ML20203K901

From kanterella
Jump to navigation Jump to search
CPSES Annual Operating Rept for 1997
ML20203K901
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 12/31/1997
From: Terry C, Walker R
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-98044, NUDOCS 9803050271
Download: ML20203K901 (20)
v • d • e


Text

i j

Famm -

FE Log # TXX 98044 File # 10250 r

=

Ref. # 10CFR50.36 1UELECTRIC February 27, 1998

c. u.c. Thrry Senior Mce President

& PrincipnlNuclear Offleer U. S. Nuclear Regulatory Connission Attention: Gocument Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) UNITS 1 AND 2 DOCKET NOS 50 445 AND 50 446 ANNUAL OPERATING RE90FJ FOR 1997 Gentlemen:

Attached is the CPSES Annual Operating Report for 1997 prepared and submitted pursuant to Technical Specification 6.9.1.2 contained in Appendix A to the Comanche Peak Steam Electric Station Unit 1 Operating License NPF 87 and Unit 2 Operating License NPF 89.

This attachment also complies witn the emual operating report guidance provided in position C.1.0 of U.S. NRC Regult. tory Guide 1.16 Revision 4.

If you have any questions, please tantact Mr. Douglas W. Snow at (254) 897 8448, 4

Sincerely, e 2. G s C. L. Terry By:

  1. 1 Roger D( W31ker Regulatory Affairs Manager DWS/dws Attachment

_,y c-Mr. E. W. herschoff. Region IV

/ l'~

l 1

Mr. J. I. Tapia. Region IV vVAU

}

u

.s Mr. T. J. Polich. NRR Resident Inspector. CPSES Hs M. L. Thomas. REIRS Project ManagerO'/ Original copy of the Partannel Exposure & Monitoring report) 9003050271 971231 PDR ADOCK 05000445 COMANCHE PEAK STEAM ELECTRIC STATION c.

P.O. E e n 1002 Glen Rose. Texas 7(6 0-1002 1

Attachme:t to TXX-98044 Page 1 of 19 L

L COMANCHE PEAK STEAM El.ECTRIC STATION ANNUAL OPERATING REPORT 1997 TEXAS UTILITIES ELECTRIC COMPANY L

i l

Attchme:t 13 TXX-98044 l

Page 2 of,19 TABLE OF CONTENTS 1.0 Sunmary of Operating Experience 2.0 Outages and Reductions in Power 3.0 Persor.nel 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 5.0 Irradiated Fuel Inspection Results 6.0 Outage Ret

?d Single Radioactivity Release or Radiation Exposure 1.0 an Individual that Accounts for More than 10 Percent of Allowable Annual Values

[

Att:chment ta TXX 98044 f

Page 3 c,19 1.0 EttiRY OF OPERATING EXPERIENCE The Comanche Peak Steam Electric Station (CPSES) is a dual unit pressurized water reactor power plant. each unit licensed at 3411 Megawatt thermal (MWt).

It is located in Somervell County in North Central Texas approximately 65 miles southwest of the Dallas Fort Worth Metropolitan ara. The nuclear steam supply system was purchased from Westinghouse Electric Corporation and is rated for a 3425 MWt output per each unit.

1.1 CP',ES UilT 1 CPSES Unit 1 achievt.d initial criticality on April 3.1990. Initial power generation occurred en April 24. 1990, and the plant was declared comercial on August 13, 1990. Since being declared comercial. CPSES Unit 1 has generated 56.402.312 net Megawatt hours (MWH) of electricity as of December 31. 1997, with a net unit capacity factor of 75.8% (using HDC). The unit and reactor availability factors were 98.8% and 99.3%. respectively, for the year 1997.

During this reporting period there were no failures or challenges to the Power Operated Relief Valves or Safety Valves.

Figure 1.1-l'provides the generation profile of the average daily net electrical output of Unit 1 for 1997. Table 1.11 is a compilation of the monthly sumaries of the operating data and Table 1.12 contains the yearly and total sumaries o' the operating data.

1.2 CPSES UNIT 2 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 33,290.781 net Megawatt hours (HWH) of electricity as of December 31. 1997, with a net unit capacity factor of 74.8% (using K)C). The unit and reactor availability factors were 86.2% and 88.05. respectively, for the year 1997.

On January 4. the unit entered a planned maintenance outage to repair an oil leak to the capacitance coupled voltage transformer (CCVT). The repairs o.7 the CCVT were completed :.d the unit returned to 100% power on January 10. The following work was also completed successfully in this maintenance outage:

Replaced the #2 oil cooler to the Main Transformer 2MT2 Rod Drop Testing Inspection & Replacement of the Heater Drain Pump 2 02 shaft Solenoid replacement for the main feedwater (FW) isolation valve hydraulic pumps Main FW pump 2 A bearing inspections and alignment On October 22. 1997 the unit began the end of cycle power ramp down for its third refueling outage. The unit entered the refueling outage on October 25 when a manual reactor trip was initiatsi after four control rods unexpectedly inserted during ramp down. Additionally. the Power Relief Valves opened after the unit was cooled down to the Low Temperature Overpressure Protection (LTOP) arming temperature (35'1) with pressure above LTOP setpoint.

During the refueling outage. 76 new fuel assemblies were loaded for Cycle 4. The y

s _ _ _ _ _ _ _ _ _ -__.

Att:chme:t 12 TXX-98044 Page 4 of,19 Overprossure Protection (LTOP) arming temperature (350) with pressure above LTOP setpoint.

During the refueling outage. 76 new fuel assemblies were loaded for Cycle 4.

The refueling outage lasted 46 days and ended on December 10, 1997 and Unit 2 was returned to service.

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

)

Containment Integrated Leak Rate Testing Emergency Diesel Generator 18 month Inspection e

e Emergency Diesel Generator five (5) year Inspection Emergency Diesel Generators Turbo Overhaul e

Low Pressure Turbine 1 and 2 Eddy Current Testing of Last Stage e

Blades e

1004 Eddy Current Testing on Two Steae Generators 40% Eddy Current Testing on the rema'ining Two Steam Generators e

Installation of Woodward 701 Governor Systerc on Diesel e

Generators Inspection of Fuel Assablies e

Reactor Coolant Pump Cartridge Seal Changeout on Pumps 01 & 04 TDAFW Pump Turbine tear down e

Tear down Inspection on the 2A & 2B Hain Feedwater Pumps and e

turbines.

)

Figure 1.21 provides the generation profile of the average daily net electrical output of Unit 2 for 1997. Table 1.2-1 is a compilation of the monthly summaries of the operating data and Table 1.2 2 contains the. 'arly and the total summaries of the operating data.

2.0 CUTAGES AND REDUCTIONS IN POWER 2.1 CPSES UNIT 1 Table 2.1 describes unit operating expcience including unit shutdowns and provides explanations of significant dips in average power levels for 0/SES Unit 1.

2.2 CPSES UNIT 2 Table 2.2 describes unit operating experience inclunng unit shutdowns ard provides explanations of significant dips in average power levels for CPSES Unit 2.

3.0 PERSONNEL EXPOSURE AND MONITORING REPORT The personnel exposure and monitoring report for CPSES is provided in Table 3.0.

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

Att:chmnt to TXX 98044 l

Pcge 5 cf19 k

CPSES Units 1 and 2 primary coolant did not exceed the limits of Technical Specification 3.4.7 for the calendar year 1997.

(

5.0 IRRADIATED FUEL INSDECTION RESULTS 5.1 CPSES UNIT 1 No irradiated fuel inspections were performed since there was no refueling outage for Unit 1 in 1997.

5.2 CPSES UNIT 2 The reactor coolant fission product activity levels were carefully monitored througnout Cycle 3 omration. Analysis of the activity levels indicated no leaking fuel. Nonet1eless, visual inspections were performed by inspection personnel from the edge of the spent fuel pool to assess the external condition of the fuel assemblies. In addition, selected Cycle 3 assemblies (which indicated varying degrees of the Axial Offset Anomaly (A0A) from flux map results) were also inspected using an underwater camera. All fuel assemblies inspected appeared to be in good condition, including tnose with indications of A0A.

6.0 OUTAGE RELATED SINGLE RADI0 ACTIVITY RELEASE OR RADIAIION EXPOSURE TO AN INDIVIDUAL THAT ACCOUNTS FOR MORE THAN 10 PERCENT OF ALLOWABLE ANNUAL V% LUES CPSES Units 1 and 2 did not experience any single release of radioactivity p eater inan 10% of an allowable dose-limit during an outage or forced reduction in power of over 20% of designed power level during 1997.

During.1997 CPSES Unit 2 conducted a refueling outage (see section 1.2).

During the outage activities, one individual received radiation exposure exceeding 10% of an allowable dose limit in a single exposure event. This exposure is tabulated in Table 6.0.

1 a

Attachment to TXX-98044 Page 6 of 19 FIGURE 1.1-1 C0 HANG 1E FEAK STEAM ELECTRIC STATION - UNIT 1 GENERATION PROFILE AVERAGE DAILY UNIT POWER LEVEL 1200 YY f

I y

~ j y

~

800 h

600 400 200 0-JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC Actual

TABLE 1.1.1 (PAGE 1 0F 2)

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 HONTHLY ELECTRIC POWER GENERATION DATA (1997)

January February tiarch Apr11 liay June Hours RX was Critical 744 672 744 719 744 720 RX Reserve Shutdown Hours 0

0 0.0 0.0 0.0 0.0 Hours Gererator On-Line 744 672 744 719 744 720 Unit keserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (HWH) 2.530.063 2.278.471 2.529.482 2.454.782 2.531.275 2.450.993 Gross Electric Energy Generated (HWH) 858.760 774.167 859.801 833.050 857.168 822.932 Net Electric Energy Generated (HWH) 825.342 744.210 826.276 800.088 822.320 788.772 RX Service Factor (t) 100.0 100.0 100.0 100.0 100.0 100.0 RX Availability Factor (t) 100.0 100.0 100.0 100.0 100.0 100.0 Unit Service Factor (t) 100.0 100.0 100.0 100.0 100.0 100.0 Unit Availability Factor (2) 100.0 100.0 100.0 100.0 100.0 100.0 Unit Capacity Factor (t. using HDC net) 96.5 96.3 96.6 96.8 96.1 95.3 Unit Capacity Factor (t. using DER net) 96.5 96.3 96.6 96.8

%.1 95.3 Unit Forced Outage Rate (t) 0.0 0.0 0.0 0.0 0.0 0.0 Hours in Month 744 672 744 719 744 720 Net HOC (HWe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0 i

e,

Att:chmert 13 TXX-98044 P;ge 8 of 19 TABLE 1.1-1 (PAGE 2 0F 2)

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 HONTHLY ELECTRIC POWER GENERATION DATA (1997) hly Aucust September October Rovember December Hours RX was Critical 744 744

/20 669 720 727 RX Reserve Shutdown Hours 0.0 0.0 0.0 28 0.0 0.0 Hours Generator On-Line 744 744 720 661 720 724 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (HWH) 2.536.073 2.531.964 2.449.639 2.196.888 2.452.982 2.387.719 Gross Electric Energy Generated (HWH) 844.106 841.507 817.512 737.744 830.714 805.949 Net Electric Energy Generated (HWH) 808.774 806.219 783.498 702.946 797.808 772.630 RX Service Factor (t) 100.0 100.0 100.0 89.7 100.0 97.8 RX Availability Factor (2) 100.0 100.0 100.0 93.5 100.0 97.8 Unit Service Factor (t) 100.0 100.0 100.0 88.8 100.0 97.3 Unit Availability Factor (t) 100.0 100.0 100.0 88.8 100.0 97.3 Unit Capacity Factor (f. using HDC net) 94.5 94.2 94.6 82.0 96.4 90.3 Unit Capacity Factor (t using DER net) 94.5 94.2 94.6 82.0

%.4 90.3 Unit Forced Outege Rate (*)

0.0 0.0 0.0 11.2 0.0 2.7 Hours in Month 744 744 720 745 720 744 Net HDC (Hwe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0

Att:chmnt t)TXX-98044 P ge 9 of19 TABLE 1.1 2 C0HANCHE PEAK STEAM ELECTRIC STATION UNIT 1 ANNUAL ELECTRIC POWER GENERATION DATA (1997)

YEAR CUMULATIVE Hours RX was Critical 8,667 54,761 RX Reserve Shutdown Hours 28 2,632 Hours Generator On Line 8,657 54,110 Unit Reserve !.6down Hours 0

0 Gross Thersel Energy Generated (HWH) 29,330,333 176,779,784 Gross Electric Energy Generated (HWH) 9,883,430 59,071.960 Net Electric Energy Generated (HWH) 9,4/8,883 56,402,312 RX Service Factor (%)

98.9 84.6 RX Availability Factor (*)

99.3 88.6

~

'Mit Service Factor (*)

98.8 83.6 Unit Availability Factor (%)

98.8 83.6 Unit Capacity F6ctor (*,using HDC net) 94.1 75.8 Unit Capacity Factor (%,using DER net) 94.1 75.8 Unit Forced Outage Rate (t) 1.2 4.2 Hours in Reporting Period 8,667 64,552 4-

Attechment to TXX-98044 Page 10 of 19 FIGURE 1.2-1 COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 GENERATION PROFILE AVERAGE DAILY UNIT POWER LEVEL 1200 r

9 r

I 1000 800 h

600 400 i

200 0

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

)

Actual m

o-Att chmert 13TXX 98044 Pcge 1I of 19 TABLE 1.2-1 (PAGE 1 0F 2)

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 2 MUNTHLY ELECTRIC PCWER GENERATION DATA (1997)

January February liacch April tidy June Hours RX was Critical 662 672 744 719 744 720 RX Reserve Shutdown ilours 82 0.0 0.0 0.0 0.0 0.0 Hours Generator On Line 641 672 744 719 744 720 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy Generated (MWH) 2.118.763 2.281.114 2.536.639 2.450.050 2.144.436 2.368.586 Gross Electric Energy Generated (MWH) 722.129 780.163 868.282 837.235 721.890 798.349 Net Electric Energy Generated (MWH) 690.736 751.577 835.763 805.278 689.326 766.191 RX Service Factor (t) 88.9 100.0 100.0 100.0 100.0 1)0.0 RX Availability Factor (%)

100.0 100.0 100.0 100.0 100.0 100.0 86.2' 100.0 100.0 100.0 100.0 100.0 Unit Service Factor (t)

Unit Availability Factor (*)

86.2 100.0 100.0 100.0 100.0 100.0 Unit Capacity Factor (%. using MDC net) 80.7 97.3 97.7 97.4 80 6 92.5 Unit Capacity Factor (1. using DER net) 80.7 97.3 97.7 97.4 80.6 92.5 Unit Forced Outage Rate (t) 0.0 0.0 0.0 0.0 0.0 0.0 Hours in Month 744 672 744 719 744 720 Net MDC (HWe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0

Attrchmest is TXX-98044 Pcge 12 of 19 TABLE 1.2-1 (PArf 2 0F 2)

COMANCHE PEAK STEAM ELEC %IC STATION - UNIT 2 MONTHLY ELECTRIC POWER GENERATION DATA (1997)

July August September.

October November December

^

Hours RX was Critical 744 744 720 580 0

574 RX Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Hours Generator On-Line 744 744 720 580 0

526 Unit Reserve Shutdown Hours 0.0 0.0 0.0 0.0 0.0 0.0 Gross Thermal Energy' Generated (HWH) 2.530.620 2.536.238 2.451.499 1.958.441 0

1.445.873 Gross Electric Energy Generated (HWH) 849.412 850.680 826.109 664.015 0

490.948 Net Electric Energy Generated (HWH) 816.149 817.440 793.814 635.988 0

459.788 RX Service Factor (t) 100.0 100.0 100.0 77.9 0.0 77.2 RX Availability Factor (t) 100.0 100.0 100.0 77.9 0.0 77.2 Unit Service Factor (t) 100.0 100.0 100.0.

77.9 0.0 70.7 Availability Factor (t) 100.0 100.0 100.0 77.9 0.0 70.7 Unit Capacity Factor (% using HDC net) 95.4 95.5 95.9 74.2 0

53.7 Unit Capacity Factor (%. using DER net) 95.4 95.5 95.9 74.2 0

53.7 Unit Forced Datage Rate (t) 0.0 0.0 0.0 0.0 0.0 0.0 Hours in Month 744 744 720 745 720 744 Net HDC (Hwe) Estimated 1150.0 1150.0 1150.0 1150.0 1150.0 1150.0

l'*

Attachme:t ts TXX-98044 l

Page 13 of 19, TABLE 1.2 2 COMANCHE PEAK STEAM ELECTRIC STATION UNIT 2 ANNUAL ELECTRIC POWER GENERATION DATA (1997)

XEAR C MILATIVE Hours RX was Critical 7,623 32,104 RX Reserve Shutdown Hours 82 2,311 Hours Generator On Line 7,554 31,788 Unit Reserve Shutdown Hours 0

0 Gross Thermal Energy Generated (MWH) 24,822,259 103,105,886 Gross Electric Energy Generated (MWH) 8,409,212 34,801,312 Net Electric Energy Generated (MWH) 8,062,050 33,290,751 RX Service Factor (t) 87.0 83.0 RX Availability Factor (t) 88.0 89.0 1

Unit Service Factor (t) 86.2 82.2 Unit Availability Factor (t) 86.2 82.2 Unit Capacity Factor (t using MDC net) 80.0 74.8 Unit Capacity Factor (t, using DER net) 80.0 74.8 Unit Forced Outage Rate (t) 0.0 5.8 Hours in Reporting Period 7,623 37.543 l

Attrchmext ta TXX-98044 Page 14 of 19 TABLE 2.1 (PAGE 1 0F 1)

COMANCHE PEAK STEAM ELECTRIC STATION - UNIT 1 UNIT OPERATING EXPERIENCE INCLUDING SHUTDOWNS AND P0kfR REDUCTIONS' ETHOD OF TYPE SHUTTING DOWN F: FORCED DURATION

  • THE REACTOR OR NO DAIE S: SCHEDULED (HOURS)

REASON REDJCING EQWER CORRECTIVE ACTIONS /COMENTS i

1 971027 F

83.6 G

3 Automatic Rei.ctor trip after switchyard breaker tripped and removed the load frca the generator. Prior to returning to power a source range detector malfunctioned and was replaced. The Unit was returned to 100* power on October 31.

at 2245. (

Reference:

LER 445/97-009).

2 971213 F

19.8 A

1 Manual reactor shutdown per T.S. 3.3.2.

Action 26 due to inoperable Train B Solid State Protection Sequencer. (

Reference:

I LER 445/97-010). Work was completed on sequencer and Unit placed back in service on December 14. at 0610 and returned to 100* pcwer on December 15. at 2359.

i

1) REASON
2) ETHOD A: EQUIPMENT FAILURE (EXPLAIN) E: OPERATOR TRA'NING AND LICENSE EXAMINATION 1: MANUAL B: MAINT OR TEST F: ADNINISTRATIVE 2: MANUAL SCRAM C: REFUELING G: OPERATIONAL ERROR (EXPLAIN) 3: AU'3tATIC SCRAM -

D: REGULATORY RESTRICTION H: oTHER (EXPLAIN) 4: oTIER (EXPLAIN)

  • INDICATES SHUTDOWN H0lRS/0THERWISE *NA* FOR NOT APPLICABLE n

.= < - - -

m Att:chment 13 TXX-98044 Page 15 of 19 TABLE 2.2 (PAGE 1 CF 3)

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

  • THE REACTOR OR

[fQ DAIE S: SCHEDULED (HOURS)

REASON REDUCING POWER CORRECTIVE ACTIONS /C0ffENTS 1

970104 S

102.5 B

1 At 1620 on January 4. the Unit entered a planned maintenance outage to repair oil leak to the capacitance coupled voltage transformer (CCVT). Additionally, completed repair work on main feedwater isolation valves and main transfor m r 2MT2 as well as heater drain pump 2-02 shaft replacement and main feedwater pump bearing inspections. Unit returned to 100%

power on January 10 at 1457.

2 970222 S

A 4

On February 22. at 0606 after completion of routine Turbine Stop and Control valve Testing.

the Unit was held at 72% power to replace the positioner on feedwater heater normal drain level control valve 2-LV-2509. The positioner was replaced and the Unit returned to 1002 power on the same day at 1615.

3 9705%

F A

4 On May 5. at 0430 Unit power was reduced to 48% due to a cracked weld on main feedwater pump 2B casing vent valve 2FN-0011. Weld was repaired and the Unit returned to 100% power on May 7. at 12,44. Unii was at reducert power for approximately 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />.

2) KTHG)
1) REASON A: EQUIPMENT FAILURE (EXPLAIN) E: OPERATOR TRAINING AND LICENSE EXANINATION 1: MMUAL 2: MNtML SCRAN B: MAINT OR TEST F: ADMINISTRATIVE 3: AUTOMTIC sCRAN C: REFE LING G: OPERATIONAL ERROR (EXPLAIN) 4: OTE R (EXPLAIN)

D: REGAATORY RESTRICTION H: OTER (EXPLAIN)

  • INDICATES SHUTDOWN HOURS /0THERWISE *NA" FOR NOT APPLICABLE l

Attachment tm TXX-98044 Page 16 of 19 TABLE 2.2 (PAGE 2 0F 3)

COMANCHE PEM STEAM ELECTRIC STATION - UNIT 2 UNIT OPEi<ATING EXPERIENCE INCLUDING SHUTDOWNS AND POWER REDUCTIONS ETH00 0F TYPE SHUTTING DOWN F: FORCED JJRATION*

THE REACTOR OR g)

DAIE S: SCHEDULED (HOURS)

REASON REDUCING POWER CORRECTIVE ACTIONS / COP 9ENTS 4

970523 F

A 4

On May 23. at 1745the Unit reduced power to 48% to troubleshoot and repair main feedwater pump 28 outboard bearing due to high vibration. The problem was ijentified as a cracked inboard water seal collar. The collar was replaced and the Un;t returned to 100* power on June 3 at 1810. The Unit was at reduced power for a approximately 264 hours0.00306 days <br />0.0733 hours <br />4.365079e-4 weeks <br />1.00452e-4 months <br />.

5 971025 S

164.9 C

2 On October 25. at 0404 while down powering SA 971101 S

720.0 C

2 to begin the third refueling outage 58 971201 S

218.0 C

2 (2Rr03) the reactor was manually tripped after 4 control rods inserted (LER 446/97-002-00). At the beginning of the third refueling outage. the Power Operated Relief Valves 2-PCV-0456A and 2-PCV-0455A opered after the unit was cooled down to the Low Temperature Overpressure Protection (LTOP) aiing terperature (350 Degrees) with pressure above the LTOP

etpoint. (Special Report 2-SR-97-001-00)

Unit was returned to service on December 10 at 0204.

2) E TH0D
1) REASON A: EQUltHENT FAILURE (ELUIN) E: OPERATOR TRAINING AND LICENSE EXAMINATION 1: WNUAL 2: M NUAL SCRAM B: MAINT OR TEST F: ADMINISTRATIVE

~

3: AUTOMATIC SCRAM C: REFUELING G: OPERATIONAL ERROR (EXPLAIN) 4: OTIG (EXPIAIN)

D: REGULATORY RESTRICTION H: nTER (EXPLAIN)

  • INDICATFS SHJTDOWN HOURS /01NERWISE *NA" FOR NOT APPLICABLE

A n

Attachment ts TXX-98044 Page 17 of19 TABLE 2.2 (PAGE 3 0F 3)

COMANCHE PEAK STEAM ELECTRIC STATION -' UNIT 2 UNIT OPECATING EXPERIENCE INCLUDING SHUTD0lelS AND POWER REDUCTIONS ETHOD OF

'. TYPE SHUTTlNG DOWN F: FORCED DURATION

  • THE REACTOR OR NQ DATE.

5: SCHEDULED (HOURS)

REASON REDUCING POWER CORRECTIVE ACTIONS /CONfMTS 6

971213 F

A 4

On December 13. at 1020 while returning to' poter after 2RFn3. Unit holds at 55%

power to' repair leak on tha main feedvater pump 2B casing drain line weld. The Unit was held at 551 power for approximately 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />. Repairs were ccupleted and Unit returned to 100% power December 19 at 1053.

I

2) ETHDD
1) REASON A: EQUIPMENT FAILURE (EXPLAIN) E: OPERATOR TRAINING AND LICErl EXmImTION 1: MNUAL 7: MNJ4L SCRAN B: MA 9T OR TEST F: ADMINISTRATIVE C: REFUELING G: OPERATIONAL ERROR (EXPLAIN).

3: AUTomTIC SCRAM 4: OTER (EXPLAIN)

D: REGULATORY RESTRICTION H: OTER (EXPLAIN)

  • INDICATES SETD0bN H0tRS/0TERWISE *NA* FOR W 9PN.ICABLE

m c_

+ _

' _ Att:chmmt to TXX-98044

. Page 18 cf 19

-TABLE 3.0 COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 1997 PERSONNEL EXPOSURE AND MONITORING REPORT

  1. Personnel f>100 mrem)

Total Person - rem Wark & Job Fune*ian Station 1[liktX C2RtIAct Station Utility Contract Reacter Operations & Serveillance -

Malatensace & Construction 0

0 8

.061

.000 2.656 Operations 11 0

0 4.279

.000

.149 Health Physics & Lab 9

1 31 2.758

.144 8.010 Supervisory & Omce StsN 0

0 0

.096

.000

.000 de gleeerlag Staff 1

0 0

.422

.000

.122 Arutine Plant Malatenance

- Malatensace A Constructies 11 0

148 5.179

.000 44.734 Operntlens 3

0 1

1.460

.000

.448 Health Physics & Lab 5

0 3

1.459

.050 1.715 Supervisory & Omce StaN '

0 0

0

.052

.000

.080 Engineerlag StaN 0

0 0

.512

.000

.378 12-service laspection Maintensace & Constructica 0

0 67 -

.088

.000 24.679

. Operations 2

-0 0

.466

.000

.000 Health Physics & Lab 2

0 15

.684

.000 4.302 Supervisory & Omce Staff 0

0 0

.000

.000

.000 Engineerts: Staff -

0 0

4

.129

.000 1.0(3

  • Special Plant Malatenance Maintenance & Construction 0

0 31

.017

.000 9.103 Operstless _

0 0

2

.030

.000

.619 Health Physics & Lab 0

0 0

0111

.000

.056 Supervisory & Omce StaN 0

0 0

.018

.000

.000

__ Engineering Staff 0

0

-0

.135

.000 _

.239

- Waste Processlag

- Malatemance & Construction 0

0 3_

.045 -

.000 -

1.098

' Operations 0

0 1

.401

.000

.234 Health Physics & Lab I

O O

.502

.f, ")

.180

-- Supervisory & Omce Staff 4-0 0

.007

.000

.000 Englaeering St3ff 8

0 0

.026

.000

.041 Refueling Malatecance & Construction 0

0 50

.161

.000

-21.481-Operations 5

0 0

1.271

.000

.059

- Health Physics & Lab 5

0 7

1.145

.000 2.220

- Supervisory & Omce Staff 9

0 0

.006

.000

.005 Eagleeering Staff 0

0 I

.191

.000

.240

- Totals Malatenance & Construction 14 0

293 5.551

.000 103.751 Operations 23 0

5 7.907

.000 1.510 1_

Health Physics & Lab 23 1

56 6.566

.265 16.482 Supervisory & Omce Staff 0

0

'0

.179

.000

.086

. Englaeerlag Stan 2

0 9

1.416

.000 2.083 Grand Totals 62 1

363 21.619

.265 123.912

  • Coatlag repairs in all radiologically controlled areas.

Att:chtnert t2 TXX-98044 Page 19 cf 19 TieLE 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 Activity Sinale Event Total Annual Exoosure (mraml Exoosure (meem)

Nozzle Dam.

Westinghouse 585 640

Retrieved from "https://kanterella.com/w/index.php?title=ML20203K901&oldid=5486939"