Text

Annual Operating Rept 1992. W/930226 Ltr
	ML20044B694
Person / Time
Site:	Comanche Peak
Issue date:	12/31/1992
From:	William Cahill, Walker R; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TXX-93084, NUDOCS 9303030086
	Download: ML20044B694 (32)
	v • d • e

_ . _ _ ______ _ _ _ _ _ _ _ _ _

1 id y7 Log # TXX-93084 File # 10250 (clo & Att.)

Ref. # 10CFR50.36

=

TUELECTRIC February 26. 1993 William J. Cahill, Jr.

a,np r,ca r,cun,r U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 1 DOCKET NO. 50-445 ANNUAL OPERATING REPORT Gentlemen:

Attached is the CPSES Annual Operating Report for 1992 prepared and

submitted pursuant to Technical Specification 6.9.1.2 contained in Appendix j A to the Comanche Peak Steam Electric Station Unit 1 Operating License NPF-

87. This attachment also complies with the annual operating report guidance provided in position C.I.b of U.S. NRC Regulatory Guide 1.16 Revision 4.

If you have any questions, please contact Mr. Roy Cisneros at (214) 812-8814.

Sincerel .

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p. ,f>

William J. Cahill Jr By: OM' '

Roger %. Walker Manager of Regulatory Affairs for NE0 RC/grp 1 Attachment I l

c- Mr. J. L. Milhoan. Region IV Resident Inspectors CPSES (2) .

Mr. T. A. Bergman, NRR I Mr. A. B Beach, Region IV )

Ms. C. T. Raddatz. ONRR (w/ Original Copy of the Personnel Exposure Monitoring Report-Table 3 of Att.)

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Attachment to TXX-93084 -

Page 2 of 30 l i

l TABLE OF CONTENTS i i

I 1.0 Summary of Operating Experience- ;

2.0 Outages and Reductions in Power f 3.0 Personnel Exposure and Monitoring Report 4.0 Report of Results of Specific Activity Analysis in which the Primary Coolant Exceeded the Limits of ,

Technical Specification 3.4.7 i 5.0 Irradiated Fuel Inspection Results l 1

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Attachment to TXX-93084 I Page 3 of 30 ;

1.0 SUPHARY OF OPERATING EXPERIENCE I t

The Comanche Peak Steam Electric Station (CPSES) is a pressurized water l Reactor licensed at 3411 Megawatt thermal (MWt). It is located in r Somervell County in North Central Texas about 65 miles southwest of the .

Dallas-Fort Worth Metropolitan area. The nuclear steam supply system t was purchased from '4estinghouse Electric Corporation and is rated for a '

3425 MWt output. ;

i 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 14,842,376 MW hours of electricity as of December 31, 1992, with a net plant capacity factor of 61.7 (using MDC). The unit and Reactor availability was 79.1% and 84.0%, respectively for 1992. ;

On October 22, 1992, the unit was removed from service for its second refueling outage. Overall, the outage was successful in its !

implementation with a duration of 64 days. Sixty-one fresh fuel ;

assemblies were loaded for Cycle 3. The unit was returned to service on December 31, 1992. ;

During the refueling outage the major work scope included:

A Reactor Coolant Pump seal replacement ,

,

Removal of stuck Reactor vessel stud (from the first refueling outage) ,

Replacement of lower element of "B" Train Station Service Water Pump due to cooling flow problems '

An upgrade to the diffuser and shaft on the Auxiliary Feedwater Pump (followup to 10CFR Part 21 Notification)

Steam Generator maintenance including eddy current testing and sludge j lancing

Motor Operated Valve refurbishment and testing

The installation of Unit 1 - Unit 2 interface design modifications ;

in preparation for combined unit operation.

Figure 1.0 provides a histogram of the average daily electrical output of the unit for 1992. Table 1.1 is a compilation of the monthly summaries of the operating data and Table 1.2 contains the yearly and j total summaries of the operating data. ;

2.0 OlfTAGES AND REDUCTIONS IN POWER Table 2.0 describes plant shutdowns and provides explanations of significant dips in average power levels.

l Attachment TXX-93084 Page 4 of 30 3.0 PERS0hNEL EXPOSURE AND MONITORING REPORT <

The personnel exposure and monitoring report is provided in Table 3.0.

4.0 REPORT OF RESULTS OF SPECIFIC, ACTIVITY ANALYSIS IN WHICH THE PRIMARY COOLANT EXCEEDED THE LIMITS OF TECHNICAL SPECIFICATION 3.4.7 Technical Specification 6.9.1.2.b requires the results of specific activity analyses in which the primary coolant exceeded the limits of Technical Specification 3.4.7.

The information is provided for this report in three parts to reflect each event as follows:

4.1 Reactor trip on July 20, 1992 A. Reactor power history, Table 4.1A and Figure 4.1A B. Radiciodine isotopic analyses, Table 4.1B C. Clean up flow history, Table 4.1C D. Graph of I-131 and one other radiciodine, Figure 4.1D E. Time duration when specific activity exceeded the radiciodine limit: 16.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months from July 20, 1992, at 1802 hours0.0209 days 0.501 hours 0.00298 weeks 6.85661e-4 months through July 21, 1992, at 1035 hours0.012 days 0.288 hours 0.00171 weeks 3.938175e-4 months 4.2 Reactor trip on October 12, 1992 A. Reactor power history, Table 4.2A and Figure 4.2A .

B. Radiciodine isotopic analyses, Table 4.2B C. Clean up flow history, Table 4.2C D. Graph of I-131 and one other radiciodine, Figure 4.2D E. Time duration when specific activity exceeded the radiciodine limit: 15.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months from October 12, 1992, at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months through October 13, 1992, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months -

4.3 RFO-2 shutdown on October 23, 1992 A. Reactor power history, Table 4.3A and Figure 4.3A B. Radiciodine isotopic analyses, Table 4.3B C. Clean up flow history, Table 4.3C D. Graph of I-131 and one other radiciodine Figure 4.3D E. Time duration when specific activity exceeded the radiciodine limit: 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months from October 23, 1992, at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months through October 23, 1992, at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months .

Attachment to TXX-93084 Page 5 of 30 5.0 IRRADIATED FUEL INSPECTION RESULTS In October 1992, CPSES Unit 1 entered its second refueling outage.

During Cycle 2, TU Electric accepted a Westinghouse proposal to install and qualify a new system for fuel assembly failure detection termed "in-mast" sipping. This system relies on the detection of fission product gases from failed fuel assemblies as does the well established "in-can" sipping technique. The difference in the two systems is that "in-mast" sipping is performed from the refueling machine mast during core off-load instead of from a sealed can located in the spent fuel pool. "In-can" sipping was performed along with "in-mast" sipping :

during RF02 in order to qualify the "in-mast" sipping system. ,

Underwater TV camera inspections of the fuel assemblies were also i performed. Ultrasonic testing (UT) of the suspected failed fuel j assemblies was subsequently performed to identify the location of the !

failed fuel rods. l The results of the sipping and UT inspections revealed a total of nine (9) failed fuel rods located in five (5) fuel assemblies. There were two (2) fuel failures detected in fuel assembly C50, one (1) fuel i failure in assembly C33, one (1) fuel failure in assembly C64, one (1) :

fuel failure in assembly C27, and four (4) fuel failures in assembly t B51.

Visual inspections revealed a debris fretting scar and several secondary r hydride blisters on the failed fuel rod in assembly C33. The top end i plug, along with some attached fuel cladding, was observed to be lodged in the bottom of the top nozzle of assembly C50. Further visual observations from the top of assembly C50 indicated that the top end plug originated from fuel assembly rod location N10. The fuel rod plenum spring, however, appeared to be intact in the failed rod. ;

In addition, what appeared to be a small piece of debris was visually observed to be lodged just below the bottom grid of fuel assembly B21.

UT and sipping inspections did not indicate any fuel failures in this assembly, however. Assembly B21 was discharged as originally scheduled

during this refueling outage No other significant anomalies were observed in the remainder of the l fuel assemblies; however, unusually light colored fuel rod clad surfaces ;

were observed on many of the fuel rods in the outer row of face 1 of fuel assembly B51. This is the face nearest to the four (4) failed fuel rods in the assembly. The failed fuel rods were located adjacent to each other in a 2 X 2 square array in the assembly.

G COMANCHE PEAK UNIT 1 (CPK1) Il ll GENERATION PROFILE AVERAGE DAILY UNIT POWER LEVEL [S G

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JAN. FEB.

1992 FIGURE 1.0

TABLE 1.1 (PAGE 1 0F 2)

ELECTRIC POWER GENERATION DATA (1992) m 2, MONTHLY j h" January February March April MAy n J.u_ns y$

w Hours RX was critical 723.2 696.0 744.0 719.0 719.4 671.6 E RX Reserve Shutdown Hours 20.8 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 700.12 696.0 744.0 719.0 715.0 650.9 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 2,251,260 2,169,396 2,079,346 2,248,606 2,368,550 1,997,702 Gross Elec. Energy Generated (MWH) 750,911 725,402 688,005 749,207 794,804 662,996 Net Elec. Energy Generated (MWH) 718,465 695,388 655,850 716,848 759,931 629,145 RX Service Factor 97.2 100.0 100.0 100.0 96.7 93.3 RX Availability Factor 100.0 100.0 100.0 100.0 96.7 93.3 Unit Service Factor 94.1 100.0 100.0 100.0 96.1 90.4 Unit Availability Factor 94.1 100.0 100.0 100.0 96.1 90.4 Unit Capacity Factor (using MDC net) 84.0 86.9 76.7 86.7 88.8 76.0 Unit Capacity Factor (using OER net) 84.0 86.9 76.7 86.7 88.8 76.0 Unit Forced Outage Rate 5.9 0.0 0.0 0.0 3.9 9.6 Hours in Month 744.0 696.0 744.0 719.0 744.0 720.0 Net MDC (Mwe) estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0

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

TABLE 1.1 (PAGE 2 0F 2)

ELECTRIC POWER GENERATION DATA (1992)

AR MONTHLY "! O cn9-o8 Atly Auaust September October November Decembqt *a Eeo Hours RX was critical 685.2 744.0 720.0 517.2 0.0 163.7 d

RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 255.3 7-0 Hours Generator On-Line 647.5 744.0 720.0 496.7 0.0 116.1 gj Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 2,121,754 2,511,574 2,435,875 1,596,348 0.0 183,422.4 Gross Elec. Energy Generated (MWH) 705,003 839,406 814,036 533,013 0.0 35,384 Net Elec. Energy Generated (MWH) 669,291 803,345 779,666 501,435 0.0 17,448 RX Service Factor 92.1 100.0 100.0 69.4 0.0 22.0 RX Availability Factor 92.1 100.0 100.0 69.4 0.0 56.3 Unit Service Factor 87.0 100.0 100.0 66.7 0.0 15.6 Unit Availability Factor 87.0 100.0 100.0 66.7 0.0 15.6 Unit Capacity Factor (using MDC net) 78.2 93.9 94.2 58.5 0.0 2.0 Unit Capacity Factor (using DER net) 78.2 93.9 94.2 58.5 0.0 2.0 :

Unit Forced Outage Rate 13.0 0.0 0.0 6.2 0.0 9.1 Hours in Month 744.0 744.0 720.0 745.0 720.0 744.0 Net MDC (Mwe) estimated 1150.0 1150.0- 1150.0 1150.0 1150.0 1150.0

Attachment to TXX-93084 Page 9 of 30 TABLE 1.2 ELECTRICAL POWER GENERATION 0ATA 1992 y_EpAR CUMULATIVE Hours RX was critical 7,103.3 15,518.5 RX Reserve Shutdown Hours 276.1 2,258.6 Hours Generator On-Line 6,949.3 15,158.5 Unit Reserve Shutdown Hours 0.0 0.0 Gross Thermal Energy Generated (MWH) 21,963,833 47,295,827 Gross Elec. Energy Generated (MWH) 7,298,167 15,635,165 Net Elec. Energy Generated (MWH) 6,946,812 14,842,376 RX Service Factor 80.9 74.2 RX Availability Factor 84.0 85.0 Unit Service Factor 79.1 72.4 Unit Availability Factor 79.1 72.4 Unit Capacity Factor (using MDC net) 68.8 61.7 Unit Capacity Factor (using OER net) 68.8 61.7 Unit Forced Outage Rate 3.9 7.9 Hours in Reporting Period 8,784 20,921

h TABLE 2.0 (PAGE 1 0F 2)

UNIT SHUTDOWNS AND POWER REDUCTIONS hfff a~

METHOD OF o3

~* "

TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR E8Ei EQt EAIE S: SCHEDULED (HOURS) REASON REDUCING POWER CORRECTIVE ACTIONS / COMMENTS _4 E

1 920108 F 43.88 G 3 Rx/ Turbine Trip due to high Primary Water a temperature, caused by operator error. Unit ej entered MODE 3. LER-92001 was submitted. 2' 2 920204 F 126.9 8 1 Reduced power to troubleshoot and correct Main Feedwater pump "B" excess vibration.

3 920306 S 58.6 B 1 Minor leak repairs on moisture separator reheaters.

4 920320 S 267.0 B 1 Maintenance on Main Feedwater pumps.

5 920401 S 0 B 4 Reduced power to perform maintenance on Main Feedwater pumps.

6 920423 S 0 8 4 Reduced power to perform alignment on Main Feedwater pump A.

7 920508 F 29.0 G 3 Reactor trip caused by personnel error during calibration of nuclear instrumentation. LER-92009 submitted.

8 920603 F 0 D 4 Plant Shutdown initiated due to inoperability of both trains of Control Room HVAC. LER 92012 submitted.

9 920611 F 69.1 A 2 Manual Reactor trip initiated due to loss of feedwater flow. LER 92014 submitted.

10 920720 F 96.5 A 2 Manual Reactor trip initiated due to loss of feedwater flow. LER 92014 submitted.

TABLE 2.0 (PAGE 2 0F 2) mn UNIT SHUTDOWNS AND POWER REDUCTIONS hh h METHOD OF Cf S(g TYPE SHUTTING DOWN u, ,,

F: FORCED DURATION THE REACTOR OR oo HQ. QalE S: SCHEDULED (HOURS) REASON REDUCING POWER CORRECTIVE ACTIONS / COMMENTS ;j

?

11 921012 F 32.9 A 2 The Reactor was manually tripped when Steam g3 Generator No. 4 Feedwater Control Valve failed gg closed. Unit entered MODE 3. LER 92022 submitted. a 12 921014 F 20.8 0 4 Technical Specification restriction to less than 50% RTP by axial flux out of limits.

13 921023 S 215.4 C 1 Refueling outage. Commenced power reduction 0832 22 October. i 14 921101 S 720.0 C 1 Refueling Outage.

15 921201 5 616.3 C 1 Refueling Outage.

16 921230 F 11.6 A 4 A ground in the Turbine Control System was present.

While working in the energized cabinet, a relay picked up and shut the HP stop valves. The operator manually tripped the turbine. The Reactor remained critical.

1) REASON 2) METHOD A: EQUIPMENT FAILURE (EXPLAIN) L: OPERATOR TRAINING AND LICENSE EXAMINATION 1: MANUAL B: MAINT OR TEST F: ADMINISTRATIVE 2: MANUAL SCRAM C: REFUELING G: OPERATION ERROR (EXPLAIN) 3: AUTOMATIC SCRAM D: REGULATORY RESTRICTION H: OTHER (EXPLAIN) 4: OTHER (EXPLAIN)

i Attachment to TXX-93084 Page 12 of 30 i

TABLE 3.0 Personnel Exposure and Monitoring Report i Work & Job Function r Personnel (>100 mrem) Total Man. Rem l Station Utility Contract Station Utility Contract Reactor Operations

& Surveillance Maintenance & Construction 8 0 53 2.481 0.000 17.912 -

Operations 0 0 4 0.629 0.000 1.908 ,

Health Physics & Lab 2 0 5 0.964 0.000 1.397 Supervisory & Office Staff 0 1 0 0.052 0.132 0.035 Engineering Staff 0 0 1 0.055 0.000 0.531 Routine Fiant M.alnlenance Maintenance & Construction 0 0 15 0.128 0.000 5.040 ,

Operations 2 0 4 2.041 0.039 1.409 Health Physics & Lab 0 0 5 0.186 0.000 2.574 Supervisory & Office Staff 0 0 0 0.167 0.010 0.022 ,

Engineering Staff 0 0 3 0.050 0.005 0.655 inserace inspecton Malntenance & Construction 1 0 37 1.573 0.000 13.429 Operations 0 0 4 1.800 0.039 1.841 Heam Physics & Lab 1 0 8 0.645 0.000 3.534 Supervisory & Office Staff 0 0 0 0.133 0.000 0.039 Engineering Staff 0 0 1 0.118 0.005 0.733 5pec:al Plant Maintenance Maintenance & Construction 6 0 66 2.238 0.000 20.941 Operations 1 0 7 2.139 0.039 3.192 y Health Phytk:s & Lab 5 0 17 1.720 0.000 7.603 Supervisory & Of5cs Staff 0 0 0 0.200 0.000 0.039 Engineering Staff 0 0 1 0.164 0.005 0.645 Waste Processing Maintenance & Construction 5 0 105 2.269 0.000 36.869 Operations 1 0 10 2.088 0.039 3.566 Health Physics f. Lab 5 0 16 2.628 0.000 5.577 Supervisory & Of5ce Staff 0 0 0 0.167 0.000 0.039 Engineering Staff 0 0 3 0.170 0.000 1.066 Refueling Maintenance & Construction 1 0 19 0.646 0.000 12.111

Operations 1 0 2 1.014 0.039 1.001 Health Phycles & Lab 0 0 5 0.352 0.000 2.506 Supervisory & Off'.ca Staff 0 0 0 0.092 0.000 0.018 Engineerino Staff 0 0 0 0.093 0.005 0.281 Tolais Maintenance & Construction 32 0 282 9.335 0.000 106.302 Operations 35 1 24 9.711 0.195 12,917 Health Physics & Lab 16 0 76 6.495 0.000 23.191 Supervisory & Office Staff 1 1 0 0.811 0.142 0.192 Engineering Staff 1 0 8 0.650 0.020 3.911 ,

Grand Tota!s 85 2 390 27.002 0.357 146.513

i

t Attachment to TXX-93084 >

Page 13 Of 30 TABLE 4.1A (Page 1 Of 2)

CORE HISTORY D'ATA BASE - SHIFT LOG DATA Unit: 1 Cycle: 02 Period from: 071892 0 0100 to: 072092 0 1600 CBD Core Burnup Date Time Power Avg)AO EFPD

(%) (steps) (% mwd /MTU 0100 99.8 220 -2.89 7365.7 192.3 ,

07/18 100.0 220 -2.82 7367.3 192.4 07/18 0200 7368.9 192.4 07/18 0300 99.8 219 -2.94 0400 99.9 219 -2.89 7370.5 192.5 07/18 219 -2.93 7372.1 192.5 ;

07/18 0500 99.9 7373.7 192.5 0600 99.9 219 -2.99 i 07/18 219 -3.02 7375.3 192.6 07/18 0700 99.9 7376.9 192.6 0800 99.9 219 -3.05 07/18 219 -3.22 7378.5 192.7 07/18 0900 99.8 7380.0 192.7 1000 99.7 219 -3.33 07/18 220 -3.26 7381.6 192.8 07/18 1100 99.9 7383.2 192.8 1200 100.1 220 -3.25 07/18 220 -3.34 7384.8 192.8 07/18 1300 100.0 7386.4 192.9 1400 100.0 220 -3.38 07/18 220 -3.41 7388.0 192.9 07/18 1500 100.1 7389.6 193.0 a

1600 100.0 221 -3.35 07/18 221 -3.22 7391.2 193.0 07/18 1700 100.1 7392.8 193.0 1800 100.1 221 -3.17 07/18 221 -3.03 7394.4 193.1 07/18 1900 100.0 7396.0 193.1 2000 99.8 221 -2.91 07/18 220 -2.85 7397.6 193.2 !

07/18 2100 99.8 7399.2 193.2 2200 99.6 219 -2.91 07/18 219 -2.83 7400.8 193.3 07/18 2300 99.8 7402.4 193.3 07/18 2400 99.7 219 -2.84 0100 99.8 219 -2.77 7404.0 193.3 07/19 219 -2.77 7405.5 193.4 07/19 0200 99.6 7407.1 193.4 07/19 0300 99.7 219 -2.82 0400 99.7 219 '2.90

- 7408.7 193.5 07/19 99.5 219 -2.97 7410.3 193.5 !

07/19 0500 219 -3.02 7411.9 193.5 07/19 0600 99.7 193.6 0700 99.5 219 -3.15 7413.5 07/19 219 -3.21 7415.1 193.6 07/19 0800 99.8 7416.7 193.7 ,

07/19 0900 99.5 219 -3.38 i

1000 99.8 220 -3.38 7418.3 193.7 1 07/19 99.9 220 -3.47 7419.9 193.8 4 07/19 1100 220 -3.45 7421.5 193.8 07/19 1200 99.8 193.8 1300 99.8 220 -3.51 7423.0 07/19 220 -3.46 7424.6 193.9 i 07/19 1400 99.7 193.9 i 1500 99.8 220 -3.47 7426.2 07/19 99.7 220 -3.34 7427.8 194.0 4

07/19 1600 99.8 220 -3.25 7429.4 194.0 l 07/19 1700 220 -3.03 7431.0 194.0 07/19 1800 100.0 194.1 1900 99.8 220 -2.93 7432.6 1 07/19 220 -2.70 7434.2 194.1 ,

07/19 2000 99.8 194.2 2100 99.7 220 -2.56 7435.8 07/19 99.7 219 -2.46 7437.4 194.2 07/19 2200 99.5 218 -2.56 7439.0 194.3 07/19 2300 194.3 99.4 218 -2.59 7440.5 07/19 2400 218 -2.55 7442.1 194.3 07/20 0100 99.5 7443.7 194.4 07/20 0200 99.4 218 -2.63 0300 99.5 218 -2.86 7445.3 194.4 07/20 218 -3.10 7446.9 194.5 )

07/20 0400 99.7 194.5 0500 99.8 219 -3.21 7448.5 !

07/20 99.9 220 -3.25 7450.1 194.5 07/20 0600 194.6 0700 100.1 222 -3.12 7451.7 07/20 222 -3.08 7453.3 194.6 j 07/20 0800 99.9 194.7 0900 99.8 222 -3.06 7454.9 :

07/20 99.8 222 -2.99 7456.5 194.7 07/20 1000 222 -2.92 7458.1 194.7 07/20 1100 99.8 194.8 1200 99.8 221 -3.07 7459.6 07/20 I

Attachment to TXX-93084 Page 14 of 30 TABLE 4.1A (Page 2 of 2)

CORE HISTORY DhTA BASE - SHIFT LOG DATA

Unit: 1 Cycle: 02 Period from: 071892 @ 0100 to: 072092 9 1600 CBD Avg AO Core Burnup Date Time Power mwd /MTU EFPD

(%) (steps) (%)

221 -3.07 7461.2 194.8 07/20 1300 99.9

-3.02 7462.8 194.9 07/20 1400 99.7 221 221 -2.88 7464.4 194.9 07/20 1500 99.8

-2.82 7466.0 195.0 07/20 1600 99.2 221 07/20 lbOZ $ PWick *Tf/P I

{

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Comanche Peak Steam Electric Station [$

Unit 1, Cycle 2 Hourly Power Levels y Prior to Reactor Trip on 7/20/92 @ 1600 o.,3

-n EG Power (%RTP) =

y 102 8 8a 101 - -- -

100 A -

99 -

90 -

97 -

96 7/18 7/19 7/20 Date (Starting at 0000 hours0 days 0 hours 0 weeks 0 months )

Reactor Power FIGURE 4.1A From Core IIistory Data Base 4

, 2- - . , - - . , , , - . . . . ., , .._r ,.,-,-c , , . , ,,,..,-m._.. m. -.y. . - - .-,.. ~ ..-...,,,r. . . , , .,- , .. +.w .m ,. < - - . , , . . . . . -

4 EN NC o TABLE 4.18 O '3

^"

RADIO 10 DINE ISOTOPIC ANALYSES Wg g

CPSES UNIT ONE, HEACTOR TRIP 20 JUL 92 d

x 07/21/92 07/22/92 07/23/92 e 07/21/92 07/21/92 DATE 07/20/92 07/20/92 07/20/92 07/21/92 07/21/92 725 1035 1325 745 805 8 >

TIME 735 1802 2120 40 400 0 0 0 0 0 @

0 0 0 72 ;

100 0 70 70 70

% POWER 70 70 72 LETDOWN 6.770E-01 1.810E-01 4.420E-02 9.230E-01 9.090E-01 7.910E-01 8.740E-01 8.720E-01 9.660E-02 6.990E-02 l-131 1.310E-02 8.450E-01 2.650E-01 2.170E-01 1,720E-01 1.610E-01 5.340E-01 3.840E-01 2.930E-01 4.020E-01 6.330E-02 7.380E-03 1-132 1.320E-02 6.500E-01 5.060E-01 8.120E-01 6.090E-01 7.240E-01 7.410E-01 1-133 1.710E-02 2.020E-02 1.640E-01 1.670E-02 1.040E-01 6.430E-02 2.810E-03 .

1-134 2.790E-01 2.130E-01 1.630E-01 1.620E-02 4.920E-01 3.950E-01 1-135

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

to TXX-93084 Page 17 of 30 Table 4.1C CLEAN UP FLOW HISTORY CPSES Unit 1 Reactor Trip, July 20, 1992 LETDOWN DATE TIME FLOW C0 K NTS 07/18/92 0830 69 07/19/92 0830 70 07/20/92 1200 No Entry CVCS Demineralizers taken out of service for maintenance.

07/20/92 1600 No Entry Reactor trip (approxinate time). l 07/20/92 0735 70 07/20/92 1100 70 07/20/92 2120 72 07/21/92 0725 70 CVCS Demineralizers placed back in service.

07/21/92 1035 70 DEI returned to less than 1.0 uCi/gm.

07/21/92 1325 70 07/22/92 0745 70 07/22/92 2140 72 07/22/92 2340 72 07/23/92 0215 70 ,

07/23/92 0808 72 07/23/92 1140 70 07/23/92 2330 70 07/24/92 0730 70 07/25/92 0903 70 07/26/92 0750 70 l

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. Attachment to TXX-93084 i Page 19 of 30 I.

TABLE 4.2A CORE HISTORY DATA BASE - SHIFT LOG DATA l Unit: 1 Cycle: 02 Period from: 101092 0 0100 to: 101292 9 1300 Date Time Power CBD Avg AO Core Burnup

(%) (steps) (%) mwd /MTU EFPD ,

10/10 0100 99.6 217 -3.51 10373.8 270.9 10/10 0200 99.8 217 -3.85 10375.4 270.9 10/10 0300 99.7 217 -3.97 10377.0 271.0 10/10 0400 99.8 218 -4.06 10378.6 271.0 10/10 0500 99.8 218 -4.15 10380.2 271.0 10/10 0600 99.8 218 -4.14 10381.8 271.1 ;

10/10 0700 99.8 218 -4.24 10383.4 271.1 10/10 0800 99.8 218 -4.28 10385.0 271.2 10/10 0900 99.7 218 -4.33 10386.6 271.2 '

10/10 1000 99.7 218 -4.40 10388.2 271.3 10/10 1100 99.8 218 -4.38 10389.8 271.3

10/10 1200 99.7 218 -4.45 10391.3 271'.3 10/10 1300 99.7 218 -4.46 10392.9 271.4 :

10/10 1400 99.7 218 -4.43 10394.5 271.4 10/10 1500 99.6 218 -4.38 10396.1 271.5

10/10 1600 99.8 218 -4.29 10397.7 271.5 ,

10/10 1700 99.4 218 -3.83 10399.3 271.5 10/10 1800 99.5 218 -3.62 10400.9 271.6 10/10 1900 99.5 218 -3.60 10402.5 271.6 10/10 2000 99.7 218 -3.55 10404.1 271.7 10/10 2100 99.9 218 -3.35 10405.7 271.7 10/10 2200 99.7 218 -3.52 10407.3 271.8 10/10 2300 100.0 218 -3.68 10408.8 271.8 10/10 2400 100.1 218 -3.84 10410.4 271.8 10/11 0100 100.2 219 -3.84 10412.0 271.9 10/11 0200 100.0 219 -4.02 10413.6 271.9 272.0 !

10/11 0300 100.0 219 -4.15 10415.2 10/11 0400 100.0 219 -4.11 10416.3 272.0 ;

10/11 0500 99.8 219 -4.18 10418.4 272.0 10/11 0600 100.0 219 -4.17 10420.0 272.1 10/11 0700 99.8 219 ~4.18 10421.6 272.1 10/11 0800 99.8 219 -4.22 10423.2 272.2 10/11 0900 99.9 219 -4.24 10424.8 272.2 ,

10/11 1000 99.9 219 -4.22 10426.4 272.3 10/11 1100 99.9 219 -4.18 10428.0 272.3 7 10/11 1200 100.0 219 -4.17 10429.6 272.3 i 10/11 1300 100.0 219 -4.12 10431.2 272.4 10/11 1400 99.9 219 -4.09 10432.8 272.4 ,

10/11 1500 100.0 218 -4.24 10434.4 272.5 10/11 1600 100.1 218 -4.22 10436.0 272.5 10/11 1700 99.9 218 -4.32 10437.6 272.5 10/11 1800 100.0 218 -4.36 10439.2 272.6 10/11 1900 99.8 218 -4.31 10440.7 272.6 10/11 2000 99.6 218 -4.26 10442.3 272.7 i 10/11 2100 99.7 218 -4.25 10443.9 272.7 10/11 2200 99.8 218 -4.24 10445.5 272.8 ,

10/11 2300 99.8 218 -4.12 10447.1 272.8 .

10/11 2400 99.8 218 -3.98 10448.7 272.8 10/12 0100 99.8 218 -4.05 10450.3 272.9 10/12 0200 99.8 218 -3.87 10451.9 272.9 10/12 0300 99.8 218 -3.77 10453.5 273.0 10/12 0400 99.9 218 -3.73 10455.1 273.0 >

10/12 0500 99.9 218 -3.68 10456.7 273.0 10/12 0600 99.8 218 -3.89 10458.3 273.1 10/12 0700 99.7 218 -3.91 10459.8 273.1 10/12 0800 99.9 218 -3.99 10461.4 273.2 10/12 0900 99.8 218 -4.13 10463.0 273.2 '

10/12 1000 99.8 218 -4.27 10464.6 273.3 '

10/12 1100 99.9 218 -4.30 10466.2 273.3 10/12 1200 99.7 218 -4.35 10467.8 273.3 i

i Attachment to TXX-93084 ,

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to TXX-93084 Page 23 of 30 Table 4.2C CLEAN UP FLOW HISTORY CPSES Unit 1 Reactor Trip, October 12, 1992 LETDOWN !

DATE TIME FLOW 10/09/92 0400 73 10/10/92 0800 73 10/11/92 0400 73 10/12/92 0400 73 10/13/92 0400 72 10/14/92 0400 72 I

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i Attachment to TXX-93084 Page 25 Of 30 TABLE 4.3A ,

(Page 1 of 2) l!

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CORE HISTORY DATA BASE - SHIFT LOG DATA Unit: 1 Cycle: 02 Period from: 102192 0 0100 to: 102392 0 2400 Date Time Power CBD Core Burnup (steps) Avg)AO

(% mwd /MTU EFPD

(%) .

r 0100 99.8 219 -3.91 10711.3 279.7 10/21 218 -3.97 10712.9 279.7 ;

10/21 0200 99.9 '

0300 99.8 218 -4.06 10714.5 279.8 10/21 218 -4.10 10716.0 279.8 10/21 0400 99.7 99.8 218 -4.12 10717.6 279.9 10/21 0500 218 -4.08 10719.2 279.9 10/21 0600 100.0 0700 100.0 218 -4.15 10720.8 279.9 -

i 10/21 218 -4.21 10722.4 280.0 10/21 0800 99.8 10724.0 280.0 10/21 0900 99.9 218 -4.22 1000 99.9 218 -4.19 10725.6 280.1 10/21 218 -4.21 10727.2 280.1 10/21 1100 99.9 99.8 218 -4.31 10728.8 280.2 10/21 1200 218 -4.34 10730.4 280.2 10/21 1300 99.8 99.7 218 -4.38 10732.0 280.2 -

10/21 1400 218 -4.39 10733.6 280.3 -

10/21 1500 99.9 '

99.8 218 -4.36 10735.2 280.3 10/21 1600 218 -4.31 10736.8 280.4 10/21 1700 99.8 1800 99.8 218 -4.28 10738.3 280.4 10/21 218 -4.24 10739.9 280.4 10/21 1900 99.7 280.5 2000 100.1 218 -4.21 10741.5 10/21 218 ~4.33 10743.1 280.5 10/21 2100 100.3 280.6 2200 100.1 218 -4.34 10744.7 10/21 218 -4.34 10746.3 280.6 10/21 2300 100.1 10747.9 280.7 10/21 2400 100.1 218 -4.30 0100 100.1 218 -4.32 10749.5 280.7 10/22 218 -4.29 10751.1 280.7 10/22 0200 100.1 !

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10/22 100.1 218 -3.98 10760.7 281.0 10/22 0800 100.1 216 -3.35 10762.3 281.0 10/22 0900 98.4 208 -3.35 10763.8 281.1 10/22 1000 93.4

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10/22 1200 81.2 189 -3.23 10766.5 281.1 10/22 1300 73.9 177 -3.21 10767.6 281.2 10/22 1400 67.3 165 -2.92 10768.7 281.2 10/22 1500 60.3 145 -4.01 10769.7 281.2 1600 52.8 127 -1.39 10770.5 281.2 i 10/22 124 6.38 10771.3 281.3 10/22 1700 46.1 10/22 1800 39.3 109 18.68 10771.9 281.3 1900 39.0 109 27.78 1C772.5 281.3 10/22 103 35.42 10773.2 281.3 10/22 2000 44.9 -

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I Attachment to TXX-93084 Page 26 Of 30 TABLE 4.3A (Page 2 Of 2)

^

CORE HISTORY DATA BASE - SHIFT LOG DATA l Unit: 1 Cycle: 02 Period from: 102192 @ 0100 to: 102392 9 2400 i Time Power CBD Avg AO Core Burnup Date EFFD

(%) (steps) (%) mwd /MTU l 8 -1.14 10775.5 281.4 10/23 1300 .0 10775.5 281.4 f 1400 .0 8 1.46 10/23 .0 0 2.75 10775.5 281.4 10/23 1500 0 -47.05 10775.5 281.4 10/23 1600 .0 10775.5 281.4 1700 .0 0 .00 i 10/23 0 .00 10775.5 281.4 l 10/23 1800 .0 281.4 1900 .0 0 .00 10775.5 10/23 0 .00 10775.5 281.4 i 10/23 2000 .0 281.4 2100 .0 0 .00 10775.5 ;

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CPSES UNIT ONE, RFO-2 SHUTDOWN gg cx DATE 10/23/92 10/23/92 10/23/92 10/23/92 10/23/92 10/23/92 a TIME 445 1100 1352 1630 2030 2230 $

% POWER 2 2 0 0 0 0 $

LETDOWN 72 72 72 70 73 73 1-131 3.800E-02 9.020E-01 8.630E-01 8.730E-01 7.550E-01 8.180E-01 1-132 5.470E-03 1.240E-01 1.040E-01 9.690E-02 8.350E-02 9.060E-02 1-133 4.290E-02 7.380E-01 6.590E-01 6.080E-01 4.870E-01 4.900E-01 1-134 6.060E-03 l-135 1.600E-02 1.830E-01 1.240E-01 9.390E-02 6.330E-02 5.170E-02 DEI 5.112E-02 1.121 E+00 1.055E+00 1.049E+00 8.948E-01 9.579E-01

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Attachment 1 to TXX-93084 Page 29 of 30 Table 4.3C CLEAN UP FLOW HISTORY CPSES Unit 1, RFO-2 Shutdown LETDOWN DATE TIME FLOW 10/21/92 0200 72 10/22/92 0950 72 10/22/92 1610 72 10/23/92 2230 73

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