Text

Annual Operating Rept,Jan-Dec 1987
	ML20147B006
Person / Time
Site:	Fermi
Issue date:	12/31/1987
From:	Sylvia B; DETROIT EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	CON-NRC-88-0030, CON-NRC-88-30 NUDOCS 8803010420
	Download: ML20147B006 (36)
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Fermi 2 Annual Operating Report January 1 - December 31, 1987 Detroit Edison Company NRC Docket No. 50-341 Facility Operating License No. NPF-43

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8803010420 871231 PDR ADOCK 05000341 R

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Enclosure to f

NRC-88-0030 i

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Table of Contents l

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i 1.0 Introduction 3

i 2.0 Summary of Operating Experience 3

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j 2.1 Summary of Operations 3

l 2.2 Summary of Outages and Forced Reductions 4

i Greater Than 20 Percent of Full Power i

23 Fuel Performance 9

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l 2.4 Shore Barrier Survey 10 l

f 2.5 Safety Relief Valve Challenges 10 2.6 Personnel Monitoring and Exposure 11 I

1.7 Service Life of Main Steam Bypass Line 13 t

2.8 Specific Activity Analysis of the Primsry Coolant 13

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f 2.9 ECCS Outages 14 i

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NRC-88-0030 Page 3 r

i 1.0 Introduction The Fermi 2 Nuclear Power Plant site is located on the western shore of Lake Erie in Frenchtown Township, Monroe County, Michigan.

The Nuclear Steam Supply System is a General Electric BWR 4, with a pressure-suppression Mark I containment. The unit l

l 1s rated at 3292 MWt. The plant is owned jointly by the Detroit Edison Company (approximately 90 percent) and the Wolverine Power Supply Cooperative, Incorporated (approximately 10 percent).

Detroit Edison has reached agreement with Wolverine Power Supply Cooperative Inc. to purchase the cooperative's remaining ownership interest in Fermi 2 effective January 1, 1990.

Detroit Edison has exclusive responsibility and control over the operation and maintenance of the facility.

2.0 Summary of Operating Experience 2.1 Summary of Operations This operations summary covers the period from

3 January 1, 1987 to December 31, 1987. At the beginning of i

1987. Fermi 2 was operating at about the restricted power level of 20% and testing of startup test phase Test Condition 1 (TC-1) was in progress. TC-1 was completed on January 7, 1987. A main steam line instrument tap repair I

outage began on January 9, 1987 and was completed on January 24, 1987. NRC authorization to proceed up to 50%

power was received on February 16, 1987. Test Condition 2 (TC-2) was entered on February 24, 1987 and completed on l

March 16, 1987 along with the Loss of Offsite Power test.

A Moisture Separator Reheater (MSR) refit outage began on i

i March 16, 1987 and was completed on April 3, 1987. The plant was also shutdown between April 12, 1987 and May 10, 1987 for some additional main steam line tap repair work.

An Outage to repair a feedwater check valve began on July 31, 1987 and was completed on October 9, 1987.

Several other modifications were also completed during this j

outage to enhance the material condition of the plant and to achieve readiness for exceeding 50% power.

NRC J

authorization to exceed 50% power was received on December 1

5, 1987. Test condition 3 (TC-3) was completed on December 1

26, 1987. Test Condition 5 (TC-5) was completed on l

December 30, 1987.

At the end of 1987. Fermi 2 was operating at about 75% power when plant shutdown occurred j

due to a reactor trip.

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i Enclecuro to NRC-88-0030 Page 4 NOTE:

NRC authorization to proceed up to 100% power was received on January 15, 1988. Fermi 2 achieved commercial operation on January 23, 1988 after a successful run for 100 consecutive hours at more than 90% of power level.

2.2 Summary of Outages and Forced Reductions Greater Than 20 Percent of Full Power o

January, 1987 January 2, forced a utdown - 71 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Reactor was not shutdown. The turbine-generator was l

shutdown after three small steam leaks w&,re detected.

3 The leaks were from broken spare instrument lines located between the turbine control valves and the turbine-generator.

r Jac"ary 5. forced shutdown - 618.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Reactor was shutdown to inspect and repair welds on instrument taps attached to the main steam lines.

Outage scope was expanded to include work on the Control Center HVAC chiller.

o February, 1987 i

February 16, forced shutdown - 3 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

-l Reactor was not shutdown. Turbire Generator tripped

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due to the performance of procet te 27.112.04 (Turbine i

Generator Valves Low VAC on Load Test). The purpose of this procedure is to verify the operability of the Turbine Generator Low Condenser Vacuun Trip Circuitry. The procedure has been revised to prevent i

inadvertent turbine trips.

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February 17, forced shutdown - 10 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Reactor was not shutdown. Generator was shutdown to investigate a possible ground on field. No evidence of a ground fault was discovered.

Enclosuro to NRC-88-0030 Page 5 February 18, forced shutdown - 5 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Reactor was not shutdown. Generator was shutdown again for additional investigation of a pc' xible ground fault. No evidence of a fault was found.

February 23, forced shutdown - 22.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Reactor was not shutdown. Generator automatically shutdown. The cause of the trip was investigated.

February 26, forced shutdown - 58.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Turbine trip and subsequent reactor trip was due to a generator negative ground fault. The most probable

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cause was that an aluminum strip in the iso phase bus duct broke free and made contact with the bus which resulted in a ground fault.

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Continuation of February 26 forced shutdown - 55 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Reactor was restarted on February 28.

Before generator synchronization, an automatic shutdown occurred on March 1 due to pressure spike caused by operator error in resetting the turbine control circuit alara. Corrective actions included revising the alarm response procedure. Reported as LER 87-008 dated March 31, 1987.

c March 16, schedule outage - 2 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Reactor was not shutdown. Turbine Stop Valve Trip and Generator Load Rejection (within the bypass valves capacity) Test was performed. The test satisfactorily demonstrated the response of the reactor and its control systems to protective trips in the turbine and l

generator.

March 16, scheduled outage - 365.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months The final TC-2 test, Loss of Turbine - Generator, and Loss of Offsite Power, was performed. While in Hot i

Shutdown a scram signal was initiated when operators were placing the RHR into the shutdown cooling. This

4 Enclo::ura to l

NRC-88-0030 i

Page 6 i

was reported as LER 87-007 The planned outage i

between TC-2 and TC-3 began March 17, 1987. The main outage activity involved modifying the Moisture Separator Reheaterts. Other work included replacing an innerspring on two MSIVs and repairing the t

regenerative heat exchangers. Outage activities completed in March included ~ instal'ation of a permanent hatch on the torus, preventive maintenance i

on the EDGs and replacement of RHR pump acto" B.

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April, 1987 4

Continuation of March 16 scheduled outage - 127.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months i

Continuation of the planned outage between TC-2 and TC-3 Major outage activities included modifying the Moisture Separator Reheaters, installation of a i

permanent hatch on the torus and replacemer.t of RHR r

pump motor B.

April 6, forced shutdown - 42.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months i

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Reactor scran due to personnel error while performing i

Average Power Range Monitor B Channel functional test.

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During the performance of this test, half scram l

signals are introduced on channel "B".

The I&C repairman sistakenly pulled the Trip Reference Card for APRM "A".

This generated a full scram.

Corrective actions included counselling the individual and revising tt,e procedure. Reported as LER 87-011

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dated May 5, 1987 April 10, forced shutdown - 13.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Reactor was not shutdown. Main Turbine-Generator j

tripped due to high vibration on No. 5 bearing.

J Investigation revealed that a false signal was generated due to a failed vibration sensing element.

The failed equipment was replaced.

April 11, forced shutdown - 474 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months J

Turbine-generator was manually tripped due to a stean j

leak on a weld from instrument taps on the sain steam lines. A stean leak was reported from a pipe connection on the east bypass valve. The leak could l

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Enclosuro to NRC-88-0030 Page 7 i

not be isolated so the reactor was placed in cold i

shutdown. Outage work includes repair of the east I

bypass valve, replacing instrument taps, inspecting welds, installing instrument tubing supports and repacking valves in the Turbine Building.

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May 12, 1987 Continuation of April 11 forced shutdown - 668 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 3

i A vibration problem caused the south reactor feedpump

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turbino to trip on May 13 This lead to an automatic shutdown of the reactor. As a corrective action, the reactor feedwater system procedure has been revised.

This was reported as LER 87-017 dated June 12, 1987.

On May 20 an Unusual Event was declared due to leakage from a valve on the reactor water cleanup system.

i Operators shutdown the reactor because they were l

unable to identify the type of leakage. The valve was j

repacked. It was reported in LER 87-018.

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June 16, forced shutdown - 41.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months l

Reactor power was reduced and the turbine-generator l

was taken off line in order to repair an oil leak in one of the two main transformers. Two pressure relief l

l diaphragas on the transformer have been changed.

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June 18, forced shutdown - 8.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months j

Reactor was not shutdown. Turbine-generator tripped i

due to high vibration on No. 5 bearing.

Investigation revealed that a false signal was generated due to a failed vibration sensing element. The failed i

equipment was replaced.

i June 24, forced shutdown - 108.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months J

Main turbine generator was manually shutdown in l

preparation for the Technical Specifications required plant shutdown due to inoperable Reactor Coolant l

System recirculation loop. As corrective action, recirculation pump B actor generator set brushes were l

inspected and repaired.

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NRC-88-0030 j

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o July, 1987 July 20, forced shutdown

.117.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Reactor Scram occurred after a Turbine Valve Fast 2

Closure. The Turbine Valve Fast Closure was the result of a false high vibration signal from the Main Turbine Generator No. 1 bearing. To prevent i

recurrence the Alarm Response Procedure for high j

vibration signals has been revised.

July 26, forced shutdown - 129.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Generator was taken off line and reactor power was reduced to repair a leaking Feedwater Check Valve.

j Subsequently, the reactor was shutdown and a maintenance outage began.

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August, 1987 i

l Continuation of July 26 Outage - 744,0 hours0 days 0 hours 0 weeks 0 months i

A maintenance outage, continued from last month. The l

expanded outage included work on environmental qualifications, preventative maintenance of Residual Heat Renoval System Divisions I r.nd II, testing of the Thermal Recombiners Division I and II, control room

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block wall modifications, Vreelan valve inspections, l

installation of motor operated valves for the Emergency Equipment Cooling Water Divisions I and II l

j makeup tank, a system flow balance for EECW and l

l reduction of the amount of Control Room information i

system dots.

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September, 1987 l

Continuation of July 26 Outage - 720.0 hours0 days 0 hours 0 weeks 0 months The maintenance outage continued from last month.

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Repairs to the Feedwater Check Valves, Low Pressure j

Coolant Injection Swing Bus, Vreelan valve Recombiners i

i Division I and II and other work identified as outage i

scope was completed.

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a Enclosuro to NRC-88-0030 Page 9

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o October, 1987

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Continuation of July 26 Outage - 262.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months The maintenance outage ended on October 9.

Repairs to the Feedwater Check Valves, Low Pressure Coolant Injection Swing Bus, Vreelan Valve inapections, and other work identified as outage scope was completed.

After Startup surveillances were completed, the reactor returned to Power Operation. Startup Testing j

continued at power levels below 50 percent of rated thermal power.

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o November, 1987

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d No shutdowns or power reductions o

December, 1987 l

t December 31, forced shutdown - 5.13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months f

During the installation of a Temporary modification, a l

lead gt ounded in error caused a false demand signal for increased feedwater flow. This resulted in a High Reactor Water Level, Turbine Control Valve Fast

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Closure and Reactor Trip. The personnel involved were counselled.

2 3 Fuel Performance l

At the beginning of the year, the plant was operating at i

19% power, with a limit of 20% in the A2 sequence. The j

year ended with the plant shutdown, after a scram from 72%

l power. There were 11 startups during the year, 11 scrams, l

and one controlled shutdown. Total energy generation i

during 1987 was 75.2 Effective Full Power Days (248 4

GWd-thermal). End of year core average exposure was 80.5 l

Effective Full Power Days, with 372 EFPD remaining in the i

j cycle.

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A rod sequence exchange was performed on November 9, 1987 l

1 to change to the B2 sequence. The plant initially exceeded l

20% power on February 23, 1987, and 50% power on l

j December 8, 1987. At the end of the year, power was still l

limited to 755, and TC-5 startup Testing was complete. The fuel thermal limits were maintained within the required

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j spocifications for the entire year.

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Encloruro to-I NRC-88-0030 Page 10 i.

2.4 Shore Barrier Survey l

A survey of the Feral 2 shore barrier was completed on i

August 22, 1987, per Procedure 43 000.01, "Shore Barrier Surveillance", and as required by Technical Specification-373 The results of the survey indicated no damage, significant movement, or deterioration of the barrier. All forty-seven (47) survey point elevations were within the tolerance specified in Technical Specification Table 3 7 3-1.

Civil Engineering Drawings 6C721-44 through 49 1

were revised to incorporate the survey data. No unusual incidents occurred in 1987 that would have required additional surveillance.

r 25 Sarety Relief valve challenges

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There were no Safety Relief Valve challenges during 1987, other than the actuations which occurred during the Safety Relief Valve Test Program.

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NRC-88-0030 Page 11 2.6 Personnel Monitoring and Exposure Pursuant to 10CFR20.407(a)(2), a tabulation of the number of individuals for whom monitoring was provided is shown in Table 2.6-1.

Table 2.6-2 provides a breakdown of radiation exposure by work and job function as required by Technical specification 6.9 1 5(a).

Table 2.6-1 l

Statistical Summary Report of the Number of Individuals for When l

Personnel Monitoring was Provided.

For the Period January 1, 1987 to December 31, 1987 l

NUMBER OF INDIVIDUALS ESTIMATED WHOLE BODY EXPOSURE RANGE IN EACH RANGE (REMS) 3726 No Heasurable Exposure 287 Exposure >

.10 43

.10 to

.25 11

.25 to

.50 0

.50 to

.75 0

.75 to 1.00 0

1 00 to 2.00 0

2.W to 3 00 0

3 00 to 4.00 0

4,00 to 5.00 0

5.00 to 6.00 0

6.00 to 7.00 0

7.00 to 8.00 0

8.00 to 9.00 0

9 00 to 10.00 0

10.00 to 11.00 0

11.00 to 12.00 0

12.00 and Over

Enc'losuro t'o NRC-88-0030 Pcg2 12

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NRC-88-0030 Page 13 l

2.7 Service Life of Main Steam Bypass Line In accordance with Detroit Edison letter VP-86-0154 dated November 7,1986, the cumulative time the Main Steam Bypass Lines are operated with tne bypass valves between 30% and 45% opened will be reported annually. A cumulative value i,

of 100 days is not to be exceeded without prior NRC

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notification.

Evaluations performed by Stone and Webster and by Hopper and Associates conclude that the bypass lines are i

acceptable for safe operation when operated within the 100 i

4 day constraint. Based on these evaluations, the new main l

steam bypass piping that was installed in 1985 has a

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service life which will allow it to remain in service for the life of the plant under anticipated operating t

conditions. The cumulative value for 1987 is 7.9 days, well within the constraint of 100 days.

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2.8 Specific Activity Analysis of the Primary Coolant Exceeding

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the Limits of Technical Specification 3.4.5 i

During 1987 the specific activity of the primary coolant did not exceed the limits of Technical Specification 3 4.5.

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NRC-88-0030 i

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I 2.9 ECCS Outages Pursuant to Fermi 2 Tecnnical Specification 6.9.1 5.o a l

summary of ECCS System Outages which occurred between i

January 1, 1987 and December 31, 1987 is provided. The l

tabulation of ECCS outage hours (Table 2.7-1) includes both forced and planned outages, i

Table 2.7-1 l

ECCS Outage Hours January 1, 1987 to December 31, 1987 ECCS System Forced Hours Planned Hours f

i LPCI Division I 760.5 1571 5 LPCI Division II 84.2 1199 3 Core Spray Division I 38.1 191.6

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Core Spray Division II 94.5 174.5 l

HPCI 1224.7 2281.0 ADS 8.6 0.0 l

ECCS System Outage Division I & II Low Pressure Coolant Injection l

Out of Service fros 0935 2/25/87 to 1204 2/25/87 Duration: 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Forced Outage Outage Summary:

l The Division I & II Low Pressure Coolant Injection systems were declared inoperable when the 42 321.01 surveillance, 72CF bus Auto i

transfer operability test failed.

Investigation found the Manual j

transfer working, subsequently a retest of the Auto transfer was i

successful.

Dirty CMC switch contacts were the suspected cause of the original failure. After a successful performance of 42 321.01 the Division I & II Low Pressure Coolant Injection Systems were returned to service.

ECCS System Outage: Division I & II Low Pressure Coolant Injection Out of Service from 1956 6/25/87 to 0304 6/27/87 Duration: 31.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Forced Outage

I Enclosuro to NRC-88-0030 Page 15 i

Outage Summary:

The Division I & II Low Pressure Coolent Injection systems were declared inoperable when they did not start during a low level transient. Subsequently, the systems' controls ur.d instrumentation were verified functional and the Division I & II LPCI systems were i

1 returned to service.

ECCS Systen Outage Division I & II Low Pressure Coolant Injection j

Out of Service from 0038 6/27/87 to 0236 6/27/87 Duration: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Planned Outage i

Outage Summary:

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The Division i & II Low Pressure Coolant Injection Systems were removed from service to perform Division I & II LPCI logic functional tests. Upon completion of tests the Division I & II Low Pressure l

Coolant Injection Systems were returned to service.

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ECCS System Outage: Division I & II Low Pressure Coolant Injection i

Out of Service from 0430 8/20/87 to 1300 8/21/81 Duration:

32 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage l

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Outage Summary:

l Both Divisions of RHR were removed from service to perfors aaintenance on the actuator and disc "open" limit switches for the E11-F050A valve l

and the actuator "open" limit switch on the E11-F050B valve. The disc "open" limit switch for the E11-F050A was adjusted and both actuator 1

"open" limit switches were replaced. Both divisions of the RHR were returned to service following the limit switch maintenance.

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ECCS System Outi:ge: Division I & II Low Pressure Coolant Injecticn 1

l Out of Service from 1340 8/28/87 to 1445 9/10/87 l

j Duration: 313 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Planned Outage Outage Suasary:

Both ')ivisions of RHR were removed fre service to permit diagnostic testing of the E11-F010 valve, which indicated closed in the control i

room but was in fact partially open, and had to be manually closed, i

Investigation revealed that the closed limit switch is picked up before the valve is fully closed and that operation of the key lock j

switch immediately following "closed" indication would stop the valve prior to it actually closing. By not immediately operating the keylock i

switch upon "closed" indication, the valve operated correctly. While l

the opportunity was available, the E11-F010 valve was checked out 1

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1 Enclo:ura to NRC-88-0030 Page 16 electrically and stroke tested. The outage also provided time to perform a Raychem inspection on valves E11-F017A, E11-F024A, E11-F028A and E11-F010.

No rework was required and both divisions of RHR were returned to service.

ECCS System Outage: Division I & II Low Pressure Coolant Injection Out of Service from 1000 10/2/87 to 1000 10/5/87 Duration: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Planned Outage Outage Summary:

The Division I & II RHR (LPCI mode) was removed from service in order to complete the work required to close out EDP 7906 Rev. A which was to install contactors at 480V switchgear 72C and 72F and also undervoltage lockout and DC monitoring relays at 480V switchgear 72C.

Work was performed by the field to correctly install the undervoltage string circuit and also to show the correct position of the jumper I

installed by the vendor. The system was returned to service after the l

work was performed.

1 ECCS System Outage: Division I & II Low Pressure Coolant Injection Out of Service troe 0700 10/4/87 to *115 10/5/87 Duration: 28.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outage Outage Summary:

l Both Divisions of RHR were removed from service to replace the supports between the pump motor casing and the seal water heat exenanger for all four pumps.

The supports were replaced when vibration data taken indicated the existing support bracket may I

fatigue fail after an extended period of pump operation.

Both l

divisions of RHR were returned to service following the modifications.

I ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0815 3/14/87 to 1220 3/15/87 Duration: 28.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Planned Outage Outage Sunmary:

PHs on E1151 - F601A l

The Division I Low Pressure Coolant Injection was removed from service for preventive maintenance of valve E1151-F601A.

After surveillances on the valve and the system, it was returned to normal service.

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Enclo ure to NRC-88-0030 Page 17 ECCS Systes Outage Division I Low Pressure Coolant Injection Out of Service from 1230 3/15/87 to j630 3/t7/87 Duration: 52 hours6.018519e-4 days 0.0144 hours 8.597884e-5 weeks 1.9786e-5 months Planned Outage Outage Sunnary:

The Division I Low Pressure Coolant Injection was removed from service for preventive maintenance of valve E1150-F602A.

After surveillances the valve and the system was returned to normal service.

ECCS Systes Outage: Division I Low Pressure Coolant Injection Out of Service from 1700 3/17/87 to 1400 3/26/87 Duration: 213 hours0.00247 days 0.0592 hours 3.521825e-4 weeks 8.10465e-5 months Forced Outage Outage Summary:

Division I RHR was declared inoperable when the RHR Inboard Isolation Testable Check Valve E11-F050A did not function by its Test Button.

The limit switches were found to be faulty and were replaced.

Division I RHR was returned to normal operation after the surveillance was successfully conducted.

BCCS Systes Outage: Division I_ Low Pressure Coolant Injection Out of Service from 1525 3/29/87 to 1305 3/29/87 Duration: 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Forced Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was declared inoperable when the RHR pump "C" failed to start in the shutdown cooling mode. The failure was determined to be caused by dirty contacts on the associated CHC switch.

The contacts were cleaned and the Division I Low Pressure Coolant Injection system was returned to service.

ECCS Systee Outage Division I Low Pressure Coolant Injection Out of Service from 1350 5/1/87 to 1411 5/1/87 Duration: 0.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Planned Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service to perfore survoillance 24 321.01, the Remote Shutdown Panel 3L operability test. This test de-energizes the 12EB bus. When the surveillance was complete and the 12EB bus energized, the Division I Low Pressure Coolant Injection system was returned to service.

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Enclosura to NRC-88-0030 Page 18 ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0545 5/2/87 to 1951 5/2/87 Duration:

14.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Forced Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was declared inoperable when it was suspected that the "A" RHR pump motor was wet.

The motor was meggered satisfactorily and the Division I LPCI system was returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0320 6/9/87 to 1610 6/11/87 Duration: 60.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service to perform preventative maintenance on RHR pumps "A" and "C",

RHR room coolers, several valves, and several instruments. Upon completion of the work the Division I Low Pressure Coolant Injection system was returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0650 6/11/87 to 1100 6/11/87 Duration: 4.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Forced Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was declared inoperable when the RHR pump "A" minimum flow valve, E11-F007A, would not stay closed when shut after a pump start.

I&C investigated and found no problems with the minimum flow valve and controls.

The minimum flow valve was tested again and worked successfully; it was concluded that the earlier observed response was proper operation under the condition of insufficient flow to allow valve closure.

The Division I Low Pressure Coolant Injection System was then returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0115 6/27/87 to 1005 6/28/87 Duration:

_32.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage Outage Summary:

The Division I Low Pressure Coolant Irijection system was declared inoperable when the RHR heat exchanger bypass valve, E11-F048A, was I

Enclosure to NRC-88-0030 Page 19 found to have a broken gear and a loose shaft key, thus preventing valve motion in the open and close direction. The actuator was repaired and the Division I Low Pressure Coolant Injection system was returned to service.

ECCS System Outage:

Division I Low Pressure Coolant Injection Out of Service from 1015 8/2/87 to 0840 8/19/87 Duration: 406.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Forced Outage Outage Summary:

Division I RHR was declared inoperable when the E11-F031C check valve leak was discovered.

RHR pump "C" was isolated to prevent leakage into the torus.

The valve disc ar.d seat were reworked resulting in acceptable leakage and Division I RHR was returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection t

Out of Service from 0900 8/21/87 to 0430 9/30/87 Duration: 955.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service to perform several work items and some PMs. Examples are:

Inspection of Raychem heat shrink on motor wiring for actuators of E11-F004A, E11-F004C, E11-F007A, and E11-F027A; Addition of pressure tabs and instruments to Division I Thermal Recombiner blower cooling lines; Replacement of E11-F007A, combined test return line isolation valve; Repair of conduit for E11-F6120A Division I LPCI system injection check valve bypass valve; and, Inspection of various valves under PH program.

Upon completion of all work, the Division I LPCI system was returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0100 10/8/87 to 1420 10/8/87 Duration:

13.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outage Outage Summary:

Division I RHR was removed from service to perform preventive maintenance on the RHR suppression pool containment spray test isolation valve, E11-F028A. The valve was lubed, meggered, inspected and stroke time tested satisfactorily, then returned to service.

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Enclosure to NRC-88-0030-Page 20 ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0340 11/2/87 to 0928 11/4/87 Duration: 53 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was declared inoperable when the "C" RHR pump discharge isolation valve, E11-P034C was found in need of repair. Also, modification of the "C" pump motor terminal box was completed. Upon completion of all work, the Division I LPCI system was returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0930 11/3/87 to 1413 11/3/87 Duration: 4.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Planned Outage Outage Summary:

Division I RHR was removed from service to replace an existing snubber with a strut on pipe hanger E11-3158-035 in accordance with EDP 6264.

Following the work completion ano inspection the Division I RHR system was returned to service.

ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 1215 11/4/87 to 2115 11/4/87 Duration: 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Planned Outage Outage Summary:

RHR pump motor "A" was removed from service to modify the motor terminal box mounting with new bolts, washers and spacers.

RHR pump j

motor "A" was returned to service following the modifications.

j ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 1730 3/17/87 to 1225 3/24/87 Duration:

162.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to facilitate the replacement of the "B" RHR pump.

A PM item was performed on the south RHR EECS cooling unit and the "B" RHR pump was functionally tested. The Division II LPCI system was then returned to service.

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Enclo urs to NRC-88-0030 Page 21 BCCS System Outage: Division II Low Pressure Coolant In;ection Out of Service from 1155 3/30/87 to 0320 4/2/87 Duration: 63.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to repair linear indications found on the snubber reservoir support bracket for snubber E11-3151-G32.

The snubber was located on the "B" RHR heat exchanger bypass line. The Division II Low Pressure Coolant Injection system was returned to service after the snubber was repaired.

ECCS System Outage: Diviaion II Low Pressure Coolant Injection Out of Service from 1500 5/25/87 to 0850 5/27/87 Duration: 41.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was declared inoperable when the RHR pump "B" motor termination box was discovered to have partially broken away from its' mounting due to sheared mounting bolts. The mounting was modified to increase the mounting bolts' depth into the mounting on the motor casing. Upon completion of the work, the Low Pressure Coolant Injection system was returned to service.

ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 2100 6/4/87 to 2140 6/11/87 Duration:

168.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to inspect the RHR pump "D" motor termination box mounting and torque each mounting bolt to a specified valve. The Division II Low Pressure Coolant Injection system was returned to service when the work was complete.

ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 1740 8/13/87 to 0230 8/14/87 Duration: 8.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was declared i

inoperable when a leak was discovered on the "B" RHR pump seal water I

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Enclosurs to NRC-88-0030 Page 22 heat exchanger EECW return line.

The leaking pipe section was replaced and the Division II Low Pressure Coolant Injection system was returned to service.

ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 1030 8/21/87 to 1430 8/23/87 Duration: 52 hours6.018519e-4 days 0.0144 hours 8.597884e-5 weeks 1.9786e-5 months Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to repair the "D" RHR pump suction pressure indicator isolation valve, E11-F0172D. -Upon completion of the repair, the Division II LPCI system was returned to service.

ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 0540 8/24/87 to 2230 8/25/87 Duration: 40.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ~~

Planned Outage Outage Summary:

RHR pump "D" was taken out of service to inspect, lube and test valves E11-F006D and E11-F004D. Division II RHR was returned to service following this preventive maintenance.

ECCS Systes Outage: Division II Low Pressure Coolant Injection Out of Service from 0830 8/29/87 to 1949 9/3/87 Duration:

131 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service for preventative maintenance and other work items as follows:

Inspection of Raychem heat shrink on: E1150-F0178, F028B, F010, F068B, F0168, F004B, F004D, F0078, F024B and F027B; modification of RHR pumps "B" and "D" motor termination box mounting; repair of the system space cooler blower motor's sticking switch MCC 72F-4A Pos.

5AR; repacking of RHR SW punps "B" and "D" discharge valves E1100F012B and D; replacement of RHR Division II Heat exchanger bypass valve's, E1150F048B, missing valve stem indicator, cover, and cap; PM calibrations on various instruments; electrical PMs on various valves; i

meggering of RHR pumps "B" and "D" per the PH program, Upon completion of all PMs, work items and associated testing, the Division II Low Pressure Coolant Injection system was returned to service.

Encloruro to NRC-88-0030 Page 23 ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 1115 9/11/87 to 1910 9/13/87 Duration: 53 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Planned Outage Outage Summary:

RHR Division II was removed from service to rework Raychem splices in the valve motor operators for valves E11-F007P and E11-F0004B.

Division II RHR was returned to service follcaing the wiring rework.

ECCS System Outage:

Division II Low Pressure Coolant Injection Out of Service fraa 0412 9/19/87 to 1036 9/22/87 Duration: 78.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Planned Outage Outage Summary:

Division,II RHR was removed from service to support removal and replacement of the RHR pump "B" and "D" motor termination box cover for vibration testing.

In addition, a Raychem inspection was performed within the RHR pump "B" motor termination box.

The vibration testing was performed to address concerns expressed in response to the failure of 2 bolts on the "B" RHR motor termination cabinet and a leak in the "B" pump seal cooler.

Division II RHR was returned to service following testing.

ECCS System Outage: Division I & II Core Spray Out of Service from 1145 3/26/87 to 1400 3/26/87 Duration: 2 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Forced Outage Outage Summary:

The Division I & II Core Spray systems were declared inoperable, when the design pressure between E21F005A & B, Core Spray Injection Outboard Isolation Valves, was found to be only 500 psig.

This section of pipe was specified by the FSAR to have a 1250 psig rating.

The piping and fittings are the same schedule as the 1250 psig calss piping downstream of E21F005A & B.

A hydrostatic test was planned to be performed on a future convenient date to reclassify the piping to a 1250 psig class. As normal operating status is to have the E21F004 A&B isolation valves locked open and thus preventing that section of pipe from becoming overpressurized, it was decided to return the Division I & II Core Spray systems to service.

ECCS System Outage: Division I Core Spray Out of Service from 0820 8/3/87 to 0443 8/5/87 Duration: 44.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Planned Outage I

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Enclo;uro to NRC-88-0030 Page 24 Outage Summary:

The Division I Core Spray system was removed from service to perform a number of PMs and some planned work items.

Upon completion of all work the Division I Core Spray system was returned to service.

ECCS System Outage: Division I Core Spray Out of Service from 1700 8/9/87 to 0330 8/11/87 Duration:

34.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage Outage Summary:

Core Spray Division I was taken out of service to perform preventive maintenance on the E21-F005A and E21-F031A valves.

Both valves were inspected, lubed and tested.

Each valves' associated MCC breakers were also inspected and tested.

Division I Core Spray was returned to service following the preventive maintenance.

ECCS System Outage: Division I Core Spray Out of Service from 0100 9/14/87 to 2005 9/14/87 Duration:

19.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Planned Outage Outage Summary:

Division I Core Spray was removed from service to perform preventive maintenance.

During the outage, both the core spray pump "A" and "C" motors were meggered, and motor bearings and winding thermocouples were checked. Division I core spray was returned to service following the maintenance.

ECCS System Outage: Division I Core Spray i

Out of Service from 0530 9/25/87 to 1716 9/26/87 Duration: 35.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage Outage Summary:

The Division I Core Spray system was declared inoperable when a Core Spray pump "C" upper motor bearing oil sample was found to have a high moisture content.

The associated oil cooler was tested for leaks and none were found. The bearings were inspected and the oil replaced.

Upon completion of the work the Division I Core Spray system was returned to service.

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Enclosura to NRC-88-0030 Page 25 BCCS Systes Outage: Division I Core Spray Out of Service from 2120 9/29/87 to 0645 10/2/87 Duration: 57.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Planned Outage Outage Summary:

Division I Core Spray system was removed from service to facilitate modifications to the 480V switchgear 72CF (swing bus), and 480V switchgear 72C (Engineered Safety System Division I).

Isolation contactors from 72C and 72F to 72CF were added; undervoltage, lockout and DC monitoring relays were installed in 720. Upon completion of all work the Division I Core Spray system was returned to service.

ECCS System Outage: Division I Core Spray Out of Service from 0113 10/3/87 to 1323 10/4/87 Duration:

36.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Planned Outage Outage Summary:

The Division I Core Spray system was removed from service to replace the Core Spray pumps "A" and "C" coolers' EECW bulged flexible steel hoses with tubing. Upon completion of work and a leak test of the new tubing, the Division I Core Spray system was returned to service.

ECCS System Outage: Division II Core Spray Out of Service from 0600 1/5/87 to 1230 1/6/87 Duration: 30.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s-~

Planned Outage Outage Summary:

Division II Core Spray was removed from service for a preventive maintenance outage. During the outage several instruments were l

recalibrated or cleaned, and PMs were performed on the "B" and "D" pump space heaters. Oil samples were taken on both pumps.

At the completion of the outage Division II Core Spray was returned to l

service.

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ECCS System Outage: Division II Core Spray l

Out of Service from 0400 4/6/87 to 1500 4/7/87 Duration: 35.0 hours0 days 0 hours 0 weeks 0 months Planned Outage Outage Summary:

The Division II Core Spray system was removed from service to perform preventative maintenance on the system's EECW cooling unit and the Division II Core Spray Injection Outboard isolation valve E21-F004B.

When returning the unit coolar to service, the blower motor breaker l

Enclosura to NRC-88-0030 Page 26 HCC 72E-5A Pos 4C-R would not shut.

The breaker latch mechanism was cleaned and adjusted, after which the breaker operated satisfactorily.

The Division II Core Spray system was returned to service when the work was completed.

BCCS System Outage: Core Spray Division II Out of Service from 0915 4/21/87 to 0730 4/22/87 Duration: 22 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outage Outage Summary:

i The Division II Core Spray room cooler temperature controller T4100B020 was taken out of service for preventive maintenance.

Following the surveillance, Division II core spray was returned to service.

ECCS Systen Outage: Division II Core Spray Out of Service from 0915 5/22/87 to 1520 5/22/87 Duration: 6.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Forced Outage Outage Summary:

The Division II Core Spray system was declared inoperable when the Division II Injection valve, E21-F005B, was found to be not operating.

Investigation determined the failure cause to be dirty contacts in the valve motor controller.

After cleaning the contacts and verifying valve operability, the Division II Core Spray system was returned to service.

OCCS Systen Outage:

Division II Core Spray Out of Service from 0245 5/28/87 to 1405 5/28/87 Duration:

11 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Forced Outage Outage Summary:

The Division II Core Spray system was declared inoperable when the "B" Core Spray pump motor heaters were assumed to have failed when noted as "not warm to the touch". An investigation disproved the assumption and verified proper heater function.

Division II Core Spray was subsequently returned to service.

ECCS Systen Outage: Division II Core Spray Out of Service from 1800 6/8/87 to 2050 6/11/87 Duration: 74.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage

Enclosure to NRC-88-0030 Page 27 Outage Summary:

Division II Core Spray was declared inoperable due to the evaluation of DER 87-187 The DER concerns an inadvertant start of Division II Emergency Diesel Generators during a surveillance, namely ECCS Reactor Vessel Water Level functional test, 44.030.254. The Division II Core Spray pumps did not start during the event on 5-28-87.

While determing the Remedial Corrective Action for DER 87-187 on 6-8-87 the Division II Core Spray Logic was concluded to be suspect, and surveillance 44.030.002, Core Spray Division II Logic functional test, was specified to evaluate the system;s logic. Upon successful completion of the functional test, the Division II Core Spray system was returned to service.

BCCS System Outage: Division II Core Spray Out of Service from 0300 8/13/87 to 1850 8/14/87 Duration: 39.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage Outage Summary:

Tne Division Il Core Spray system was removed from service to perform preventative maintenance on the following valves: E21-F031B Div. II CS combined test return valve; E21-F015B Div. II CS full flow test return j

valve E21-F036B Div. II CS suppression pool suction valve; and E21-F005B Div. II CS injection throttle valve.

Following the completion of valve maintenance, the Division II Core Spray system was returned to service.

I ECCS System Outage: Division II Core Spray Out of Service from 1605 10/4/87 to 0508 10/5/87 Duration:

14.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Planned Outage Outage Summary:

The Division II Core Spray system was removed from service to replace the Core Spray pumps "B" and "D" coolers EECW bulged flexible steel i

hoses with tubing. Additionally, both pump motors were meggared as per the preventative maintenance program. Upon completion of the work and a leak test of the new tubing, the Division II Core Spray system was returned to service.

ECCS System Outage:

Division II Core Spray Out of Service fros 0900 10/22/87 to 1746 10/23/87 Duration: 32.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage

Encloruro to NRC-88-0030 Page 28 Outage Summary:

The Division II core spray system was taken out of service to perform preventive maintenance and repairs on the system.

In addition to several instrument recalibrations, the motor space heaters were megered and the AC & DC inverter intake and exhaust air openings were cleaned.

A leaking instrument manifold was replaced with a new manifold. At the conclusion of the outage Division II core spray was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 0210 2/9/87 to 1350 2/23/87 Duration: 340.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Forced Outage Outage Summary:

The High Pressure Coolant Injection system was declared inoperable due to a bad shaft driven oil pump coupling. Several work items and several PMs were performed as follows:

Removal of turbine casing to inspect and replace turbine rotor and shaft driven oil pump coupling; replacement of turbine bearing thermocouple, E41-N211; replacement of HPCI booster pump seal cooling water fitting; inspection of HPCI thrust bearings; replacement of HPCI journal bearings; inspection of various valve actuator motor leads; and performance of several PM calibrations.

Upon completion of all work the HPCI system was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1900 2/26/87 to 0200 3/1/87 Duration: 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months Planned Outage Outage Summary:

i'he High Pressure Coolant Injection system was removed from service to replace a leaking oil flex hose that had been installed under a temporary modification. The leaking fittings were tightened.

j Additionally, the turbine casing and steam inlet valve bolts were retorqued.

The HPCI system was returned to service after all work was complete.

ECCS System Outage: High Pressure Coolant Injeciton Out of Service from 0200 3/1/87 to 0928 3/1/87 i

Duration: 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Forced Outage 1

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a Enclosure to NRC-88-0030 Page 29 Outage Summary:

The High Pressure Coolant Injection system was declared inoperable due to the HPCI outboard steam supply isolation valve, E41-F003, failing to stroke closed for surveillance 24.202.04. Later the valve was stroked closed successfully and the HPCI system was returned to service.

ECCS Systen Outage: High Pressure Coolant Injection Out of Service from 1100 3/2/87 to 0222 3/3/87 Duration:

15.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Forced Outage Outage Summary:

The High Pressure Coolant Injection system was declared inoperable to perform a visual inspection of the inboard and outboard journal bearings.

The bearings were suspected to be damaged due to an observed low lube oil pressure during a turbine coastdown. There was no evidence of bearing damage noted by the inspection. Upon completion of the inspection, the High Pressure Coolant Injection system was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1000 3/4/87 to 1630 3/4/87 Duration: 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Forced Outage Outage Summary:

RPCI was declared inoperable when during a test, the E41-F003 valve tripped on thermal overloads during a simulated auto initiation of the HPCI system. Troubleshooting did not indicate any problem with the valve. The valve was operated successfully two additional times and no problems were encountered. Following the troubleshooting, HPCI was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 0020 3/10/87 to 0030 3/11/87 Duration: 24.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Forced Outage Outage Summary:

HPCI system was declared inoperable due to HPCI oil sample showing high particulate in inop. range.

Reduced lube oil particle count to I

within chemistry limits and returned the system to operable status.

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Enclosure to NRC-88-0030 Page 30 BCCS System Outage: High Pressure Coolant Injection Out of Service from 0400 3/18/87 to 1230 3/23/87 Duration:

128.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Forced Outage Outage Summary:

HPCI system was declared inoperable because of excess flow check valve E41-F503 was not indicating properly at zero psig Rx. pressure.

Check valve indication was restored and after surveillance the HPCI system was returned to normal service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1435 3/25/87 to 1134 3/29/87 Duration: 93 hours0.00108 days 0.0258 hours 1.537698e-4 weeks 3.53865e-5 months Planned Outage Outage Summary:

HPCI system was out of snevice to replace temporary flex pipe on HPCI lube oil line with a permanent hose to clear an earlier temporary modification. The Auxiliary oil pump was run to check for leakages on the new hose. No leaks were found, and HPCI was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1701 4/10/87 to 1647 4/11/87 Duration: 23 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Forced Outage Outage Summary:

The HIgh Pressure Coolant Injection system was declared inoperable due to a fuse blowing in the H21-P080 cabinet. Upon investigation it was determined that the turbine exhaust rupture disc pressure monitor card, E41-N655A, had failed and caused the fuse to blow. The defective card was replaced, calibrated and functionally checked.

The High Pressure coolant Inject 4.on System was then returned to service.

ECCS System Outage: High Pressure Coolant Injection j

Out of Service from 0143 6/3/87 to 0610 6/3/87 Duration: 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform Demo HUA-715, HPCI control system tuning.

This procedure required the vessel injection isolation valve, E41-F006, to be de-energized closed and the CST test return line isolation valve, E41-F011, to be energized open. Upon completion of the Demo and l

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Enclo; urn to NRC-88-0030 Page 31 repositioning of the valves, the High Pressure Coolant Injection system was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1000 6/3/87 to 1256 6/0/87 Duration:

122.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform startup test Demo. HUA.715, HPCI tuning.

Due to the problems encountered in the test, several work items were performed and some other planned work items were completed.

Upon completion of all work the HPCI system was returned to service.

ECCS System Outage: High Pressure Coolant Injection

^ut of Service from 1725 6/8/87 to 2250 6/8/87 ouration: 5.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Planned Outage Outage Summary:

The HPCI system was removed from service to conduct various instrument surveillances. HPCI was returned to service following their completion.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 0514 6/12/87 to 1354 6/18/87 Duration:

152.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Forced Outage Outage Summary:

The High Pressure Coolant Injection system was declared inoperable after it failed to properly perform a cold vessel injection quick start as per STUT.03r.015.

The HPCI turbine tripped repeatedly on overspeed during the attempted cold quick start and subsequently a pressure wave in excess of design pressure was induced in the suction piping.

Inspections of the suction piping found no damage; the suction pressure relief valve was tested and found not to reset.

The relief valve was repaired. The flow controller was troubleshot to find the reason for an apparent loss of the manual tracking function; the controller's connector ribbon cable was determined to be at fault and was replaced.

The High Pressure Coolant Injection system was returned to service when all work was complete.

Enclosura to NRC-88-0030 Page 32 ECCS System Outage: High Pressure Coolant Injection Out of Service from 0015 6/21/87 to 1130 6/22/87 Duration:

35.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform the following work items:

Installation of a spring lift stop in E4100F020, HPCI booster pump suction relief valve; tightening of position indication actuation arms and calibrate position indication limit switches on E41-N504A & B and E41-N505A&B.

Upon completion of all work the HPCI system was returned to service.

ECCS System Outage: High Pressure Coolant Injection i

Out of Service from 1910 6/24/87 to 1325 6/27/87 Duration: 66.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Forced Outage Outage Summary:

The High Pressure Coolant Injection system was declared inoperable i

when during a HPCI startup test the HPCI steam supply outboard isolation valve, E4150-F003 tripped on thermal overload at the end of the open cycle. Testing the valve operator indicated that the open torque switch was set too high and it was adjusted to a lower torque setting. The valve was successfully stroked and the High Pressure Coolant Injection system was returned to service for further startup testing.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 0207 7/1/87 to 0253 7/1/87 Duration: 0.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage Outage Summary:

HPCI was removed from service to perform surveillance 44.020.201, NSSSS-HPCI steam line flow, Division I, functional test; E41-N657A and E41-N660A. HPCI was returned to service following the surveillance.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1320 7/4/87 to 2245 7/18/87 Duration:

345.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Forced Outage Outage Summary:

The High Pressure Coolant Injection system was declared inoperable when it failed to attain full rated flow within the required time for i

a Enclo;ure to NRC-88-0030 Page 33 a quick start. Work items were initiated to correct the problem; other work items were performed to repair some previous piping damage and a few miscellaneous deficiencies.

There were also a large nurber of I&C, Electrical and Mechanical PMs performed. Upon completion of all work the HPCI system was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1245 7/19/87 to 1820 7/19/87 Duration: 5.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Planned Outage Outage Summary:

The HPCI system was removed from service to support startup testing of the system. The E41-F011 valve was de-energized open and the E41-F006 valve was de-energized closed to obtain a flowpath to the CST for a simulated HPCI quick start. HPCI was returned to service following the test.

ECCS Systen Outage: High Pressure Coolant injection Out of Service from 0630 7/25/87 to 1505 7/28/87 Duration: 80.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Planned Outage Outage Summary:_

HPCI was removed from service to replace the position limit switches on HPCI stop valve that initiate the Ramp Generator Signal Converter ramp. The deadband on the original switches was sufficient to decay the RGSC ramp enough to impact the time to rated flow criteria of 25 seconds.

In addition, the opening circuit of valves E41-F022, E41-F059 and E41-F600 were modified such that when the valves reach the full open position, the valve motor is stopped by the opening limit switch, preventing the valves from damaging themselves by backseating. During the outage, a pressure gauge was installed on the suction line of the auxiliary oil pump to support diagnostic startup testing efforts. Following completion of the above modifications, HPCI was returned to service.

ECCS System Outage: High Pressure Coolant Injection i

Out of Service from 0015 7/28/87 to 0930 7/28/87 Duration: 9 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outa6e Outage Summary:

HPCI was removed from service to recalibrate the discharge flow transmitter E41-N008 loop. The flow transmitter input to GETARS was

d Enclosurs to NRC-88-0030 Page 34 about 180 gpa at zero flow, resulting in an unnecessary time penalty when evaluating time to rated flow for startup testing.

The transmitter was recalibrated and HPCI was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1430 8/1/87 to 1610 8/1/87 Duration:

1.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform the HPCI Division II steam flow functional test, 44.020.202.

When completed, the HPCI was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1900 8/4/87 to 2049 10/11/87 Duration:

1729.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Planned Outage Outage Summary:

HPCI was removed from service for maintenance on the following items:

Raychem !.nspections on E41-F003, E41-F002, E41-F006, rework cable to E41-F002, replace motor to E41-F079, rotate the operator for E41-F006, rework torque switch settings for E41-F001, E41-F002, E41-F003, E41-F006, E41-F007, E41-F012, E41-F041, E41-F042, E41-F075 and E41-F079 to prevent backseating, perform PHs on E41-F042, install T-drains and grease reliefs on E41-F003, E41 7006, E41-F042 and E41-F600, terminal box inspection for E41-C005, rework limit switches on E41-F008 and E41-F011, replace HPCI suction pressure switch, the HPCI discharge flow transmitter E41-N008 and steamline flow differential pressure Lansmitter E41-N057B, repack E41-F011 and perform various HOVATS testing. Following completion of the outage, HPCI was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 2210 10/23/87 to 0319 10/24/87 Duration: 5.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Planned Outage Outage Summary:

HPCI was removed from service to perform surveillances 44.020.201, NSSSS-HPCI steamline flow, Division I, functional test; E41-N657A and E41-N650A and 44.020.203, NSSSS-HPCI steamline flow, Division I, calibration; E41-N657A and E41-N660A. Following the surveillances, HPCI was returned to service.

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a Enclosure to NRC-88-0030 Page 35 ECCS System Outage: High Pressure Coolant Injection Out of Service from 2154 11/5/87 to 2225 11/5/87 Duration: 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Planned Outage Outage Summary:

HPCI was removed from service to perform surveillance 44.020.202, NSSSS HPCI steam line flow, Division II, functional test; E41-N657B and E41-N660B. HPCI was returned to service following the surveillance.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1940 11/11/87 to 0050 11/12/87 i

Duration: 5.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Forced Outage Outage Summary:

The High Pressure Coolant Injection system was declared inoperable when a packing leak was discovered on the HPCI turoine steam supply valve, E41-F0001.

After tightening the packing gland nuts and stroke time testing the valve, the HPCI system was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1735 12/1/87 to 1813 12/1/87 Duration: 0.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Planned Outage Outage Summary:

HPCI was removed from service to conduct surveillance 44.030.155, ECCS-HPCI suppression pool level functional test; E41-N662B ated

{

E41-N662D.

HPCI was returned to service following the surveillance.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 1045 12/2/87 to 1320 12/3/87 Duration:

26.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform a PH calibration of the HPCI pump discharge pressure indication loop.

When complete, the HPCI system was returned to service.

ECCS Systes Outage: High Pressure Coolant Injection Out of Service from 2210 12/4/87 to 1042 12/9/87 Duration:

108.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Forced Outage

(-

. V Enclosura to NRC-88-0030 l'

Page 36 D

Outage Summary:

The High Pressure Coolant Injection system was declared inoperable when it was noted that the setpoint for the high HPCI pump suction pressure alarm specified by the I&C calibration instructions different from the Technical Specifications and MIL alarm setpoints. The answer to the associated DER cleared the discrepancy by noting the head correction was included in the I&C calibration value. The HPCI system was therefore returned to service, a

ECCS System Outage: High Pressure Coolant Injection Out of Service from 0330 12/14/87 to 2330 12/17/87 Duration: 92 hours0.00106 days 0.0256 hours 1.521164e-4 weeks 3.5006e-5 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to conduct a large numbers of PM work items. Other work items were also performed during the outage.

Upon completion of all work, the HPCI system was returned to service.

ECCS Systen Outage: High Pressure Coolant Injection Out of Service from 0830 12/21/87 to 2048 12/21/87 Duration:

12 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform a PM on the logic for the HPCI CST test return line isolation valve, E41-F011. When completed, the HPCI system was returned to service.

ECCS Systen Outage: Automatic Depressurization Out of Service from 1414 6/19/87 to 2250 6/19/87 Duration: 8.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Forced Outage Outage Summary:

The Automatic Depressurization system was declared inoperable when the ADS High Drywell pressure reset switch in panel H11-P601 surface "A" was found loose and came in contact with the "B" Inboard HSIV, B21-F0228, test switch.

This resulted in a closure of B21-F022B and a seal in of the ADS High Drywell pressure logic.

After correcting the loose switch, resetting logic and testing the associated components, the Automatic Depressurization system was returned to service.

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8. Ralph SyMa Group V ce Pre 9 dent Ec ison =400NorthDmeHghway 6

=-

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February 29, 1988 NIC-88-0030 U. S. Ibclear Regulatory Comission Attn: Document Control Desk 4

Washington, D. C.

20555 l

Reference:

Fermi 2 NIC Docket No. 50-341 NIC License No. IPF-43

Subject:

1987 Annual Coeratino Report for Fermi 2 In accordance with Fermi 2 'Ibchnical Specification 6.9.1.4 and b. S.

IUC Regulatory Guide 1.16, the Detroit Mison Conpany is submitting the Annual Operating Report for the Fermi 2 tuclear Power Plant for the period of January 1,1987 through Decenber 31, 1987.

The 1987 Fermi 2 Annual Operating Report also satisfies the reporting requirements of 10CFR20.407, Personnel Monitoring Report, Technical Specificatico 6.9.1.5.a (Annual Exposure Report by function),

t Technical Specification 6.9.1.5.b (Safety / Relief Valve Challenges),

Technical Specification 6.9.1.5.c (Emergency Core Cooling Systen Outages), and Technical Specification 6.9.1.5.d (Specific Activity Analysis of the Primary Coolant). In addition, the 1967 Annual Operating Report includes a section on Service Life of the Main Steam Bypass Line. This satisfies the commitrent stated in Detroit Mison letter VP-86-0154 dated tbvenber 7,1986.

j i

If you have any questions or coments regarding this r@ ort, please contact Mr. Girija Shukla at (313) 586-4270.

j Sincerely, Enclosure cc: Mr. A. B. Davis Mr. E. G. Greenman Mr. J. G. Keppler W

Mr. T. R. Quay

/

Mr. W. G. Rogers US!UC Region III l

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NRC-88-0030, Annual Operating Rept,Jan-Dec 1987

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