ML20236C462

1988 Annual Operating Rept for VC Summer Nuclear Station

ML20236C462
Person / Time
Site:	Summer
Issue date:	12/31/1988
From:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Ernst M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8903220164
Download: ML20236C462 (9)

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1988 ANNUAL OPERATING REPORT l

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PREFACE The 1988 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

.- i 4.0 Exposures- 4 i

g 5.0 Failed fuel 4

ATTACHMENTS l i

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1. 1988 Man-Rem Report

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1.0 INTRODUCTION

The Virgil C. Summer Nuclear Station utilizes a pressurized water reactor rated at 2775 MWt. The unit produces a maximum dependable capacity of 885 MWe net 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, 1988 the plant operated at a capacity factor of 63.7% and a unit availability of 67.8%. The reactor was critical for a total of 6,067.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, the generator remained on-line for a total of 5,954.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and the total gross electrical energy generated for 1988 was 5,317,380 MWh.

3.0 SCHEDULE 0 OR FORCED POWER REOUCTION SUMMARIES i

During the 1988 report period, the plant experienced one scheduled and six forced power reductions of greater than 20% which exceeded four hours in duration. Included in these power reductions are four outages initiated by reactor trips.

1. On Feb m ry is. 1988 at 2331 hours0.027 days <br />0.648 hours <br />0.00385 weeks <br />8.869455e-4 months <br />, a reactor trip tccurred from 100% power. One excore power range nuclear instrument channel ,

had been removed from service due to a failed surveillance test.

As required by Technical Specifications, the remaining three l

channels were being read to verify that the Quadrant Power Tilt Ratio was within its limit. A loose terminal post connection on the meter test card on one of these channels caused a momentary loss of signal to that channel resulting in a negative rate reactor trip signal being initiated. The terminal posts were l verified to be mechanically tight and the plant was back on line i February 18 at 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br />. One hundred percent power was (

obtained at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on February 19. The forced outa5e was 1 43.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in duration and reported in LER 88-002.

2. On May 12, 1988 at 0446 hours0.00516 days <br />0.124 hours <br />7.374339e-4 weeks <br />1.69703e-4 months <br />, the plant tripped from 100% power and a Safety Injection (SI) occurred. The reactor trip /SI occurred during testing of the "A" Main Steam Isolation Valve (MSIV) when a defective test switch caused the valve to fully close instead of closing the required 10%. The closing of the valve caused a rapid decrease in steam flow on "A" steam header and an increase in steam flow and decrease in pressure on B and C steam headers. The rapid steam pressure decrease in the headers initiated the reactor trip /SI signals. The switch was replaced and criticality was established at 2104 hours0.0244 days <br />0.584 hours <br />0.00348 weeks <br />8.00572e-4 months <br /> on May 12. The

! generator was placed on line at 0105 hours0.00122 days <br />0.0292 hours <br />1.736111e-4 weeks <br />3.99525e-5 months <br /> on May 13 resulting in

! a forced outage of 20.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> in duration. The event was reported in LER 88-006.

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3. On May 27, 1988 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />,. power was reduced to approximately 40% to allow for repair of condenser tube leaks. The plant returned to 100% power at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on May 30 to conclude a forced power reduction lasting 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.

4. On May 30, 1988 at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />, power was again reduced to approximately 40% due to secondary water chemistry.being out of  ;

specification. The out of specification conditions were suspected to be the result of additional condenser tube leaks.

At 1004 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82022e-4 months <br /> on June 1, 1988, a reactor trip occurred during testing of the "B" train solid state protection system. As the "B" reactor trip breaker was closed using the switch on the main control board, a momentary interruption of the 48 volt undervo'Itage signal to the "A" train reactor trip breaker and the "B" train bypass reactor trip breaker initiated a reactor trip z (LER 88-007). During the outage the condenser tube leaks were l identified and repaired. I i

On June 10, 1988 at 0518 hours0.006 days <br />0.144 hours <br />8.564815e-4 weeks <br />1.97099e-4 months <br />, criticality was established. The generator was placed on line at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. The forced outage (breaker to breaker) was 228.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> in duration. The power reduction to 40% initiated on May 30 was an additional 45.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of forced reduced power operation.

l 5. On July 5 at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, power was temporarily reduced _to about l

40% to allow for repair of the Reactor Coolant Orain Tank (RCOT) pump. The plant was returned to 100% power at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on July .

6. The forced power reduction was 34.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in duration.

6. On July 26 at 0924 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.51582e-4 months <br />, the reactor tripped during testing of the "B" train solid state protection system. This event was similar to the reactor trip which occurred on June 1 and was the result of personnel error to correctly follow a procedure change initiated as a result of the previous event ( 088-009).

Criticality was again established on July 28 at 0124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br />. Tt.e generator was placed on line at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> resulting in a forced outage 47.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in duration.

7. On September 16 at 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br />, the plant commenced a load reduction for entry into the fourth refueling outage. The generator breaker was opened at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />. Major work activities included in the outage were:

A. Steam Generator Work '

The fourth inservice eddy current examination of the tubing in the'three steam generators was. performed on 100% of available tubes for the entire tube length. The results of the inspection are contained in the following table:

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l S/G A S/G B S/G C Total number of tubes plugged previously 117 293 129 Number of plugs removed and F* applied 12 17 0 Number of plugs removed for previous 5 2 0 misplugs h Number of plugs installed for new 180 233 175 indications Number of new F* tubes 85 186 69 Number of new tubes - 40% or greater 265 419 24i~' I indications Number of tubes repaired (i.e., sleeved) 0 0 0 Total number of tubes now plugged 280 507 304 Percent of total bundle now plugged 6.0% 10.8% 6.5%

i On October 26, 1988 at approximately 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />, the l' preliminary results of the eddy current examinations concluded that Technical Specifications Section 3.4.5, " Steam Generators," sample inspection category C-3 applied since greater than 1% of the inspected tubes were defective. A prompt notification was made to the NRC Operations Center at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> per the requirements of Technical Specification 4.4.5.5 and 10CFR50.72(b)2(i), and the required followur report (LER 88-011) was submitted on November'23, 1988 per 10CFR50.73(a)(2)(ii). The tube degradation, which was localized in the tubesheet area, has been attributed to Primary Water Stress Corrosion Cracking. _ Tube plugging to remove the defective tubes from service was completed un November 2, 1988.

8. Equipment Qualification - Upgrades for Harsh Environment A major work item which was undertaken throughout the course of the refueling outage involved walkdowns, inspections and modifications to ensure proper harsh environment equipment qualifications existed within portions of the plant which are inaccessible during normal power operation. Examples'of items which were examined include penetrations, limit switenes, splices, Limitorques, motors, wire and cable, ASCO solanoids, conduit and instrumentation. Work activities includea necessary maintenance involvement to perform inspections / repairs / upgrades, engineering input for evaluations and modification package generation, health physics overview for radiation monitoring and surveillance, Page 3 of 4

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and operations support for_ testing repaired or' modified equipment. Equipment qualification work was in progress throughout the entire shutdown _ period.

On December 26, 1988 at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />, initial criticality for cycle 5 was-achieved. The generator was placed on line at 1552 hours0.018 days <br />0.431 hours <br />0.00257 weeks <br />5.90536e-4 months <br />'on December 29 resulting in an outage of 2489.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. On December 31, the plant was'at 50%

power.

4.0 EXPOSURES 1

-Attachment I consists of tables which list the number of station, l utility, and other personnel (including contract personnel) receiving exposures greater than 100 Mrem / Year, and their associated man-rem ,

exposure according to work and-job functions.. l 5.0 FAILED FUEL The specific activity of the primary coolant remained within the limits of Technical Specification 3.4.8,." Specific Activity,"

throughout the report period.

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. . SOUTH CAROLINA ELECTRIC & GAS COMPANY V.C. SUMMER NUCLEAR STATION 1988 MAN-REM REPORT FOR PERSONNEL EXPOSURE GREATER THAN 100 MREM NUMBER OF PERSONNEL > 100 MREM TOTAL MAN-REM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT Reactor Operations & Surveilling Maintenance Persannel 2 0 2 1.548 0.090 2.575 Operating Personnel 23 0 2 5.940 0.070 1.256 Health Physics Personnel 3 0 18 1.013 0.025 7.440 Supervisory Personnel 0 0 0 0.610 0.005 0.100 Engineering Personnel 0 0 11 0.348 0.000 3.040 Routine Maintenance Maintenance Personnel 15 0 61 5.502 0.105 22.001 Operating Personnel 1 0 1 1.955 0.465 1.242 Health Physics Personnel 2 0 35 0.558 0.154 10.612 Supervisory Personnel 2 0 0 0.510 0.025 0.025 Engineering Personnel 0 0 0 0.130 0.000 0.435 Inservice Inspection Maintenance Personnel 1 0 45 0.735 0.220 20.610 Operating Personnel 8 0 3 3.540 0.120 1.335 l Health Physics Personnel 1 2 25 0.355 0.410 7.165 Supervisory Personnel 0 0 0 0.155 0.120 0.000 Engineering Personnel 0 0 12 0.015 0.000 3.760 Special Maintenance Maintenance Personnel 54 1 217 20.946 0.525 79.621 Operating Personnel 18 0 4 6.173 0.040 1.510 l Kealth Physics Personnel 4 1 87 1.665 0.220 26.770 !

Supervisory Personnel 6 0 1 2.350 0.040 0.126 Engineering Personnel 1 0 77 0.565 0.000 54.485 Waste Processing Maintenance Personnel 0 0 0 0.175 0.005 0.410 Operating Personnel 0 0 3 0.235 0.105 0.994 Health Physics Personnel 1 0 2 0.367 0 030 1.418 Supervisory Personnel 0 0 0 0.005 0.005 0.000 Engineering Personnel 0 0 0 0.000 0.000 0.020 Refueling Maintenance Personnel 18 0 49 10.250 0.000 18.035 Operating Personnel 4 0 7 1.605 0.005 1.705 Health Physics Personnel 3 0 38 1.360 0.000 12.580 Supervisory Personnel 5 0 0 3.765 0.000 0.000 Engineenng Personnel 0 0 4 0.065 0.000 1.740 TOTAM Maintenarice Personnel 90 1 374 39.156 0.945 143.252 Operating personnel 54 0 20 19.448 0.805 8.042 Health Physics Personnel 14 3 205 5.318 0.839 65.985 Supervisory Personnel 13 0 1 7.395 0.195 0.251 Engineering Personnel 1 0 104 1.123 0.000 63.480 GRAND TOTAL 172 4 y 704 72.440 2.784 281.010 The above W hole Body dose assignments are based on Pocket Dosimeter estimates, but also include Neutron exposures derived from REM-BALL / STAY TIME measurements.

c. v 10CFR50.36 So th Ciro irts Ekctric & Gas Ccmpany 11: 8 dham Jenkinsville, SC 29065 Nuclear Operations SCE&G February 28, 1989 nea aa,., -

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@N Mr. M. L. Ernst j Acting 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 Mr. Ernst:

t Attached is the 1988 Annual Rcport 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.

l Very truly yours,  !

0. S. Bradham AMM/0SB: led Attachment '

c: D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts W. A. Williams, Jr. K. E. Nodland General Managers J. C. Snelson J. J. Hayes, Jr. G. O. Percival L. A. Blue R. L. Prevatte W. R. Baehr J. B. Knotts, Jr.

C. A. Price /R. M. Campbell, Jr. NSRC l R. B. Clary RTS (RG 880003)

J. R. Proper File (818.02-10) l l

-= a /-