Text

1996 Annual Operating Rept for Fermi 2
	ML20135F082
Person / Time
Site:	Fermi
Issue date:	12/31/1996
From:	Smith P; DETROIT EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	CON-NRC-97-0017, CON-NRC-97-17 NUDOCS 9703110174
	Download: ML20135F082 (20)
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Fermi 2 Edison EEE23 c:1.

TS 6.9.1.4 7

February 28,199/.

NRC-97-0017 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D. C. 20555

Reference:

Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

1996 Annual Operating Report for Fermi 2 In accordance with the Fermi 2 Technical Specifications and NRC Regulatory Guide 1.16, enclosed is the Annual Operating Report for the Fermi 2 Nuclear Power Plant fcr the period from January 1,1996 through December 31,1996 (See Enclosure 1).

The 1996 Annual Operating Report for Fermi 2 satisfies the reporting requirements of Regulatory Guide 1.16, (Personnel Monitoring Report), Technical Specification 6.9.1.5.a (Annual Exposure Report by Function), Technical Specification 6.9.1.5.b (Safety / Relief Valve Challenges), Technical Specification 6.9.1.5.c (Emergency Core i Cooling System Outages), and Technical Specification 6.9.1.5.d (Specific Activity ,

Analysis of the Primary Coolant).

The 1996 Annual Operating Report also includes a section on service life of the main steam bypass line. This satisfies the commitment stated in a Detroit Edison letter to the h1C dated November 7,1986 [VP-86-0154].

If you have any questions or comments regarding this report, please contact Mr. Ken Riches, Compliance Engineer, at (313) 586-5529.

Sincerely, fl 9703110174 961231 gDR ADOCK0500g1 i Peter W. Smith Director - Nuclear Licensing Enclosure

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cc: A. B. Beach M. J. Jordan G. A. Harris A. J. Kugler 110057 Region 111 U.NW.E$,E.I!

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FERMI 2 i ANNUAL OPERATING REPORT JANUARY 1 - DECEMBER 31,1996 1

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DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 1

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. NRC-97-0017 Page 2 Table of Contents Page 1.0 Introduction 3 2.0 Summary of Operations 3 2.1 Summary of Operating Experience 3 2.2 Summary of Outages and Forced Reductions 3 Greater than 20 Percent ofFull Power 2.3 Fuel Performance 6 2.4 Shore Barrier Survey 6 2.5 Safety ReliefValve Challenges 7 2.6 Personnel Monitoring and Exposure 7 2.7 Service Life of Main Steam Bypass Line 9 2.8 Specific Activity Analysis of the Primary Coolant 9 2.9 ECCS Cooling Performance Evaluation Model 9 Changes or Errors 2.10 ECCS Outages 10 i

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. NRC-97-0017 Page 3 l.0 Introduction The Fermi 2 Nuclear Power Plant site is located on the western shore of Lake Erie in Frenchtown Township, M'onroe County, Michigan. The Nuclear Steam Supply System is a -

General Electric BWR 4 with a Mark I pressure-suppression containment. The plant is fully owned by the Detroit Edison Company. '

2.0 Summary of Operations 2.1 Summary of Operating Experience Fermi 2 was operating at 96 percent power at the start of 1996. The fifth refueling outage (RF05) commenced on September 27,1996 and was scheduled to be completed on November 19,1996. However, due to emergency diesel generator, safety relief valve position indication, and vacuum breaker closed position indication problems the l plant was stillin RF05 at the close of 1996. During 1996, with the reactor critical, the )

reactor automatically scrammed once on December 28,1996, due to a false Level 3 signal while valving in the reactor water level reference leg backfill system during i startup from RF05. There was one forced outage due to a Technical Specification required shutdown when both divisions of Emergency Equipment Cooling Water (EECW) were declared inoperable due to a make-up tank design issue. A plant modification was installed and the plant was restarted on April 19,1996. During this startup, the high pressure core injection (HPCI) and reactor core isolation cooling (RCIC) systems were declared inoperable due to surveillance test requirements not being satisfied, and a Technical Specification shutdown was required. There were eleven reactor power reductions for turbine generator related repairs, surveillance testing, and control rod pattern adjustments. Core Thermal Power (CTP) is .

administratively limited to 96 percent due to turbine and steam piping vibration limitations.

2.2 Summary of Outages and Forced Reductions Greater than 20 Percent of Full Power January 19,1996 - Power Reduction Reactor power was reduced to 55% CTP to perform scram pilot solenoid valve maintenance, scram time testing, control rod pattern adjustments and main turbine stop and control valve surveillances. ;

February 10,1996 - Power Reduction I i 1

. i Reactor power was reduced to 65% CTP to repair a steam leak on the north Feedwater Heater No. 5 and to replace the No. 3 low pressure turbine intercept valve accumulator low pressure switch.

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-- Page 4 March 27,1996 - 413.4 Hours Shutdown Technical Specification required shutdown due to both divisions of EECW being declared inoperable because of a system make-up tank design issue. A plant modification was installed.

April 19,1996 - 108.4 Hours Shutdown During unit startup from the March 27,1996 forced outage, HPCI and RCIC were declared inoperable and a Technical Specification required shutdown was completed due to surveillance test requirements not being satisfied.

April 24,1996 - Power Reduction Reactor power was reduced to 55% CTP to conduct control rod pattern adjustments to obtain a new 96% core thermal power rod line.

May 3,1996 - Power Reduction Reactor power was reduced to 68% CTP to conduct power suppression testing and to perform deep / shallow control rod exchange.

May 8,1996 - Power Reduction Reactor power was reduced to 70% CTP to repair the No. 3 high pressure control valve unitized actuator oilleak.

' June 2,1996 - Power Reduction Reactor power was reduced to 51% CTP while in a Technical Specification action statement requiring unit shutdown resulting from control complex heating, ventilation and air conditioning (CCHVAC) system testing requirements.

June 20,1996 - Power Reduction Reactor power was reduced to 76% CTP to place the "D" reactor water level reference leg backfill regulator in service and to remove the "B" regulator from service.

June 29,1996 - Power Reduction Reactor power was reduced to 65% CTP to perform control rod scram time testing and pattern adjustment, main turbine generator stop and control valve testing and turbine bypass valve tests.

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July 4,1996 - Power Reduction p

i Reactor power was reduced to 74% CTP to place the main turbine generator ,

hydrogen gas cooler temperature control valves in automatic operation. l

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August 3,1996 - Power Reduction )

Reduced reactor power to 65% CTP to perform deep / shallow control rod

j. exchange.

l September 7,1996 - Power Reduction j 2

Reduced reactor power to 60% CTP to perform control rod pattern adjustment.

September 27,1996 - 80.5 Hours Shutdown

! Unit shutdown to begin Refueling Outage No. 5.

October 1 - 31,1996 - 745 Hours Shutdown j- Uni; shutdown for Refueling Outage No. 5.

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} November 1 - 19,1996 - 447.5 Hours Shutdown i

Unit shutdown for Refueling Outage No. 5. l November 20,1996 - 272.5 Hours Shutdown

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! Unit remained shutdown beyond the 53 day scheduled refuel outage due to an emergency diesel generator automatic voltage regulator failure.

j December 2,1996 - 98.1 Hours Shutdown i

Unit shutdown to troubleshoot safety relief valve "A" tailpipe pressure switches.

j December 7,1996 - 333.4 Hours Shutdown

] Unit shutdown to relocate safety relief valve "A" tailpipe pressure switch sensing j line tap locations.

December 22,1996 - 27.6 Hours Shutdown Unit shutdown to repair safety relief valve "D" solenoid actuator.

December 24,1996 - 73.8 Hours Shutdown Unit shutdown to repair a Drywell to torus vacuum breaker.

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December 28,1996 - 82.8 Hours Shutdown !

Reactor scram due to false Level 3 signal while valving in the reactor water level reference leg backfill system.

2.3 Fuel Performance The reactor was operating in Mode 1 at the start of 1996. During 1996 the plant produced about 221 effective full power days based on a 3430 MWt rating. During 1996, Core Thermal Power (CTP) was administratively limited to 96 percent due to turbine limitations.

Fermi 2 began 1996 with one leaking fuel bundle in the core, which had already been suppressed by three control blades, and a sum-of-six offgas activity at the steam jet air ejector of about 120 Ci/sec. On March 16 offgas activity temporarily spiked and the spike peaked at about 600 pCi/sec. Analysis ofdata could not rule out the possibility of a second leaking fuel bundle, and a power suppression test was performed.

The test confirmed a second leaking fuel bundle, and two more control blades were fully inserted to suppress power in this bundle. All five suppressor blades remained fully inserted until the end of cycle, at which time the sum-of-six off-gas activity was about 500 pCi/sec.

General Electric performed vacuum sipping during RF05, and confirmed two leaking bundles which both were in suspect cells containing suppressor control blades. The first leaking bundle, which failed in October 1995, was bundle .ABB002 which is a thrice burned ABB bundle. The second bundle leaking bundle was YJ2624, which is a twice burned GElI bundle. ABB002 was suppressed for about eleven months, and YJ2624 was suppressed for more than four months. Based on offgas activity and coolant sampling, both bundles showed no evidence of significant degradation of the leaking fuel rods. Both bundles were discharged in RF05, and analysis to determine the cause of the leakers is scheduled for 1997, 2.4 Shore Barrier Survey A survey of the Fermi 2 shore barrier was completed as required by Technical Specification 4.7.3. The results of the survey indicated no damage, significant movement, or deterioration of the barrier. All forty-seven survey point elevations were within the tolerance specified in Technical Specification Table 3.7.3-1. Civil Engineering Drawings 6C721-44 through 49 were revised to incorporate the survey data. No unusualincidents occurred in 1996 that would have required additional surveillances.

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. NRC-97 0017 Page 7 2.5 Safety Relief Valve Challenges There were no instances in 1996 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation. There were no instances in 1996 where an SRV actuation was demanded by an automatic logic system. SRVs were manually actuated for surveillance testing or post-modification testing as described below:

Dgg Affected SRV Comments 12/01/96 All Surveillance Testing, "A" position indication anomaly identified (LER 96-017). All SRVs lift on demand 12/01/96 "A" Retest for position indication cause investigation 12/07/96 "A", "D" Retest for position indication cause investigation 12/22/97 "A", "D", "H", "R", "P" "D" failed to close on first and second attempts 12/24/96 "A", "D" Retest. "D" operates successfully,"A" position indication verified operating properly 2.6 Personnel Monitoring and Exposure Table 2.6-1 provides a breakdown of radiation exposure by work and job function as ;

required by Technical Specification 6.9.1.5.a.

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Page 8 Table 2.6-1 Detroit Edison Fermi 2 .

J96 Regulatory Guide 1.16 Direct Reading Dosimeter (DRD) Deep Dose Equivalent (DDE) Dose Report Personnel Recemng Exposure DRD DDE Mavem Functm Department Statm Utility Contract Station Utility Contract Employees Employees Workers Employees Employees Workers Plant Maintenance 71 2 47 3.529 0.000 2.252 Operations Operates 84 1 25 7.488 0 002 5.166 Health Physcs 30 0 11 2.743 0.000 1.542 Supennsory 129 14 277 7.311 0 094 8.172 Engineenng 80 3 2 1.633 0 000 0 000 Reactor Maintenance 57 2 80 7.468 0 016 6.063 Operates Operations 2 0 3 0.272 0.000 0.519 and Survei!!ance Health Physes 1 0 1 .0150 0.000 0.182 Supervisory 19 5 118 0 869 0.007 11.735 Engineenng 9 1 2 0.284 0.000 0.290 Reactor Maintenance 0 0 2 0.000 0.000 0.020 Maintenance /ISI Operations 1 0 0 0.000 0.000 0 000 Health Physics 0 0 0 0.000 0.000 0 000 Supennsory 0 1 19 0 000 0.016 0.400 Ergirst g 3 0 0 0 462 0.000 0 000 Special Mastenance 39 0 93 6.330 0.000 6.584 Maintenance Operations 4 0 5 0.039 0.000 0.976 Health Physics 3 0 2 0.561 0.000 0.097 Supervisory 24 8 469 1.761 0.145 46.792 Engineenng 11 1 1 0 335 0.008 0.255 Waste Maintenance 0 0 0 0.000 0.000 0.000 Processing Operatens 0 0 2 0 000 0.000 0.158 Health Physcs 0 0 0 0.000 0.000 0.000 Supervisory 0 0 3 0.000 0.000 0.320 Erg- 6 sig 0 0 0 0.000 0.000 0 000 Refueling Maintenance 1 1 28 0.115 0.000 4.144 Operations 8 0 4 0.387 0.000 0.698 Health Physes 19 0 6 1.610 0.000 1.011 Supennsory 21 5 248 0.822 0.000 24.279 Engineenng 18 0 7 0.641 0.000 0 670 Total Maintenance 168 5 250 17.442 0.016 19.062 Operations 99 1 39 8.186 0.002 7.517 Health Physics 53 0 20 5.064 0.000 2.832 Supesvisory 193 33 1134 10.763 0.262 91.698 Engineering 121 5 12 3.355 0.008 1.125 ._

Grand Total Personnel 2,133 Manrem 167.333 l NOTE: This report was produced using only secondary (DRD) extemal dostmetry - it does not include any intemal exposure.

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. 2.7 Service Life of Main Steam Bvoass Line In accordance with a Detroit Edison letter to the NRC dated November 7, 1986 [VP-86-0154], the cumulative time the main steam bypass lines are operated with the bypass valves between 30 percent and 45 percent open will

,! be reported annually. A cumulative value of 100 days is not to be exceeded j without prior NRC notification.

i Evaluations performed by Stone and Webster and by Hopper and Associates

concluded that the bypass lines are acceptable for safe operation when j operated within the 100 day constraint. Based on these evaluatioris, the new main steam bypass piping that was installed in 1985 has a service life which will allow it to function for the life of the plant under anticipated operating conditions. The main steam bypass lines cumulative usage was 36.36 days as

of December 31,1996.

2.8 Specific Activity Analysis of the Primary Coolant Exceeding the Limits of Technical Specification 3.4.5 During 1996, the specific activity of the primary coolant did not exceed the !

limits of Technical Specification 3.4.5.

1 2.9 ECCS Coolina Performance Evaluation Model Channes or Errors During the preparation of the 1995 Fermi 2 Annual Operating Report, Detroit Edison determined that the ECCS evaluation model change reporting section of the annual report had not been included in previous Annual Operating Reports, from 1989 through 1994, as required by Fermi 2 plant procedures.-

Detroit Edison believed that the vendor letters to the NRC satisfied the 10 CFR 50,46 reporting requirements.

In July 1991, as part of the Fermi 2 Power Uprate Program, the SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis was performed.

This analysis provides a baseline of 1602 degrees Fahrenheit where the impact of any previous change or error notices would have been already considered.

On April 25,1996, Detroit Edison confirmed with General Electric that the total accumulation of peak clad temperature (PCT) changes or errors identified as being applicable to Fermi 2 since July 1991 was 65 degrees Fahrenheit. This 65 degrees Fahrenheit change meets the notification requirements per 10CFR50.46(a)(3)(ii) because the change in PCT is greater than the thirty day reporting threshold (50 degrees Fahrenheit) for the accumulation of the absolute magnitude of changes or errors in the evaluation models or their application, and was reported to the NRC on May 28,1996 (Detroit Edison Letter No. NRC-96-0052).

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j $ ( Enclosure to NRC-97-0017 1 Page 10 l 1 After adding the 65 degrees Fahrenheit to the licensing basis PCT determined

) in the 1991 SAFER /GESTR analysis, there is still more than 500 degrees

, Fahrenheit of margin to the 2200 degree Fahrenheit limit specified in 10CFR50.46. The resulting PCT is still well below the temperature range where cladding oxidation and hydrogen generation becomes significant.

Therefore, the core-wide metal-water reaction and maximum local oxidation 3 remain well within the 10CFR50.46 limits. Also, the statistical upper bound PCT of 1351 degrees Fahrenheit plus the 65 degrees Fahrenheit change remains well below the 1600 degrees Fahrenheit limit specified in the NRC acceptance of the SAFER /GESTR methodology.

l 2.10 ECCS Outages Pursuant to Fcrmi 2 Technical Specification 6.9.1.5.c, a summary of the Emergency Core Cooling System (ECCS) outages which occurred between January 1,1996 and December 31,1996 is provided. The tabulation of ECCS outage hours (Table 2.10-1) includes both forced and planned outages for the Low Pressure Coolant Injection (LPCI), Core Spray, HPCI, and Automatic -

Depressurization Systems (ADS). An outage was considered to be whenever one of the ECCS systems was out-of-service at a time it was required to be operable per Technical Specifications.

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ECCS Outanes Table 2.10-1 ECCS Outage Hours January 1,1996 to December 31,1996 4- ECCS SYSTEM FORCED HOURS PLANNED HOURS i LPCI Division I- 0.0 63.32 LPCI Division II 0.0 48.20 Core Spray Division I 0.0 168.27 Core Spray Division II 0.0 124.71 ADS Division I 0.0 0.0 ADS Division II 0.0 0.0 HPCI 0.0 45.42 t

DIVISION I LOW PRESSURE COOLANT INJECTION ECCS System Outage: Division I Low Pressure Coolant Iniection Out of Service from 1944 02/12/96 to 0520 02/13/96 Duration: 9.60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months Planned Outage Outage Summary: Surveillance Performance.

ECCS System Outage: Division I Low Pressure Coolant Iniection Out of Service from 1615 03/27/96 to 1927 03/27/96 i

Duration: 3.20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months Planned Outage i

Outage Summary: Surveillance Performance.

I ECCS System Outage: Division I Low Pressure Coolant Iniection Out of Service from 0230 05/15/96 to 0630 05/15/96 Duration: 4.00 hours0 days 0 hours 0 weeks 0 months Planned Outage I Outage Summary: Surveillance Performance.

ECCS System Outage: Division I Low Pressure Coolant Iniection Out of Service from 0530 08/13/96 to 1705 08/14/96 Duration: 35.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Planned Outage

. Outage Summarv; Division I of the Residual Heat Removal (RHR) system was removed from service for a planned preventative maintenance outage.

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' Enclosure to NRC-97-0017 Page 12 ECCS System Outage: Division I Low Pressure Coolant Iniection Out of Service from 210108/14/96 to 2245 08/14/96 Duration: 1.73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months Planned Outage Outage Summary: Surveillance Performance.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0834 09/22/96 to 1109 09/22/96 Duration: 2.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Planned Outage Outage Summary: LPCI electrical swing bus inoperable.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 2218 09/27/96 to 0400 09/28/96 Duration: 5.70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months Planned Outage Outa.ge Summaw: Surveillance Performance.

ECCS System Outage: Division I Low Pressure Coolant Iniection Out of Service from 2319 12/02/96 to 0015 12/03/96 Duration: 0.93 hours0.00108 days 0.0258 hours 1.537698e-4 weeks 3.53865e-5 months Planned Outage Outage Summary: Surveillance Performance.

DIVISION 11 LOW PRESSURE COOLANT INJECTION ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 2147 3/26/96 to 2253 03/26/96 Duration: 1.10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months Planned Outage Outage Summary: Surveillance Performance.

ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 0020 06/25/96 to 1645 06/26/96 i Duration: 40.42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months Planned Outage j l

Optage Summarv: Division II of the RHR system was removed from sewice for a ;

planned preventative maintenance outage. !

ECCS System Outage: Division II Low Pressure Coolant Iniection Out of Service from 0157 06/27/96 to 0230 06/27/96 Duration: 0.55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months Planned Outage l Outage Summary: Surveillance Performance. ;

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' Enclosure to NRC-97-0017 i Page 13 ECCS System Outage: Division II Low Pressure Coolant Iniection j Out of Service from 0834 09/22/96 to 1109 09/22/96 1 Duration: 2.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Planned Outage Outage Summary: LPCI electrical swing bus inoperable.

ECCS System Outage: Division 11 Low Pressure Coolant Injection Out of Service from 0_l30 12/08/96 to 0225 12/08/96 Duration: 0.92 hours0.00106 days 0.0256 hours 1.521164e-4 weeks 3.5006e-5 months Planned Outage Outage Summary: Surveillance Performance.

ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 195212/24/96 to 2230 12/24/96 Duration: 2.63 hours7.291667e-4 days 0.0175 hours 1.041667e-4 weeks 2.39715e-5 months Planned Outage Outage Summary: Surveillance Performance.

DIVISION I CORE SPRAY ECCS System Outage: Division I Core Sprav. Pump "A" Out of Service from 0812 01/05/96 to 1115 01/05/96 Duration: 3.05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage !

l Outage Summary: Electrical Bus Undewoltage Trip Surveillance Performance l

ECCS System Outage: Division I Core Sprav. Pump "C" ;

Out of Service from 0854 01/12/96 to 1440 01/12/96 Duration: 5.76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months Planned Outage )

i Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division I Core Spray. Pump "C" Out of Service from 1253 02/16/96 to 1432 02/16/96 Duration: 1.65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division I Core Sprav. Pumo "A" Out of Service from 1800 03/07/96 to 1830 03/08/96 Duration: 24.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage Outage Summary: Electrical Bus Undewoltage Trip Surveillance Performance 1

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8 Enclosure to NRC-97-0017 Page 14 ECCS System Outage: Division I Core Soray. Pump "C" 4

Out of Service from 1215 03/15/96 to 1405 03/15/96 j Duration: 1.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Planned Outage

' Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance l ECCS System Outage: ' Division I Core Spray Out of Service from 1050 04/29/96 to 1130 04/29/96 i Duration: 0.67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months Planned Outage i Outage Summary: Core Spray Pump and Valve Surveillance Performance l

ECCS System Outege: Division I Core Sprav. Pump "A" l )

Out of Service from 0920 05/10/96 to 1305 05/10/96 1 Duration: 3,75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Planned Outage Outage Summary. Electrical Bus Undervoltage Trip Surveillance Performance l ECCS System Outage: Division I Core Sprav. Pump "C" i Out of Service from 1330 05/15/96 to 0955 05/16/96 Duration: 20.42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months Planned Outage l

Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance 4

' ECCS System Outage: Division I Core Spny. Pump "A" Out of Service from 1016 06/07/96 to 1400 06/07/96 Duration: 3,73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months Planned Outage

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. ECCS System Outage: Division I Core Sprav j Out of Service from 0535 06/11/96 to 1725 06/12/96 Duration: 35.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Planned Outage Outage Summary: Division 1 of Core Spray was inoperable due to the planned RCIC/ Core Spray room cooler maintenance outage.

ECCS System Outage: Division I Core Sprav. Pump "C" Out of Service from 0902 06/14/96 to J247 06/14/96 Duration: 3.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance

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/ Enclosure to NRC-97-0017 Page 15 ECCS System Outage: Division I Core Spray Out of Service from 0422 07/01/96 to 1230 07/02/96 l Duration: 32.13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months Planned Outage j Outage Summary: Planned Maintenance Outage ECCS System Outage: Division I Core Sprav. Pump "A" Out of Service ftom 1616 07/03/96 to 2005 07/03/96 Duration: 3.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance 4

i ECCS System Outage: Division I Core Sorav. Pumo "C" i Out of Service from 0835 07/12/96 to 1245 07/12/96 Duration: 4.17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division I Core Sorav. Pumo "A" Out of Service from 0854 08/09/96 to 1424 08/09/96 Duration: 5.50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months Planned Outage Outage Summaiv: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division I Core Sprav. Pumo "C" Out of Service from 1007 08/17/96 to 1400 08/17/96 Duration: 3.88 hours0.00102 days 0.0244 hours 1.455026e-4 weeks 3.3484e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division I Core Sprav. Pump "A" Out of Service from 093109/06/96 to 1354 09/06/96 Duration: 4.38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months Planned Outage j i

Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance j i

ECCS System Outage: Division I Core Sprav. Pump "C" {

Out of Service from 0900 09/13/96 to 1335 09/13/96 ;

Duration: 4.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Planned Outage l

Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance {

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' Enclosure to NRC-97-0017 Page 16 ECCS System Outage: Division I Core Sprayfumo "A" Out of Service from 1223 09/21/96 to 1500 09/21/96 Duration: 2.62 hours7.175926e-4 days 0.0172 hours 1.025132e-4 weeks 2.3591e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division I Core Spray. Pump "C" Out of Service from 1225 09/22/96 to 1440 09/22/96 Duration: 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months Planned Outage

_0_ulage Summary: Electrical Bus Undervoltage Trip Surveillance Performance DIVISION 11 CORE SPRAY ECCS System Outage: Division II Core Sorav. Pump "B" Out of Service from: 0845 01/19/96 to 1120 01/19/96 Duration: 2.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II Core Spray Out of Sewice from 1824 01/23/96 to 2100 01/19/96 Duration: 2.60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months Planned Outage Outage Summary: Core Spray Pump and Valve Surveillance Performance ECCS System Outage: Division II Core Soray. Pump "D" Out of Service from 0845 01/26/96 to 1400 01/26/96 Duration: 5.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months Planned Outage Outage Summarv: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II Core Spray. Purap "B" Out of Service from 1230 02/20/96 to 0320 02/21/96 Duration: 14.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Planned Outage Outage Summary; Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II Core Spray. Pump "D" Out of Service from 134102/27/96 to 0527 02/28/96 Duration: 16.77 hours8.912037e-4 days 0.0214 hours 1.273148e-4 weeks 2.92985e-5 months Planned Outage Outage Summan: Electrical Bus Undervoltage Trip Surveillance Performance

' Enclosure to NRC-97-0017 Page 17 ECCS System Outage: Division II. Core Spray pump "B" Out of Service from: 0818 03/25/96 to 1444 03/25/96 Duration: 6.43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II. Core Spray Out of Senice from: 2136 04/23/96 to 2237 04/23/96 Duration: 1.02 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Planned Outage Outage Summary: Core Spray Pump and Valve Surveillance Performance ECCS System Outage; Division II. Core Sprav pump "B" Out of Service from: 0910 04/24/96. to 1245 04/24/96 Duration: 3.58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Perfonnance ECCS System Outage: Division II. Core Sprav pump "D" Out of Service from: 0855 04/26/96 to 1245 04/26/96 Duration: 3.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months - Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II. Core Spray pump "B" Out of Service from: 0800 05/24/96 to 1330 05/24/96 Duration: 5.50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage:- Division II. Core Sprav pump "D" Out of Service from: 0840 05/31/96 to 1330 05/31/96 Duration: 4.83 hours9.606481e-4 days 0.0231 hours 1.372354e-4 weeks 3.15815e-5 months Planned Outage Outage Summarv; Electrical Bus Undervoltage Trip Surveillance Performance

- ECCS System Outage: Division II. Core Spray pump "B" Out of Service from: 0910 06/21/96 to 1338 06/21/96 Duration: 4.47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months Planned Outage Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II. Core Sprav pump "D" Out of Service from: 0807 06/28/96 to 1240 06/28/96 Duration: 4.55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months Planned Outage m

d Enclosure to 4

NRC-97-0017

Page 18

, Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II. Core Sprav pump "B" i Out of Service from: 0840 07/19/96 to 1429 07/19/96 Duration: 5.82 hours9.490741e-4 days 0.0228 hours 1.35582e-4 weeks 3.1201e-5 months Planned Outage

]

1 Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance ECCS System Outage: Division II. Core Sprav pump "D" Out of Service from: 0834 07/26/96 to 1335 07/26/96

Duration: 5.02 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Planned Outage Outane Summary: Electrical Bus Undervoltage Trip Surveillance Performance 1

~

ECCS System Outage: Division II Core Spray Out of Service from 0529 07/31/96 to 2253 07/31/96 Duration: 17.40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months Planned Outage Outane Summary: Planned Maintenance Outage

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. ECCS System Outage: Division II. Core Sorav pump "D"

)

Out of Service from: 0855 08/30/96 to 1300 08/30/96 I

Duration: 4.08 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage i

! Outage Summary: Electrical Bus Undervoltage Trip Suiveillance Performance I

l ECCS System Outage: Division II. Core Sprav pump "B" Out of Service from: 0815 09/20/96 to 1220 09/20/96 Duration: 4.08 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage l

'i

, Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance

! ECCS System Outage: Division II. Core Sprav pump "D" Out of Service from: 1025 09/24/96 to 1437 09/24/96 Duration: 4.20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months Planned Outage

,l l Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance 4

! ECCS System Outage: Division II. Core Soray pump "D" Out of Service from: 165011/30/96 to 004212/01/96 3

Duration: 7.87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months Planned Outage i

Outage Summary: Electrical Bus Undervoltage Trip Surveillance Performance d

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'# Enclosure to NRC-97-0017 Page 19 DIVISION I & DIVISION II AUTOMATIC DEPRESSURIZATION SYSTEM The Automatic Depressurization System (ADS) accumulated Zero outage hours from January 1,1996 to December 31,1996.

IIIGII PRESSURE CORE INJECTION ECCS System Outage: HPfl Out of Service from 0409 07/16/96 to 0116 07/18/96 Duration: 45.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Planned Outage Outage Summary: Annual HPCI system planned outage for corrective and preventative maintenance.

ECCS System Outage: HPCI Out of Service from 180912/01/96 to 1827 12/01/96 Duration: 0.30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Planned Outage Outage Summary: Surveillance Performance l

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NRC-97-0017, 1996 Annual Operating Rept for Fermi 2

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