maintena nce Maintenance Personnel 90 0
317 39.760 0 000 293 099 Operating Personnel 8
0 0
1.459 0 000 0 000 Health Phys 4cs Personnel 7
1 71 1.221 688 53 936 Supervisorypersonnel 1
0 0
.120 0 000 0 000 l
Engineering Personnel 4
16 17 1.713 5 606 8 040 Waste Processing Maintenance Personnel 7
0 11 2 215 0 000 3 170 1
Operating Personnel 0
0 1
0.000 0 000 375 Health Phys,cs Personnel 2
0 10 890 0 000 3 965 Supervisory Personnel 0
0 0
0 000 0.000 0 000 E ngineerirq Personnel 0
0 0
0 000 0 000 0 000 Re f ueling Maintenance Personnel 25 0
58 9 930 0 000 22 145 Operating Personnel 2
0 0
269 0 000 0 000 Health Physics Personnel 1
0 9
181 0 000 1 745 Superv sory Personnel 1
0 0
325 0 000 0 000 Engineering Personnel 0
5 9
0 000 1 295 1 830 TOTALS Maintenance Personnel 165 0
484 60 322 0 000 341 568 Operating Personnel 44 0
3 8 516 0 000 310 Health Physics Personnel 20 2
158 5 022 938 74 225 l
Su perv,sorypersonnel 2
0 0
445 0 000 0 000 l
Engsneering Personnel 8
29 40 2 508 9 610 13 285 l
GRAND TOTAL 239 31 685 76 813 10 548 429 838 1
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ATTACHMENT I Pago 3 of 3 SOUTH CAROLINA ELECTRIC & GAS COMPAMV V. C. SUMMER NUCLEAR STATION 1987 MAN-REM REPORT NUMBER OF PERSONNEL <100 MREM TOTAL MAN-REM WORK & JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT Reactor Operations & Surveillance Maintenance Personnel 84 0
87 2.121 0 000 1.655 Operating Personnel 41 1
56 1.348 005 1.023 Health Physics Personnel 14 1
63
.365 020 2.443 Supervisory Personnel 9
3 9
250
.080
.101 Engineering Personnel 11 23 25
.180
.709 449 Routine Maintenance Maintenance Personnel 141 2
309 5 357 085 9 523 Operating Personnel 7
0 0
.135 0.000 0 000 Health Physics Personnel 8
2 72 240 020 2.508 Svoervisory Personnel 3
0 3
045 0 000 009 Engineering Personnel 10 25 20
.197 569
.567 Inservice Inspection Maintenance Personnel 35 1
70 1 065 070 1.721 Operating Personnel 19 0
0
.492 0 000 0 000 Health Physics Personnel 4
0 52 095 0 000 1.812 Supervisory Personnel 1
0 1
.040 0 000
.005 Engineering Personnel 4
7 23 080 171 875 Special Maintenance Maintenance Personnel 70 1
125 2 806 025 5 744 l
Operating Personnel 39 0
1 1.201 0 000
.025 Health Physics Personnel 4
2 28
.148
.030 1.144 Supervisory Personnel 4
2 2
.212
.055 011 Engineering Personnel 7
6 16
.107
.158
.542 Waste Processing Maintenance Personnel 42 0
45 1 005 0 000 1.435 Operating Personnel 4
0 2
.074 0 000 009 Health Physics Personnel 9
1 42 410 040 1 218 l
Supervisory personnel 0
0 0
0 000 0 000 0 000 Engrneering Personnel 1
9 1
040
.172 C35 Refuebnq Maintenance Personnel 24 1
43
.985 080 1 518 Operating Personnel 10 0
0 233 0 000 0 000 Health Physics Personnel 3
0 44 120 0 000 1 640 Supervisory Personnel 1
0 0
025 0 000 0 000 Engineering Personnel 2
3 17 036 020 645 TOTALS Mainterpce Personnel 396 5
679 13.339 260 21 596 120 1
59 3 483 005 1 057 Operating Personnel Health Physics Personnel 42 6
301 1 378 110 10 765 Suoervrsory Personnel 18 5
15 572 135 126 l
Engmeering Personnel 35 73 102 640 1 793 3 111 GRAND TOTAL 611 70 1156 19 412 2 309 36 657 i
,.,~.
th rouna Electric & Gas Company Dan umn Columbia. SC 29218 Nuclear Operations e'SCE&G February 29, 1988 Dr. J. Nelson Grace Regional Administrator U. S. Nuclear Reguletory 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 1987 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, 6.9.1.5, and Regulatory Guide 1.16.
If there are any questions, please call us at your convenience.
y tru y your,
'l D. A, N man CJM/ DAN:jz Attachment c:
'J.
G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts
- 0. S. Bradham W. A. Williams, Jr.
General Managers L. A. Blue W. R. Baehr C. A. Price R. B. Clary W. R. Higgins J. R. Proper R. M. Campbell, Jr.
K. E. Nodland J. C. Snelson G. O. Percival R. L. Prevatte J. B. Knotts, Jr.
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