TXX-9704, Ses Annual Operating Rept 1996

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Ses Annual Operating Rept 1996
ML20135D507
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 12/31/1996
From: Terry C, Walker R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-97040, NUDOCS 9703050301
Download: ML20135D507 (25)
v • d • e


Text

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M' Log # TXX 97040 2M File # 10250 Ref. # 10CFR50.36 1UELECTRIC'  ;

February 28, 1997 C. Lance Terry y Group Mce President l

U. S. Nuclear Regulatory Commission Attention: Document Control Desk

Washington, DC 20555 -  !

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)-

UNITS 1 AND 2 i DOCKET NOS. 50 445 AND 50 446 '

+

ANNUAL OPERATING REPORT FOR 1996  !

Gentlemen-Attached is the CPSES Annual Operating Report for 1996 prepared and submitted pursuant to Technical Specification 6.9.1.2 contained in Appendix A to the l Comanche Peak Steam Electric Station Unit 1 Operating License NPF 87 and Unit 2 Operating License NPF 89. This attachment also complies with the annual operating report guidance provided in position C.1.b of U.S. NRC Regulatory Guide 1.16 Revision 4.

If you have any questions, please contact Mr. Jacob M. Kulangara at (817)897-0124. ,

Jl Sincerely, 0h C. L. Terry By: MN RogeF D. Walker Regulatory Affairs Manager JMK/jmk Attachment c- Mr. J. E. Dyer, Region IV Mr. J. I. Tapia. Region IV Mr. T. J. Polich, NRR Resident Inspector, CPSES Ms. M. L. Thomas, REIRS Project Manager (W/ Original copy of the )y Personnel Exposure & Monitoring report) 9703050301 961231 PDR ADOCK 05000445 R PDR a 1 05008G P. O. Box 1002 Glen Rose Texas 76043 .

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COMANCHE PEAK STEAM ELECTRIC STATION i i  !

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a ANNUAL OPERATING REPORT 1996  !

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l TEXAS UTILITIES ELECTRIC COMPANY

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1 Attachment to TXX 97040 Page 2 of 24 I

i TABLE OF CONTENTS i

i 1.0 Summary of Operating Experience I

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2.0 Outages and Reductions in Power  ;

- 3.0 Personnel Exposure and Monitoring Report i

4.0 Report of Results of Specific Activity Analysis in which the Primary '

Coolant Exceeded the Limits of Technical Specification 3.4.7 5.0 Irradiated Fuel Inspection Results 6.0 Outage Related Single Radioactivity Release or Radiaticn Exposure to an Individual that Accounts for More than 10 Percent of Allowable Annual Values 1

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Attachment to TXX 97040 ,

Page 3 of 24 i 1,0 SUMARY OF OPERATING EXPERIENCE l

The Comanche Peak Steam Electric Station (CPSES) is a dual unit pressurized  !

water reactor power plant, each unit licensed at 3411 Megawatt thermal (HWt).

It is located in Somervell County in North Central Texas approximately 65 ,

miles southwest of the Dallas Fort Worth Metropolitan area. The nuclear steam  !

supply system was purchased from Westinghouse Electric Corporation and is l rated for a 3425 Wt output.

1 1.1 CPSES UNIT 1 l l

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CPSES Unit 1 achieved initial criticality on April 3,1990. Initial power  ;

generation occurred on April 24, 1990, and the plant was declared commercial on August 13, 1990. Since being declared commercial, CPSES Unit I has  ;

generated 46,923,429 net Megawatt hours (HWH) of electricity as of December 31,19% with a net unit capacity factor of 72.9% (using HDC). The

, unit and reactor availability factors were 82.7% and 83.6%, respectively, for the year 19%.

J On October 4,19% power reduction was initiated for the unit for its fifth refueling outage. The main turbine was tripped on October 5, 1996 for the outage. Overall, the outage was successful in its implementation with a i

, duration of 42 days. 84 fresh fuel ammblies were loaded for Cycle 6. The i unit was returned to service on Nove ber 16, 1996.

Figure 1.11 provides the generation profile of the average daily net electrical output of Unit 1 for 1996. Table 1.11 is a cowilation of the monthly surmaries of the operating data and Table 1.12 cocains the yearly and total summaries of the operating data.

During the refueling outage, the major work scope completed included:

  • Main Generator Inspection i
  • High Pressure Turbine Inspection
  • Balance of Plant Pump Inspections
  • Reactor Pr0tection bstem Bypass Hodification  ;
  • Inverter and Batten Charger Replace 9nts i e Reactor Coolant P r.p Cartridge Seal ugeout

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  • Residual Heat Reqv11 Pump Couphng Upgrade
  • Main Feedwater Pump Digital Controller Installations o

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l l 1.2 CPSES UNIT 2 l

l CPSES Unit 2 achieved initial criticality on March 24, 1993. Initial power generation occurred on April 9,1993, and the plant was declared comercial on August 3, 1993. Since being declared commercial CPSES Unit 2 has generated 25,228,731 net Megawatt. hours (WH) of electricity as of December 31, 1996, with a net unit capacity factor of 73.3% (using MDC). The unit and reactor availability factors were 78.7% and 79.0%, respectively, for the year 19%.

On February 23,19% the unit began the end of cycle power ramp down for its second refueling outage. The unit entered the refueling outage on the same day when an unexpected turbine load shed prompted a mai..al reactor trip.

During the refueling outage, 96 fresh fuel assemblies were loaded for Cycle 3.

The refueling outage lasted 54 days and ended on April 17,19%. During startup following the outage, one of the Reactor Coolant Pump motors tripped on over current causing the unit to enter a forced outage to replace the motor. Unit 2 was returned to service on May 6,19%,

During the refueling outage, the major work scope completed included:

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  • Reacter Vessel 40 month Hot Leg Nozzle Exam
  • Main Generator Inspection '
  • Integrated Test Sequence on Train A and B j
  • Inspection of Fuel Assemblies l
  • Main Feedwater Pump Digital Controller Modification
  • Emergency Diesel Generators Train B Turbo Overhaul Figure 1.21 provides the generation profile of the average daily net electrical output of Unit 2 for 1996. Table 1.2-1 is a compilation of the  ;

monthly summaries of the operating data and Table 1.2 2 contains the yearly '

and the total summaries of the operating data.

I 2.0 OUTAGES AND REDUCTIONS IN POWER 2.1 CPSES UNIT 1 Table 2.1 describes unit operating experience including unit shuMowns and provides explanations of significant dips in average power levels for CPSES Unit 1.

2.2 CPSES UNIT 2 i Table 2.2 describes unit operating experience including unit shutdowns and l

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provides explanations of significant dips in average power levels for CPSES l Unit 2. j 3.0 EXPOSURE Als MONITORING REPORT

!' The personnel exposure and monitoring report for CPSES is provided in l Table 3.0.

4.0 REPORT OF RNH TS OF SPECIFIC ACTIVITY ANALYSIS IN WICH THE PRIMARY COOLANT EYrH nFD THE LIMITS OF TECHNICAL SPECIFICATION 3.4.7 i

Technical Specification 6.9.1.2.b requires the reporting of results of j
specific activity analyses in which the , 'ary coolant exceeded the limits  !

j of Technical Specification 3.4.7. i 4

CPSES Units 1 and 2 primary coolant did not exceed the limits of Technical Specification 3.4.7 for the calendar year 1996.

5.0 IRRADIATED FUEL INSPECTION RESULTS 5.1 CPRFR UNIT 1 The reactor coolant fission product activity levels were carefully monitored throughout Cycle 5 operation. Analysis of the activity levels indicated no leaking fuel. Nonetheless, visual inspections were performed by inspection personnel from the edge of the spent fuel pool to assess the external condition of the fuel assemblies. All fuel assemblies appeared to be in good ,

condition. I Also during the outage, eddy current examinations of all 53 Unit 1 control rod  !

clusters (as well as profilometry measurements on selected rods) were  !

prformed. In sunnary, the results of the exams showed miniurm wear (<5% clad wlume reduction) on all but two control rod cluster rodlets (10% clad volume i reduction in R537 and.18% clad volume reduction in R508. respectively). These I two rodlets are still well within acceptable limits for continued operation for several more cycles and were subsequently re inserted into the Unit 1 Cycle 6 core. Analyses of the inspection data indicated that the amount of wear on the Unit I control rods was less tnan expected.

Following startup for Cycle 6 operations and throughout the remainder of 19%, l Unit 1 showed no indications of leaking fuel.  !

5.2 CPSES UNIT 2 The reactor coolant fission product activity levels were carefully monitored throughout Cycle 2 operation. Analysis of the activity levels indicated the presence of one leaking fuel rod. During refueling, "in mast" sipping was I performed on all Cycle 2 assenblies as they were being off loaded from the J core. Assembly BB 41 was the only assembly which showed any signs of leaking fuel. Assembly BB-41 was then ultrasonically tested and indicated that the

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. fuel rod in assembly location P 10 was leaking.

During the refueling outage, visual examinations were also performed on all Cycle 2 fuel assemblies using an underwater camera system. Detailed visual examination of assembly BB 41 revealed a slight discoloration of the fuel rod clad surface on the exterior fuel rods in the general vicinity of the leaking rod. This type of discoloration is characteristic of nearby leaking fuel, however the actual leaking rod was not visible due to its location in the interior of the assembly. There were no additional anomalies observed in the remainder of the Cycle 2 fuel. Assembly BB 41 was discharged during the outage. Following startup for Cycle 3 operations and throughout the remainder of 19%, Unit 2 had no further indicctions of leaking fuel.

6.0 OUTAGE RELATED SINGlF RADIQACTIVITY RELEASE OR RADIATION EXPOSURE j IQ_AN INDIVIDUAL THAT ACCOUNTS FOR MORE THAN 10 PERCENT OF AllNABLE ANNUAL VALUES CPSES Units 1 and 2 did not experience any single release of radioactivity greater than 10% of an allowable dose limit during an outage or forced reduction in power of over 20% of designed power level during 19%.

During 19% CPSES Units 1 & 2 each conducted refueling outages (see section i 1.1 and 1.2). During the outage activities, certain individuals received radiation exposure exceeding 10% of an allowable dose limit in a single exposure event. These exposurcs are tabulated in Table 6.0.

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Attachment to TXX-97040 Page 7 of 23 ,

FIGURE 1.1-1 COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 GENERATION PROFILE .

AVERAGE DAILY UNIT POWER LEVEL i.2co 600 -

400 -

F 200 -

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC

6aM_L 3 CJ_A- d-4-= ' -- .4E 4 -%J. A-Si- 4 4 SL+- 1- 4 46+Ei 1. A 6a - km- - 4A _ a .L. a. _ , _ . .a._.4,a A ,.4 g _4 Attachment to TXX-97040 Page 8 of 24 .

TABLE 1.1-1 (PAGE 1 0F 2) -

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 MONTHLY ELECTRIC POWER GENERATION DATA (1996)

January February March April thtY Juan Hours RX was Critical 443 614 744 670 744 720 RX Reserve Shutdown Hours 0 0 0.0 0.0 0.0 0.0 Hours Generator On-Line 438 602 744 652 744 720 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 1.426.730 1.825.920 2.524.968 2.149.872 2.526.504 2.453.777 Gross Electric Energy Generated (MWH) 481.186 670.850 855.750 723.877 854.059 821.391 Net Electric Energy Generated (MWH) 45C.558 639.745 822.197 692.402 819.427 787.703 RX Service Factor (*) 59.6 88.3 100.0 93.2 100.0 100.0 RX Availability Factor (*) 59.6 88.3 100.0 93.2 100.0 100.0 Unit Service Factor (t) 58.9 86.5 100.0 90.7 100.0 100.0 Unit Availability Factor (*) 58.9 86.5 100.0 90.7 100.0 100.0 Unit Capacity Factor (t.using E C net) 52.7 79.9  %.1 83.7 95.8 95.1 Unit Capacity Factor (I.using DER net) - 52.7 79.9  %.1 83.7 95.8 95.1 ,

Unit Forced Outage Rate (*) 41.1 13.5 0.0 9.3 0.0 0.0 Hours in Month 744 6% 744 719 744 720 ,

Net IOC (MWe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0 t

_ _ -. _- _ -____m.u___ _ .-._ _ _ _ . _ _ _ _ .-. ._ 2__.-_ ___.u. _. ..am.- ' _ _ _ _ _mw__u____-_2______ m-_ _ . . _ _ _mw__-_--_ _ _ _ _ _ _ _ _ _ _______________---___-m.__ _ _.__.-_m. _

Attachment to TXX-97040 Page 9 cf 24 .

TABLE 1.1-1 (PAGE 2 0F 2) .

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 MONTHLY ELECTRIC POWER GENERATION DATA (1996)

Aly Auaust Sentember October November December Hours RX was Critical 744 727 720 100 372 744 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744 719 720 99 339 744 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 2.530.426 2.324.479 2.449.157 318.590 957.662 2.536.114 Gross Electric Energy Generated (MWH) 840.646 767.641 818.306 107.246 319.506 861.869 Net Electric Energy Generated (MWH) 805.610 732.670 785.257 98.013 294.453 828.201 RX Service Factor (t) 100.0 97.7 100.0 13.4 51.7 100.0 RX Availability Factor (t) 100.0 97.7 100.0 13.4 51.7 100.0 Unit Service Factor (1) 100.0  %.7 100.0 13.3 47.0 100.0 Unit Availability Factor (t) 100.0  %.7 100.0 13.3 47.0 100.0 Unit Capacity Factor (t.using IOC net) 94.2 85.6 94.8 11.4 35.6 96.8 Unit Capacity Factor (2.using DER net) 94.2 85.6 94.8 11.4 35.6  %.8 Unit Forced Outage Rate (t) 0.0 3.3 0.0 0.0 0.0 0.0 ,

Hours in Month 744 744 720 745 720 744 Net MDC (Mwe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0 i

- .- ,y _,, , -- , ,- g m +--. - *~, . - - ,

- . - . ._. .- . - ~ - - ..

.- Attachment to TXX 97040 Page 10 of 24 TABLE 1.1-2 COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 ANNUAL ELECTRIC POWER GENERATION DATA (19%)

XEAR CUMULATIVE Hours RX was Critical 7,343 46,094 RX Reserve Shutdown Hours 0.0 2.604 Hours Generator On Line 7,265 45,454 Unit Reserve Shutdown Hours 0.0 0.0 Gross Thermal Energy Generated (HWH) 24,024.199 147.449,451 Gross Electric Energy Generated ( W H) 8,122.327 49,188,530 ,

Net Electric Energy Generated (HWH) 7,756.236 46,923,429 RX Service Factor (*) 83.6 82.3 RX Availability Factor (%) 83.6 87.0 Unit Service Factor (%) 82.7 81.2 Unit Availability Factor (%) 82.7 81.2 Unit Capacity Factor (*,using HDC net) 76.8 72.9  ;

Unit Capacity Factor (%,using DER net) 76.8 72.9 l Unit Forced Outage Rate (%) 6.3 4.8 l Hours in Reporting Period 8,784 55,985  ;

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Attachment to TXX-97040 Page 11 of 23

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FIGURE 1.2-1 COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 GENERATION PROFILE AVERAGE DAILY UNIT POWER LEVEL 1,200 FF 1 --

y 800 -

600 -

u 400 -

200 -

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JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC

Attachment to TXX-97040 Page 12 of 24 ,

TABLE 1.2-1 (PAGE 1 0F 2) .

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 MONTHLY ELECTRIC POWER GENERATION DATA (1996)

January Februarv  !$ lech 8 Dell lily JuDit Hours RX was Critical 744 535 0 0 602 720 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744 535 0 0 591 720 Unit Reserve Shutdown Hours 0.0 0.0' O.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 2.529.072 1.732.152 0 0 1.738.968 2.325.950 Gross Electric Energy Generated (MWH) 864.708 390.277 0 0 575.166 781.896 Net Electric Energy Generated (MWH) 832.973 565.044 0 0 543.252 749.526 RX Service Factor (t) 100.0 76.9 0.0 'O.0 80.9 100.0' RX Availability Factor (t) 100.0 76.9 0.0 0.0 80.9 100.0 Unit Service Factor (2) 100.0 76.9 0.0 0.0 79.5 100.0 Unit Availability Factor (t) 100.0 76.9 0.0 0.0 79.5 100.0 Unit Capacity Factor (t.using N)C net) 97.4 70.6 0.0 0.0 63.5 90.5 Unit Capacity Factor (t.using DER net) 97.4 70.6 0.0 0.0 63.5 .90.5 Unit Forced Outage Rate (2) 0.0 1.7 0.0 100.0 20.5 0.0 Hours in Month 744 6% 744 719 744 720 Net M)C (mie) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0

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TABLE 1.2-1-(PAGE 2 0F 2) .

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 'I MONTHLY ELECTRIC POWER GENERATION DATA (1996)

. July Auaust September October November December  ;

Hours RX was Critical 744 744 661 722 720 744 ,

RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744 744 655 714 720 744' Unit Reserve Shutdown Hours 0.0 .0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated ( M ) 2.530.637 2.532.626 2.011.807 2.353.951 2.449.903 2.515.649' Gross Electric Energy Generated (M) 851.070 854.521 671.025 800.730 837.815 860.271 .f Net Electric Energy Generated (M) 817.644- 821.059 638.507 766.674 806.956 828,738 RX Service Factor (1) 100.0 100.0 91.8 97.0 100.0 100.0 RX Availability Factor (2) 100.0 100.0 91.8 97.0 100.0 100.0 Unit Service Factor (1) 100.0 100.0 90.9 95.8 100.0 100.0 Unit Aveilability Factor (1) 100.0 100.0 90.9 95.8 100.0 100.0 _i Unit Capacity Factor (1.using LOC net) 95.6 96.0 77.1 89.5 97.5 96.9 Unit Capacity Factor (t.using DER net) 95.6 96.0 77.1 89.5 97.5 96.9 .

Unit Forced Outage Rate (1) 0.0 0.0 9.1 4.2 0.0 0.0 Hours in Month 744 744 720 745 720 744 .j Net IOC (Mwe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0 .j t

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-. _ _ _ _ . _ _ . _ . _ . _ . _ _ ___m__. _ _ _ ___ .m m_m-.__._. .m-_. m___ ..m_m__ . _ _ . . ._ . _ - - _m . . - - - .____.ini I .- m, . ._ .- )

Attachment to TXX-97040 Page 14 of 24 TABLE 1.2 2 COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 I l

ANNUAL ELECTRIC POWER GENERATION DATA (19%)

YEaB CUMULATIVE Hours RX was Critical 6,937 24,481 RX Reserve Shutdown Hours 0 2,229 Hours Generator On Line 6,912 24,234 Unit Reserve Shutdown Hours 0.0 0.0 Gross Thermal Energy Generated (MWH) 22,720,716 78,283,626 Gross Electric Energy Generated (MWH) 7,687,479 26,392,100 Net Electric Energy Generated (HWH) 7,370,373 25,228,731 RX Service Factor (*) 79.0 81.8 RX Availability Factor (*) 79.0 89.3 Unit Service Factor (%) 78.7 81.0 i Unit Availability Factor (*) 78.7 81.0 Unit Capacity Factor (*,using MDC net) 73.0 73.3 Unit Capacity Factor (%,using DER net) 73.0 73.3 Unit Forced Outage Rate (%) 7.9 7.5 Hours in Reporting Period 8,784 29,920 1

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Attachment to TXX-97040 Page 15 of 24 .

TABLE 2.1 (PAGE 1 0F 4)

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND POWER REDUCTIONS .

METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION

  • THE REACTOR OR NQ MIE S: SCHEDULED (HOURS) REASON REDUCING POWER CORRECTIVE ACTIONS / COP 9 TENTS 1  % 0117 F 73.9 A 3 While re-energizing failed inverter IVIPC2, automatic reactor scram and Safety Injection System actuation  !

occurred at approximately 0808 on January 17, 1996. Revised ABN procedure to reflect additional steps while re-energizing invertors. Unit entered criticality on January 20, 1996 and synchronized to the grid on the same day. Unit achieved 100% power at .

0147 on January 22, 1996.

Reference:

LER 445/%-001-00 2  % 0122 F 318.3 A 2 On January 22, 1995 manually tripped the reactor at 0806 due to a loss of power to bus IEC1 due to IV1EC1 inverter failure. Following completion of inverter testing and repairs to improve equipment reliability, reactor entered criticality on February 4, 1996 at 0946.

Reference:

LER 445/%-002-00.

i 3  % 0204 F 7.7 G 1 On February 4,1996 approximately at 1630, manually tripped the turbine due to tripping of both main feedwater pumps on low suction pressure (due to improper venting of feedwater i

Attachment to TXX-97040 -

Page 16 of 24 TABLE 2.1 (PAGE 2 0F 4) .

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND POWER REDUCTIONS METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION

  • THE REACTOR OR g) DAIE S: SCHEDULED (HOURS) REASON REDUCING POWER t.unKECliVE ACTIONS /COMENTS heaters) as auxiisary feedwater pumps activated.

Reference:

LER 445/96 003-00.

4  % 0205 F "A A 4 Unit synchronized to the grid on February 5, 1996, at 0013 and the power held at 45t level to troubleshoot and align Heate- Drain Valve 1-LV-2592.

Unit reached 100t power on February 6, 1996 at approximately 1345.

5  % 0410 F NA A 4 On April 1, 1996, at 1744. Safety Injection Relief Valve 18851 leaked due to cracked weld on the piping flange and entered Technical Specification 3.0.3. On April 10. 1996, turbine load reduction began required per Technical Specificatio n to repair the leak on the Safety Injection Relief Valve. Reduced power to 12

  • to perform repairs to the cracked weld on the valve. Following completion of valve repair, power rampup began on April 11. 1995 at 0015.

Reference:

LER 445/96-005-00.

6 960411 F 66.8 A 2 After completion of repair of the cracked weld, unit was ramped up to 257 power level. On April 11.19%, at approximately 0215 action was initiated

. Attachment to TXX-97040 Page 17 of 24 .

i to bring the unit to MODE 2 to repair i TABLE 2.1 (PAGE 3 0F 4)  !

CONANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AM) POER REDUCTIONS METHOD OF i TYPE SHUTTING DOWN  !

F: FORCED DURATION

  • THE REACTOR OR  !

jg} untCTIVE ACTIONS /C0fgENTS MIE S: SCHEDULED (HOURS) REASON REDUCING POER  !

damaged seal gasket on Heater Drain  !

Valve 1-LV-2592. At this time. tripped  !

the reactor manually due to rod control '

malfunction due to a failed bank.

overlap counter circuit board. On t April 13, 1996, replaced the failed .

circuit board and the valve gasket and unit entered MODE 2 at approximately

  • 0512 and synchronized to the grid at i 2138. On April 15. 1996, the unit .

regained 1001 power'at 1800.  !

Reference:

LER 445/96-006-00.  ;

i 7 960809 F 24.7 H 3 On August 9.-1997, at 1203, reactor i automatically tripped due to lightning  !

strike causing N-16 instrument loop [

spike while N-16 loop 3 was out'of .

j service for Analog Channel Operational i

. Test. On August 10, 1996 unit [

synchronized to the grid at 1245.  !

Reference LER-445/%-007. l t

8 960812 F ~ NA A 4 During power rasp-up at 95* power, the i Heater Drain Pump 1-02 was manually ' i tripped on August 12. 1996 at 1431. due l to high inboard bearing temperature. '

Reduced power to 70% and replaced the inboard bearing and the unit continued  ;

the ramp-ep.  !

- _-_ _ . - - . _- . _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - - _ _ _ - _ _ _ . _ _ _ = _ _ - _ _ . - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ - .

Attachment to TXX-97040 Page 18 of 24

  • TABLE 2.1 (PAGE 4 0F 4)

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND POWER REDUCTIONS METHOD OF TYPE SHUTTING DOWN-F: FORCED DURATION

  • THE REACTOR OR NQ D&IE S: SCHEDULED (HOURS) REASON REDUCING POER CORRECTIVE ACTIONS /C0l#ENTS 9  % 1005 S 646.1 C 1 On October 1. 1996, at approximately 0630 unit began end of cycle coast-down in preparation for the fifth refueling (IRF05) and unit began ramping down power level for.

start of refueling outage on October 4. 1996 at 2200. On October 5, 1996 at 0253 tripped main turbine and unit began IRF05.

9  % 1101 S 381.4 C 1 Upon coupletion of the Unit refueling outage, unit returned to power on November 16, 1996 and unit regained 100% power on November 22, 1996 at 1810.

1) REASON 2) ETMID A:EQUIPE NT FAILURE (EXPLAIN) E: DERAT:R TRAINING #0 LICENSE EXAMINATION 1: IWRML B:NAINT OR TEST F: ADMINISTRATIVE 2: W4 RIAL SCRAN C:EFELING G: OPERATIONAL ERROR (EXPLAIN) 3: AtHOMATIC SCRAM  ;

D:EGULATORY RESTRICTION H: OTER (EXPLAIN) 4: OTER (EXPLAIN)

  • IICICATES SRITDOWN HOURS /0TERWISE *NA" FOR NOT APPLICABLE

Attachment to TXX-97040 Page 19 of 24 .

TABLE 2.2 (PAGE 1 0F 3) .

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND POER REDUCTIONS METHOD OF TYPE SHUTTING DOWN F: FORCED DUP.ATION* THE REACTOR OR g} MIE S: SCHEDULED (HOURS) REASON REDUCING POER CORRECTIVE ACTIONS /COMIENTS 1  % 0201 F NA A 4 On February 1,1996, at approximately 1207

'Condensating Polishing Vessel *E' partially isolated causing a reduction in condensate and feedwater flow. Manual turbine runback resulted due to low feedwater suction pressure and unit stabilized at 861 power.

2  % 0214 F NA H 4 On February 14, 1996. at approximately 0832, automatic turbine runback took place due to unexpected opening of feedwater heater bypass valve 2-PV-2286 and loss of feedwater heaters. This resulted from the closing of Gland Steam Condenser (GSD) condensate bypass flow control valve 2-FV-2243 upon removal of an associated controller card for calibration. Following the turbine runback, unit stabilized at 871 electric power. As part, of corrective measure.-issued Instrumentation

& Control procedure changes to address precautions for shared card scenario, j 3  % 0223 F 9.5 A 2 On February 23, 1996, at 0152 unit began end of cycle ramp down to start the second refueling outage (2RF02). At 0729. .

manually tripped the reactor when turbine  !

unexpectedly shed load during ramp down for the refueling outage.

Rference: ~LER 446/96 002-00.  ;

_ _ - _ . . . _ - . _ . . _ . . . . . _ . . _ .. _ __ . ....... _ ._.m. _ _._ _ ._ .. - . _ . . _ . _ . . _. . _ _

. Attachment to TXX-97040 Page 20 of 24  :'.

. r TABLE 2.2 (PAGE 2 0F 4)  ;

CONANCHE PEAK STEAN ELECTRIC STATION - bNIT 2 .

UNIT OPERATING EXPERIENCE INCLUDING SHUTD0letS AND POWER REDUCTIONS .

ETH09 0F t TYPE SHUTTING DOWN  ;

F: FORCED DURATION

  • THE REACTOR OR  !

E MIE S: SCHEDULED (HOURS) REASON REDUCING POER CORRECTIVE ACTIONS /COMENTS . . _ ,

4  % 0223 S 1278.0 C 1 On February 23, 1996. unit entered the-second refueling outage (2RF02). On i April 11, 1996, at 1254.~ the  :

Reactor Coolant Pump motor 2-01 tripped on over-current; planned unit refueling outage ended on April .

17, 1996. f i

5 960417 F 336.0 A 4 On April 17. 1996. unit entered a forced

- outage to replace the Reactor Coolant Pump .I*

motor 2-01.

6  % 0501 F 152.5 A 4 Continued forced outage to complete-  ;

repairs to Reactor Coolant Pump motor j 2-01. On Nay 1.-1996. completed Reactor Coolant Pump motor 2-01 installation and testing. Unit entered criticality on Nay ,

6. 1996 and synchronized to grid on Nay 7 1996. Unit was held at %t power due to j stuck check valve 210 -0718 requiring use of less efficient flow path.

7  % 0607 S NA B 4 On June 7, 1997, at 0350 reduced' unit power to 50% for planned ,

maintenance to replace the outboard  ;

journal bearing on main feedwater t f

-_ _ , _ _ . , _ _ . _ . _ _ . _ ._._. .___ _ _._____ . , . . _ _ . _ _ _ _ _ . _ _ _ . _ _ _ _ . . . _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ .__....._,_m_ _ _ _ _ _ _ . . _ _ _ _ . . . _ . - _ . . . . _ _ _ . - . - _

Attachment to TXX-97040 Page 21 of 24 .

TABLE 2.2 (PAGE 3 0F 4)

COMANCE PEAK STEAM ELECTRIC STATION - UNIT 2 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND POWER REDUCTIONS ,

NETHOD OF TYPE SifJTTING DOWN F: FORCED DURATION

  • THE REACTOR OR g) DAIE S: SCHEDULED (HOURS) REASON REDUCING POWER CORRECTIVE ACTIONS /COMENTS pump 28 and for repair of the stuck check valve 22-0718. On June 10.

1996, at 0538. unit achieved 100*

power upon completion of replacement and repair work.

8 960918 F 65.4 H 3 On September 18. 1996 at 1245 reactor tripped due to lightning strike causing reactor coolant system instrument spike.

Reference:

LER 446/96-006.

9  % 0922 F NA A 4 While ramping up, on September 22, 1996, at 0354 unit power held at 612 due to Heater Drain Pump 2-02 high bearing temperature. Further power level reduced to 56% due to high bearing temperature on Main Feedwater Pump 2-01. On September

26. 1996, continued power ramp-up after completing the pump repairs and the unit achieved 100% power at 0553 on the next day. ,

10  % 1011 S NA B 4 On October 10. 1996, at 2200 reduced unit power level to 50% to troubleshoot Main Feedwater (MFW) pump 2A oscillations. On October 12.

1996 replaced the pilot valve servo (controls) associated with the main-feedwater pump and unit regained 100t power at 0525 on October 13.

19%.

Attachment to TXX-97040 Page 22 of 24 '.

TABLE 2.2 (PAGE 4 0F 4) .

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND POWER REDUCTIONS METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION

  • THE REACTOR OR NQ D81E S: SCHEDULED (HOURS) REASON REDUCING POE R CORRECTIVE ACTIONS / COP 9ENTS 11  % 1018 F 31.0 H 3 On October 18, 1996, at 0306.

reactor automatically tripped due to lock-out on non-safeguards bus 2A3 which caused the de-energizing of Reactor Coolant Pump 2-03. On October 19, 1996, at 1007. unit synchronized to the grid and achieved 1002 power the following day.

Reference:

LER 446/96 007.

12 %1210 S NA B 1 On December 10, 1996, at 2122. for conservatism. reduced unit power level to 50% to perform troubleshooting and repair of inverter IV2C3. On December 11, 1996. '

at 1035 completed inve-ter card i replacement and associated repair and the unit regained 1001 power at 2026.  !

1) REASON 2) ETHOD A:EQUIPENT FAILtRE (EXPLAIN) E: OPERATOR TRAINING # D LICENSE EXANINATION 1: MANUAL
  • B:lRINT OR TEST F: ADNINISTRATIVE 2: MANUAL SCRAN C:REFLELING G: OPERATIONAL ERROR (EXPLAIN) 3: AUTOMATIC SCRAN D: REGULATORY RESTRICTION H: ODER (EXPLAIN) 4: OTER (EXPLAIN)
  • If0ICATES SRITDOWN HOURS /0TERWISE "NA* FOR NOT APPLICABLE t

.' Attachment to TXX-97040 Page 23 of 24 TABLE 3.0 COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 4

, 1996 PERSONNEL EXPOSURE AND MONITORING REFORT

  1. Personnel (>100 mrem) Total Person - renn

! Work & Job Function Station J11Hig Contract Station Utility Contract Reactor Operations & Surveillance Maintenance & Construction 0 0 22 .165 .000 6.552 Operations 42 0 0 10.070 .026 .636 Health Physics & Lab 16 0 39 4.903 .087 11.520 Supervisory & Omce Staff 0 0 0 .137 .000 .067 l- Engineering Staff 0 0 0 .939 .010 .203 i Routine Plant Maintenance 3 Maintenauce & Construction 44 0 255 10.656 .000 82.980 l Operations 9 0 4' 2.732 .060 1.420 j Health Physics & Lab 4 1 8 1.408 .155 2.332 1 Supervisory & Omce StaK 0 0 0 .118 .000 .005 t- Engineering Staff 4 0 7 2.190 .029 1.698

}- In-service Inspection j Maintenance & Construction 4 0 100 2.406 .000 43.741 i Operations . 10 0 2 8.431 .000 .505 g Health Physics & Lab 3 0 14 1.840 .000 3.492

~

Supervisory & Omce Staff 1 0 0 .649 .000 .000 Engineering Staff 5 0 5 3.358 .042 1.644

  • Special Plant Maintenance Maintenance & Construction 1 0 50 .300 .000 16.545 Operations 0 0 3 .265 .010 1.246 Health Physics & Lab 0 0 0 .097 .000 .583 Supervisory & Omce Staff 0 0 0 .021 .000 .000 Engineering Staff 2 0 4 .406 .000 1.217

. Waste Processing Maintenance & Construction 0 0 2 .059 .000 .706 Operations 1 0 I .956 .000 .551

. Health Physics & Lab 5 1 0 1.544 .187 .488 Supervisory & Omce Staff 0 0 0 .000 .000 .000 Engineering Staff G 0 0 .076 .000 .000 Refueling Maintenance & Construction 2 0 94 .896 .000 47.557 Operations 6 0 1 1.680 .004 .188 Health Physics & Lab 4 0 8 1.899 .000 2.524 Supervisory & Omce Staff 0 0 0 .011 .000 .006 Engineering Staff I 0 1 .445 .000 .597 Totals Maintenance & Constructi>n 51 0 490 14.482 .000 198.080 Operations 76 0 9 24.133 .099 4.547 Health Physics & Lab 29 1 59 11.692 .429 20.938 Supervisory & Office Staff 1 0 0 .936 .000 .078 Engineering Staff 15 0 19 7.414 .082 5.359 Grand Totals 172 1 577 58.657 .610 229.002

  • Costing repairs in the radiologically controlled areas and installation of permanent sludge lance platforms

4 .

' Attachment to TXX 97040 i

Page 24 of 24

. t .

TABLE 6.0 COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 OUTAGE RELATED RADIATION EXPOSURE TO AN INDIVIDUAL FOR A SINGLE MAINTENANCE ACTIVITY WHICH EXCEEDS 10 PERCENT OF AN ALLOWABLE ANNUAL DOSE LIMIT

  • Maintenance Deoartment Individual's Individual's l

Activity Sinale Event Total Annual Exoosure (arem) Exoosure (mres)

Nozzle Dam Radiation Protection 618 618 Nozzle Dam Safety 510** 1147

, Nozzle Dam Safety 597** 1147 Nozzle Dam Training 529 945 Nozzle Dam Maintenance 763 988 Nozzle Dam Overview 555 648 4 Nozzle Dam Overview 875 999 Nozzle Dam Emergency Planning 510 1021 Nozzle Dam Engineering 651 750 Nozzle Dam Safety 629 673 Nozzle nam Operations 753 764 Nozzle Das Emergency Planning 809 1061 d

Nozzle Dam Engineering 769 808

. Nozzle Dam Overview 872 959 3 Nozzle Dam Training 649 649 Nozzle Dam Maintenance 981 981 P

i

!

    • Event involved same individual l i

i l

l 1

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