NRC-89-0036, Annual Operating Rept for Fermi 2 for Jan-Dec 1988

Annual Operating Rept for Fermi 2 for Jan-Dec 1988

ML20235R003
Person / Time
Site:	Fermi
Issue date:	12/31/1988
From:	Sylvia B DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-89-0036, CON-NRC-89-36 NUDOCS 8903030110
Download: ML20235R003 (22)

Text

I-i.

4

^ '

e

,I l-s FERMI 2 ANNUAL OPERATING REPORT JANUARY 1 - DECEMBER 31, 1988 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPER'ATING LICENSE NO. NPF-43 i

i y

e y

R

a

, . Enclosure to

. NRC-89-0036 Page 2 i

Table of Contents P_agg 1.0 Introduction ........................................ 3 l

2.0 Summary of Operating Experience . . . . . . . . . . . . . . . . . . . . . 3 l

l i

2.1 Summary of Operating Experience ................ 3 l

1 2.2 Summary of Outages and Forced Reductions i Greater than 20 Percent of Full Power ........ 4  !

23 Fuel Performance ............................... 8 l 2.4 Shore Barrier Survey ........................... 8 2.5 Safety Relief Valve Challenges ................. 9 l 2.6 Personnel Monitoring and Exposure .............. 10 27 Service Life of Main Steam Bypass Line ......... 12 i 1

2.8 Specific Activity Analysis of the Primary Coolant .............................. 12 2.9 ECCS Outages ................................... 12 I

i l

l i

}

J

1

, Enclosure to

. NRC-89-0036 Page 3-l l

1.0 Introduction j The Fermi 2 Nuclear Power Plant site is located on the western I 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 plant is owned jointly by the Detroit Edison Company (approximately 90 ,

percent) and the Wolverine Power Supply Cooperative, Incorporated l (approximately 10 percent.) Detroit Edison has reached agreement i with Wolverine Fower 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 l

2.1 Summary of Operations '

This summary covers the operation of Fermi 2 for the period from January 1, 1988 to December 31, 1988. At the beginning of 1988, Fermi 2 was restricted to the seventy-five percent (75%) power level. On January 15, 1988, the NRC issued authorization to operate at one hundred percent (100%)

power. After operating the plant for one hundred consecutive hours at greater than ninety percent (90%)

power, Fermi 2 achieved commercial status on January 23, 1988.

On February 27, 1988, Fermi 2 shut'down as required by i Technical Specifications approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> before the scheduled Main Steam Isolation Valve (MSIV) closure test was to occur. The plant entered a Local Leak Rate Testing I outage which continued until mid-May. During this outage,  !

extensive work was performed on the moisture separator '

reheaters.

On May 23 and July 13 of 1988, Fermi 2 experienced contamination of certain areas of the reactor building due to the failure of several compression fittings. Cleanup efforts have restored the plant to near normal conditions.

i

. Enclosure to N'RC-89-0036 Page 4 ]

I The plant operated until late July when a Technical Specification requirement called for shutdown of the plant due to increased unidentified leakage in the drywell.  ;

Operation was resumed in early August.

In late August, startup testing uncovered problems with the l torque switch settings on a Low Pressure Coolant Injection  !

(LPCI) system loop select valve (Recirculation' System Pump B discharge valve) which consequently required a shutdown of the plant until early October. During that period of time i the torque and limit switch settings on safety-related motor operated valves were re-evaluated and adjusted as necessary.

On November 1, 1988, Fermi 2 successfully completed the MSIV closure test and remote shutdown from outside the Control' Room. After returning to operation on November 8, 1988,  ;

Fermi 2 ran the remainder of the year without any more significant outages. The warranty run was completed on November 18, 1988, which concluded the Startup Testing Program.

Since achieving commercial' status in January of 1988, Fermi 2 has generated 4,060,056 MWH (net) and has had an availability rating of 57.2% for the year. The unit was in a forced outage for 21.4% of the time since achieving commercial status.

2.2 Summary of Outages and Forced Reductions Greater than 20 Percent of Full Power January, 1988 1

Continuation of December 31 forced shutdown - 207.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> J I

i During the installation of a temporary modification, a lead grounded in error causing a false demand signal for increased feedwater flow. This resulted in high reactor water level, turbine control valve fast closure and a reactor scram. Corrective actions included counselling the individuals involved and revising the temporary modification procedure. Reported as LER 87-056 dated January 30, 1988.

1 Before resuming power ascension it was discovered that the Average Power Range Monitors (APRM) setdown trip had been l procedurally set too high. The APRM seldown trip was  !

recalibrates and the applicable procedure revised.

. Enclosure to

. NRC-89-0036 Page 5 January 10, forced shutdown - 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> The power supply to the North Reactor Feed Pump speed controller failed. This resulted in a low reactor vessel level scram. The power supply was replaced.

February, 1988 February 27, forced shutdown - 13 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> scheduled outage - 57.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Fermi 2 was shutdown hours before a scheduled Local Leak Rate Test (LLRT) outage. A review of the Emergency Diesel Generator (EDG) surveillance procedures revealed that the j functional tests of the EDG buses did not meet all of the  :

requirements of the Technical Specifications. Corrective )

actions were to revise the surveillance procedures to include additional logic system functional testing. The surveillance procedures were completed successfully. The plant entered the scheduled Local Leak Rate Testing outage.

March, 1988 i Scheduled outage - 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> l

An outage had been planned to complete Local Leak Rate Tests l (LLRT) required by Technical Specifications, complete specific plant modifications (Engineering Design Packages and Potential Design Changes) that would enhance plant availability, bring the plant current with preventive maintenance requirements, and complete specific corrective maintenance activities. All eighteen month surveillance procedures (completion due dates up to June, 1989) that had the potential to challenge plant safety systems if performed while at power were added to the scope. All work was to be done without the traditional Reactor Pressure Vessel (RPV) head removal. This necessitated divisionalization of the outage and planning work to ensure that two suitable methods of decay heat removal were available at all times.

The Moisture Separator Reheaters (MSRs), Mair. Steam Condenser, and Condensate Pumps were all suspected to have problems associated with them before the outage began and were examined early in the outage. Investigation revealed that the MSRs had sustained flow induced damage which included damage to the primary and secondary steam distribution plates (including their supports) and the

a

, . Enclosure to NRC-89-0036 Page 6 de-mister pads. Damage' discovered during the outage was repaired.

MOVATS testing was performed during the outage. This a diagnostic device uncover (d a " hydraulic locking" that did, i or could, exist in Limitorque operators. As a result, all f fast-acting valves had their spring packs removed and l cleaned and the actuator grease replaced. I April, 1988 Continuation of scheduled LLRT outage - 719 hours0.00832 days <br />0.2 hours <br />0.00119 weeks <br />2.735795e-4 months <br /> May, 1988 Continuation of scheduled LLRT outage - 314 hours0.00363 days <br />0.0872 hours <br />5.191799e-4 weeks <br />1.19477e-4 months <br /> Prior to synchronizing the turbine at the end of the outage three scrams occurred. First, a raccoon climbing the system  !

transformer caused a ground fault. In accordance with i Technical Specifications, a manual scram was initiated since reactor pressure was less than 300 psig. Second, operators performed a HPCI automatic transfer surveillance which directed feedwater flow to the condensate storage tank. The resultant low vessel level caused a scram signal. Finally, f while testing the electrical overspeed protection to the turbine generator, a relay failure caused the main steam bypass valves to close. A high pressure scram resulted. j The relay was replaced. l l

May 28, scheduled power reduction - 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> l Reactor power was reduced during the isolation of the Reactor Water Cleanup (RWCU) system for completion of a routine surveillance test. The power reduction was necessary to maintain reactor coolant sulfate levels below 3 l EPRI guidelines. Power was increased upon restoration of the RWCU system.

June, 1988  ;

No outages or forced reductions  !

l

(  !

1

1

, . Enclosure to

. NRC-89-0036 Page 7 i l

July, 1988 July 23, forced shutdown - 206.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> I

Unidentified leakage in the drywell increased until shutdown of the plant was necessitated in accordance with Technical Specifications. Two valves which were leaking were repaired and some items on the forced outage schedule were worked.

August, 1988 )

Continuation of July 23 forced shutdown - 170 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> August 8, forced power reduction - 29 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> A steam leak from the separator seal tank developed. Power was reduced and the turbine tripped to make the necessary repairs.

August 13, forced outage - 37.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> {

t A high vibration signal on turbine bearings 8 and 9 was -(

received. An automatic scram occurred per design. A 1 temperature control valve for the main lube oil coolers had i failed open. The valve was repaired, l l

August 21, forced outage - 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> During scheduled Startup Testing, the Low Pressure Coolant Injection (LPCI) loop select logic was declared inoperable due to the inability to close Recirculation Pump B Discharge 1 Valve B31-F0138. Three of the four valve operator leads I were found to be loose and were tightened. 1 August 28, forced outage - 77.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> The LPCI loop select logic remained inoperable due to the inability of the B31-F013B valve to close. It was I discovered that the torque switch was not properly reset following replacement of the operator in 1984.

September, 1988 Continuation of August 28 forced outage - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />

, . Enclosure to NRC-89-0036 Page 8 October, 1988 l I

Continuation of August-28 forced outage - 169 hours0.00196 days <br />0.0469 hours <br />2.794312e-4 weeks <br />6.43045e-5 months <br /> '!

l November, 1988 s November 1, scheduled shutdown - 168.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Performed Main Steam Isolation Valve (MSIV) closure test from full power and remote shutdown from outside the Control Room as part of the Startup Test program. The Startup Test program was completed November 8, 1988. ,

December, 1988 No outages or forced reductions.

23 Fuel Performance i

At the beginning of the year, the plant was in cold shutdown. The year ended with.the plant operating at. full power in the A2 control rod sequence. 'There were 11 startups, 4 scrams, and six controlled shutdowns. Total {

energy generation during 1988 was 173.4 Effective Full. Power  !

Days (EFPD). End of year core exposure was 254.6 EFPD, with 192.6 EPPD remaining in the cycle. The longest period of .

continuous critical operation was 72 days from May 12, 1988 I to July 23, 1988.. '

Control rod sequence exchanges occurred while shutdown on May 5, 1988 (B2 to A1) and August 6, 1988 (A1 to B1). A sequence exchange was performed at 45% power on December 17, 1988 (B1 to A2). At the end of the year, there were no power restrictions and startup testing was complete. The '

fuel thermal limits were maintained within the required specifications for the entire year. There were no indications of failed fuel rods.

2.4 Shore Barrier Survey A survey of the Fermi 2 shore barrier was completed on October 20, 1988, per Procedure 43 000.01, " Shore Barrier Surveillance", and as required by Technical Specification.

3 7.3 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 E _____ _ ___ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . _ _ _ - - - - - - - . - - - - - - .

, Enclosure to NRC-89-0036 Page 9 3 7 3-1. Civil Engineering Drawings 6C721-44 through 49 were revised to incorporate the survey data. No unusual incidents occurred in 1988 that would have required additional surveillance.

2.5 Safety Relief Valve Challenges A Full Reactor Isolation was performed in Test Condition Six at 98.1% Core Thermal Power (CTP) to deteratine the transient '

behavior of the Reactor during and subsequent to a simultaneous fast closure of all Main Steam Isolation Valves '

(MSIV). The test simulated low Main Steam Line pressure and resulted in a Group I isolation.

The resulting pressure and water level transients were i observed to assess the adequacy of system response to that predicted by the Transient Safety Analysis Design Report (TSADR). As a result of this testing, the following safety relief valve actuations occurred:

SRV "A" (1'1108) -

tailpipe pressure switch actuation - k

. duration 92 seconds. }

"A" SRV -

rescated at pressure of 913 2 psig.

2nd SRV actuation -

Reactor Pressure Vessel pressure 1021.1 psig.

Low-Low set SRV "A" -

duration 153 seconds. Rescat at 913.2 psig.

SRV "B" (1110#) -

tailpipe pressure switch actuation - ,

duration 14 seconds. .

SRV "C" (1110#) -

tailpipe pressure switch actuation -

duration 13 seconds.

SRV "G" (1110#) -

tailpipe pressure switch actuation -

duration 48 seconds.

SRV "G" -

reseat pressure 913 2 psig (Note:

"G" did not reopen since "A" functioned as designed for the low-low set logic).

SRV "H" (1130#) -

tailpipe pressure switch actuation - p ,

duration 2.5 seconds.

SRV "J" (11308) -

tailpipe pressure switch actuation -

duration 4 seconds.

. . Enclosure to NRC-89-0036 Page 10 The relief valves that opened or were opened during the MSIV test did reclose, but some " weeping" existed as evidenced by the failure of SRVs A, K, H, J, and R discharge temperatures to return to within 10 F of the temperature recorded prior to MSIV closure. (Note: SRVs "K" and "R" did not automatically open during this test but were manually actuated.) After the return of the plant to power operation, only SRVs "A" and "M" still showed weeping. This information is under evaluation and will be resolved by the In-Service Inspection organization. o 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 breakdovn of radiation exposure by work and job function as required by Technical Specification 6.9.1.5(a).

Table 2.6-1 Statistical Summary Report of the Number of Individuals for Whom Personnel Monitoring was Provided For the Period 1 January 1, 1988, to December 31, 1988 NUMBER OF INDIVIDUALS FSTIMATED WHOLE BODY EXPOSURE RANGE IN EACH RANGE (REMS) 2002 No Measurable Exposure 648 Exposure < .100 1 214 .100 to .249 77 .250 to .499 22 500 to 749 l 3 .750 to 999 1 1.000 to 1.999 0 2.000 to 2.999 0 3 000 to 3 999 l 0 4.000 to 4.999 5.000 to 5.999 0

0 6.000 to 6.999 0 7.000 to 7.999 0 8.000 to 8.999 0 9.000 to 9.999 l

0 10.000 to 10 999 0 11.000 to 11.999 0 12.000 and Over i

...-__.-__a

ss rr oe 00732 1 6025 67043 38073 09069 00000 01 722 2 6

t h 1 4585 62008 68767 50393 91 220 00000 88775 ct 61 823 30885 09300 00000 521 69 6 aO r

01 032 401.7 3

1 032 4 4971 1 4 1 3 0 t d 1 2 4 6 nn oa C

m 00009 70005 00000 20090 00000 00000 90094 2 e 00000 30000 00000 30000 00000 00000 60001 9 R s 00000 00000 00000 00000 00000 00000 0 ye 0 0 0.C.0 nt e aiy Ml o i l l t p aUm t E o

T s

ne 39304 71 480 90909 20062 561 54 64208 80450 1 5831 1 4730 4301 0 00000 00000 69436 24692 8

5 4eey 25049 40031 24613 62272 00200 00000 621 66 3 c .

'a t p i 1 00 1 1 2 1 4 2 91 31 1 1 1 7

3 Sm E

N O

I T

C N

U F8 8

V/ ss B1 rr 2

T/

3 moe R2 et h 26400 20000 50004 5321 0 01 1 00 00000 4071 4 6 6 R ct 1 2 1 01 1 2 442 1 2

O1 P mao r 1 1 2 E o 0td E Rt 0nn L

E8 1 oa B C A R8 >

T U/

S1 l O0 e s P/ nye X1 nt e 00000 00000 00000 00000 00000 00000 00000 0 E0 oiy L sl o Q ri et lp U PUm N E W f Q o r s ene 6 boe 56803 40000 30001 401 1 0 00000 00000 6691 4 0 miy 32 1 1 - 233 1 ut o N al t p S m E

n l l l l l t l oe e e e e e s e i c n n n n n n n t nl nl l l nl t l nl l l nl l l n! l l i

rl l l nl l icaenl oee e oee e oee e oee e oee e oee e oee l

ul nernn snn nl snn nernn nl snn nernn nl snn nernn nl snn nernn nl snn nernn n. l snn rernn Fi oneoo oneoo noneoo oneoo oneoo oneoo oneoo esnPss esnP ss osnP ss esnP ss snP ss snP ss snP ss bvro rr cro rr i ro rr cro rr ro rr ro rr ro rr oressee nessee t essee nessee essee essee essee J uP rcPP aPrcPP cPrcPP aP rcPP gP rcPP P rcPP P rcPP S ei n ei e ei n ei n ei ei ei

& eP syg eeP syg pep syg eeP syg ieP syg eP syg eP syg

&c yrn t c yrn sc yrn t c yrn sc yrn c yrn c yrn k nghoi n n gh oi nnghoi nngh oi snghoi nghoi nghoi s rsanP sr i anP sr I anP sr i anP sr eanP sr anP sr anP sr l opni ie ani ie ni i e ani i e cni ie ni ie ni ie a WOet hve Met h ve eet hve Met h ve oet hve get hve et h ve t t at rn t at rn ct at rn t at rn rt at rn nt at rn t at rn o rnrl ei enrl ei i nrl ei l nrl ei P nrl ei i nrl ei nrl ei T oieapg nieapg vieapg aieapg i eapg l i eapg sieapg t apeun i apeun rapeun i apeun eapeun eapeun l apeun d cMOHSE tMOHSE eMOHSE cMOHSE t MOHS 2 uMOHSE aMOHSE n a u s e s f t a

_ e o n p a e o r R R I S W R T G

1

. Enclosure to WRC-89-0036 Page 12

)

2.7 Service Life of Main Steam Bypass Line i

In accordance with Detroit Edison letter VP-86-0154 dated j November 7,.1986', the cumulative time the Main Steam Bypass -

Lines are operated with the bypass valves between 30% and 45% opened will be reported annually. A cumulative value of j 100 days is not to be exceeded without prior NRC notification.

Evaluations performed by Stone and Webster and by Hopper and Associates concluded that the bypass lines are acceptable for safe operation when operated within the 100 day constraint. Based on these evaluations, the new main steam bypass piping that was installed in 1985 has a service life which will allow it to remain in service for the life of the q plant under anticipated operating conditions. The i cumulative value for 1988 is 4.9, well-within the constraint of 100 days.

2.8 Specific Activity Analysis of the Primary Coolant Exceeding the Limits of Technical Specification 3 4.5 i

During 1983 the specific activity of the primary coolant did {

not exceed the limits of Technical Specification 3 4.5 I l

2.9 ECCS Outages 1 l

Pursuant to Fermi 2 Technical Specification 6.9.1.5.c, a summary of ECCS System Outages which occurred between January 1, 1988 and December 31, 1988 is provided. The tabulation of ECCS outage hours (Table 2 9-1) includes both forced and planned outages for the Core Spray, LPCI, ADS, and HPCI systems. An outage was considered to be whenever j one of the ECCS systems was out-of-service at a time it was l required to be operable per Technical Specifications.

1 1

, Enclosure to NRC-89-0036 Page 13 Table 2.9-1 ECCS Outage Hours January 1, 1988 to December 31, 1988 ECCS System

~-~

Forced Hours Planned Hours LPCI Division I 9.7 293 5 LPCI Division II 478 3 185.4 Core Spray Division I 0.3 131.2 Core Spray Division II 12.7 68.8 HPCI 42.9 205.9 ADS 95.5 0.0 ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0618 2/11/88 to 2355 2/13/88 Duration: 65.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Planned Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service to perform Preventive Maintenance (PM) on pumps "A" and "C".

Following completion of the PM tasks and required surveillance tests, 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 0230 5/14/88 to 2225 5/16/88 Duration: 67.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Planned Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service to perform Preventive Maintenance (PM) on RHR pump "A" and miscellaneous other tasks. Following conpletion of the PM tasks and required surveillance tests, the Division I Low Pressure Coolant Injection system was returned to service.

l l

1

_ _ _ _ _ ________-_____________-______________.__-_------------_------J

. Enclosure to-NRC-89-0036 Page 14 ECCS System Outage: Division I Low Pressure Coolant Injection Out of Service from 0500 10/18/88 to 2100 10/24/88 Duration: 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> Planned Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service for various Preventive Maintenance (PM) tasks, (i.e., Hi-Pot tests, visual inspections, temperature detector recalibration, etc.).

Upon completion of the scheduled PM tasks, 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 10/26/88 to 1959 10/26/88 Duration: 9.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Forced Outage Outage Summary:

The Division I Low Pressure Coolant Injection system was removed from service to replace a Rosemont trip unit (E11-N655A) for RHR Pump "A" i input into the Automatic Depressurization System (ADS) logic. The work request was completed and the RHR Pump "A" Discharge Pressure

( ADS Permissive) calibration surveillance was run successfully. The Division I Low Pressure Coolant Injection system was returned to service.

ECCS System Outage: Division II Low Pressure Coolant Injection

, Out of Service from 1938 1/9/88 to 2311 1/9/88 Duration: 3 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to perform a routine surveillance test. Following completion of the surveillance test, the Division II Low Pressure Coolant Injection system was returned to service.

~

, Enclosure to NRC-89-0036 l

Page 15 1g ECCS System Outage: Division II Low Pressure Coolant Injection  !

Out of Service from 1349 1/10/88 to 1458 1/10/88 1 Duration: 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service when RHR pumps "B" and "D" were inadvertently placed in the "Off/ Reset" position while preparing to place Division II RHR in )

shutdown, cooling. Both Pumps "B" and "D" were placed back in the ]

" Auto" position and the Division II Low Pressure Ccolant Injection system was returned to service.-

i ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 0457 2/23/88 to 2323 2/25/88

, Duration: 66.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Planned Outage l l Outage Summary:

l 1

]

\

The Division II Low Pressure Coolant Injection system was removed from service to perform Preventive Maintenance (PM) on the pump motors (meggering, cleaning and inspection) and the room cooler. Following completion of the PM tasks and required surveillance tests, the )

l Division II Low Pressure Coolant Injection system was returned to service.

l l

l 1 l ECCS System Outage: Division II Low Pressure Coolant Injection i Out of Service from 0355 4/9/88 to 2330 4/13/88 Duration: 115.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from 1 service to repair a cracked and leaking weld on the pump "D" suction line tap for E11-F160D. The crack developed as the result of running the pump dead-headed for approximately 30 minutes. The weld was repaired and the pump returned to service.

l l

l l

L___________--.__.

I I

. Enclosure to '

NRC-89-0036 Page 16 EC*S System Outage: Division II Low Pressure Coolant Injection Out cf Service from 2300 6/25/88 to 2330 6/28/88 Duration: 72.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service after failing a surveillance test due to an indicated flow of less than 10,000 gpm. A work request was initiated and completed to correct the flow indication problem. The surveillance test was performed again successfully. 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 0800 8/10/88 to 0050 8/13/88 Duration: 64.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to perform various Preventive Maintenance (PM) tasks.

Following completion of the PMs and required surveillance tests, the Division II Low Pressure Coolarit Injection system was returned to  !'

service.

ECCS System Outage: Division II Low Pressure Coolant Injection ~

Out of Service from W 30 8/13/88 to 1515 8/13/88 fj Duration: 8.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Planned Outage

' i Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from j service to perform Preventive Maintenance (PM) on RMR pump "D" and I valve B31-F004D. Following completion of the PM tasks and required i surveillance tests, the Division II Low Pressure Coolant Injection system was returned to service.

. Enclosure to NRC-89-0036 Page 17 ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 1325 8/15/88 to 1053 8/16/88 Duration: 21.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Planned Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service to perform selected Preventive Maintenance (PM) tasks on RHR pump "D". Following completion of the PM tasks and required surveillance tests for RHR Pump "D", 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 1640 8/20/88 to 1227 8/21/88 Duration: 19.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service when the Recirculation Pump B Discharge Valve (B31-F031B) would not close following pump trip for a Test Condition 4 Startup test. Valve inspection indicated that three of four valve operator leads were loose. The loose leads were tightened 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 1450 8/28/88 to 2019 9/8/88 Duration: 269.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Forced Outage Outage Summary:

The Division II Low Pressure Coolant Injection system was removed from service when the B31-F0318 valve again would not close while performing the Startup Test. As a result, a generic inspection of selected MOVs for torque and limit switch settings was initiated. The valve torque and limit switch settings were corrected and the valve passed its required tests. The Division II Low Pressure Coolant Injection system was returned to service.

, Enclosure to i

NRC-89-0036 Page 18 ECCS System Outage: Division II Low Pressure Coolant Injection Out of Service from 0550 10/28/88 to 0205 10/29/88 Duration: 20 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Planned Outage Outage Summary [

The Division II Low Pressure Coolant Injection system was removed from service to perform various Preventive Maintenance (PM) tasks (relube, oil change) on RHR cooling tower fans "B" and "D". Upon completion of the PM tasks, Division II Low Pressure Coolant Injection was returned to service.

ECCS System Outage: Division I Core Spray Out of Service from 0600 1/12/88 to 2255 1/12/88 Duration: 16.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Planned Outage Outage Summary:

The Division I Core Spray system was removed from service to perform Preventive Maintenance (PM) on the room cooler and various valves.

Following completion of the PM tasks and required surveillance tests, the Division I Core Spray system was returned to service.

ECCS System Outage: _ Division I Core Spray Out of Service from 2306 3/26/88 to_0119 3/27/88 Duration: 2.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Planned Outage Outage Summary:

The Division I Core Spray system was removed from service to perform routine surveillance testing. Upon completion of the test the Division I Core Spray system was returned to service.

ECCS System Outage: Division I Core Spray Out of Service from ~d528T/58/8'8 to 0300 7/1/F8 Duration: 69.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Planned Outag.e Outage Summary:

The Division I Core Spray system was removed from service to perform l Preventive Maintenance (PM) on Core Spray Pump "C" and the room i cooler. Following completton of PM tasks and required surveillance tests, the Division I Core Spray systera was returned to service.

I

. Enclosure to c NRC-89-0036 Page 19 ECCS System Outage: Division I Core Spray Out of Service from 1415 9/13/88 to 1430 9/13/88 Duration: _ 0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Forced Outa3e_

Outage Summary:

1 The Division I Core Spray system was removed from service when valve E21-F007A was inadvertently closed. The valve was re-opened j immediately and the Division I Core Spray system was returned to service.

ECCS System Outage: Division I Core Spray Out of Service from 0425 12/13/88 to 0110 12/15/08 Duration: 44.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Planned Outage Outage Summary:

The Division I Core Spray system was removed from service to perform Preventive Maintenance (PM) on Pumps "A" and "C". Both motors were meggered and term boxes inspected. Temperature detectors were checked and calibrated on both pumps as well. The Division I Core Spray system was returned to service following the preventive maintenance.

ECCS System Outage: Division II Core Spray Out of Service from 2050 1/28/88 to 0930 1/29/88 Duration: 12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Forced Outage Outage Summary:

The Division II Core Spray system was removed from service when the pumps were sprayed with condensation and steam. The Division II Core Spray system was returned to service after the pumps were dried and i meggered. I ECCS System Outage: Division II Core Spray Out of Service from ~65E1 10/25/88 to 0230 10/28/68 Duration: 68.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Planned Outage Outage Summary:

The Division II Core Spray system was removed from service to perform Preventive Maintenance (PM) on breakers, relays and motors for Pumps "B" and "D". Upon conpletion of the FM tasks, the Division II Core Spray system was returned t'o service.

l

I

' . Enclosure-to NRC-89-0036 Page 20 ECCS System Outage: High Pressure Coolant Injection Out of Service from 1235 1/26/88 to 0051 1/27/88 Duration: 12.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Forced Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service when it was discovered that the thermal overloads for valve E41-F012 were not tested as required. The thermal overloads were tested per applicable surveillance requirements and the High Pressure Coolant Injection system was returned to service.

ECCS System Outage: High Pressure Coolant Injection Out of Service from 0600 6/7/88 to 2000 6/10/88 Duration: 86.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform various Preventive Maintenance (PM) tasks. Following completion of the PM tasks and required surveillance tests, the High Pressure Coolant Injection system was returned to service.

ECCS System Outage: _High Pressure Ccolant Injection-Out of Service from 0500 11/20/88 to 0445 11/25/88 Duration: 119.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Planned Outage Outage Summary:

The High Pressure Coolant Injection system was removed from service to perform Preventive Maintenance (PM) on process instrumentation. Upon completion of the various PM tasks, the High Pressure Coolant  !

Injection system was returned to service.  !

, Enclosure to N'RC-89-0036 Page 21 ECCS System Outage: High Pressure Coolant Injection Out of Service from 1558 12/28/88 to 2230 12/29/88 Duration: 30.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Forced Outage Outage Summary:

I The High Pressure Coolant Injection system was removed from service by isolating valve E41-F600 to perform a surveillance test following Instrumentation and Controls work on the E41-N660B Trip Unit. The work request was completed and all required surveillance were run.

The High Pressure Coolant Injections system was then returned to  ;

" Standby" mode of operation. i ECCS System Outage: Automatic Depressurization System Out of Service from 0725 5/26/88 to 0654 5/30/88 Duration: 95.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Forced Outage Outage Summary:

The Automatic Depressurization system was removed from service when alarm 1D36 - ADS Channel B ECCS Pump Permissive was received when no ECCS pumps were running. A work request was initiated to troubleshoot  ;

and correct the problem. The Automatic Depressurization system was I then returned to service.

2 l

l

\

l l

i l .

, e ,B. Rilph Sylvl2

- Senior Vice President Detrol,t 6400 Nortti Oiue Hignaay l Neeport, Michigan 481FA 3 (313) L8s41$0 February 21, 198 NEC-89-0036 i

U. S. Ibclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 l l

Reference:

Fermi 2 NTC Docket No. 50-341 NIC License Nc. NPF-43

Subject:

1988 Annual Oneratina Report for Fermi 2 In accordance with Fermi 2 Technical Specification 6.9.1.4 aril NIC Regulatory Guide 1.16, the Detroit Edison Conpany is submitting the  ;

Annual Operating Report for the Fermi 2 Nuclear Power Plant for the j period of January 1,1988 through December 31, 1988.

The 1988 Fermi 2 Annual Operating Report also satisfies the reporting requirements of 10CFR20.407, (Personnel Monitoring Report), Technical Specification 6.9.1.5.a (Annual Exposure Report by Function), l Technical Specification 6.9.1.5.b (Safety / Relief Valve Challenges),

Technical Specification 6.9.1.5.c (Emergency Core Cooling System Outagen), ar.3 Technical Specification 6.9.1.5.d (Specific Activity Analysis of de Primary Coolant) . In addition, the 1988 Annual Operating Report includes a section on cervice life of the nain steam bypass line. This satisfies the commitment stated in Detroit Edison letter VP-86-0154 to the Nuclear Regulatory Commission dated  ;

tbvenber 7,1986.

1 i

If you have any questions or comments regarding this report, please i contact Mr. Arnold Jaufmann at (313) 586-4213. {

Sincerely, l Enclosute r

f l

l cc: Mr. A. B. Davis l Mr. R. C. Knop fir. W. G. Rogers Mr. J. F. Stang ff

' 8 l

l

-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - )