ML20005G485

Monthly Operating Rept for Dec 1989 for Hope Creek Generating Station,Unit 1.W/900115 Ltr

ML20005G485
Person / Time
Site:	Hope Creek
Issue date:	12/31/1989
From:	Brennan C, Hagan J, Loeper S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001190222
Download: ML20005G485 (19)

Text

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating Station s

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U. 8.. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 9

Dear' Sir:

MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOC.KET NO. 50-354 L In compliance with Section'6.9, Reporting Requiren(.nts for the L'

E Hope Cresk Technical Specificarious, the" operating statiatico for .

Decembez-l are being forwarded- te you with tha sumnary of changes.

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h-testa,'and experiment,* for December 1989 pursuant to the t

, (requirements;of 10CFR50.59(b). j

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Sincerely-yours,

. J agan General Manager -

Hope Creek Operations

,  :- g RAR:sc Attachment C Distribution 9001190222 891231 PDR R ADOCK 05000354 ,

PDC '

The Energy People TER w!lke

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INDEX NUMBER SECTION OF PAGES

" " Average Daily Unit Power Leve1......................... 1

, Operating Data Report.................................. 3

< Refueling Information.................................. 1 Monthly Operating Summary.............................. 1 Summary of Changes, Tests, and Experiments............ 11 d;,

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-354 UNIT _ Hope Creek DATE 1/15/90 COMPLETED BY ___S. Loeper TELEPHONE (609) 339-5257 F

t _ MONTH _ December 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1077 17 1075 2- 1063 18 1057 3 1069 19 1069 4 1066 20 3 Q2,1 ,,,,

5 _ , , , , _ 1071 21 _ , , , _ _ , _ , , 3 O_7_q, _ _ , _ , , , ,

6 ,,,, .,__1057 22 _J.01%

7 1084 23 ____ , ,,,,_1,q2 6 _ ,. _,

8- 1158 24 _;1ER, ,_,,_,_ -

9 .__ 1071 25 1069__

'10 1071 26 1047 11 1062 27 1088 12 1057 28 1065 i

L 13 1081 29 1064 14- 1072 30 883 15 1067 31 0 16 1069

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e g OPERATING DATA REPORT DOCKET NO. 50-354

, UNIT _ Hope Creek j DATE _1/15/90_

COMPLETED BY- S. Loeper -

1 TELEPHONE _(609) 339-52p7 F CPERATING STATUS  :

1. REPORTING PERIOD December __1989. GROSS HOURS IN REPORTING PERIOD 744  ;

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) _3293 p MAX. DEPEND. CAPACITY (MWe-Net) _1031 DESIGN ELECTRICAL RATING (MWe-Net) 1057

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) None 4 REASONS FOR RESTRICTION (IF ANY)

THIS YR TO  ;

MONTH DATE CUMULATIVE ,

/5. NO. OF ROUPS REACTOR WAS CRITICAL 715.7_ _6_813.9 __21761 5_,,_

-4. REACTOF.;RESER'!F SHUTLOWN NOURS 09 2 __. 0 . 3 __ 0Q .

'. 7 .= HOURS U.!NERATOR CN LINE ,- 715.7 _ ,,_, _i,11,9J_ 213 51,L__

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'8.. UNIT RESERVE SiiUTDOWN HOURS _ 0,0 _J . 0 0.1_

19. GROSS THERMAL ENERGY GENERATZD

' (Mrdi _;,3?2,811 2 2_0_,J_5_,2{7_2 _63,, 9 5 6 , 3 8L 7 101, 1

GROSS ELECTRICAL ENERGY GENERhTED (MWH) 796,120 _6,929,819- ,_2_.2dji,fJG,)_

'11. NET ELECTRICAL ENERGY GENERATED (MWH) 763,037 __6,606,4_49_ _21,156,549__

12. REACTOR SERVICE FACTOR 96.2 77.8 81.8_,

13. - REACTOR AVAILABILITY FACTOR 96.2 77.8 81.8

14. UNIT SERVICE FACTOR 96.2 76.7 80.3 l- 15. . UNIT AVAILABILITY FACTOR 96.2 76.7 80.3

16. UNIT CAPACITY FACTOR (Using MDC) 99.5 73.1 77.2 17 . - UNIT' CAPACITY FACTOR (Using Design MWe) 96.1 70.7 74.6

18. UNIT FORCED OUTAGE RATE 3.8 1.4 5.6

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):

None Scheduled

20. _IF SHUT DOWN AT END OF REPORT PERIOD, ZSTIMATED DATE OF START-UP: 1/3/90

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L'- OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS i

DOCKET NO. _50-354 i UNIT _ Hope Creek Unit 1__  ;

DATE 12/15/89  ;

COMPLETED BY _S.LoeDer .

REPORT MONTH November 1989 TELEPHONE (609) 339-5257 METHOD OF 4 SHUTTING DOWN THE TYPE < REACTOR OR -

F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

N3. DATE S SCHEDULED (HOURS) (1) POWER (2) COMMENTS 11 09/16 S 129.7 C 4 CONTINUATION OF REFUELING OUTAGE

. 12 11/19 S 8.8 B 1 7URBINE TESTING

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SUMMARY

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.. .a OPERATING DATA REFORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-354 .

i r- UNIT __ Hope Creek Unit 1_

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t DATE _1/15/90 COMPLETED BY _S.Loeper REPORT MONTH December.__1989_ TELEPHONE (609) 339-5257 NETHOD OF  ;

SHUTTING he DOWN THE  :

'; , TYPE REACTOR OR F FORCED OURATION P.EASON R5DUCINO CORRECTIV% ACTION / '

J r NO '. DATE S SCHFDULEDg (HOURS) (1. ) POWSR f2) COMMENTS ;

l's . 12/30

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F 28.3 A' 3 FkILUREOFLIHkT

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SWITCH DURING

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TESTING OF THE MAIN TURBINE i

.n TARUST BEARING WEAR DETECTOR -

(LEP 89 -026) l t

SUMMARY

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i REFUELING INFORMATION  :

COMPLETED BY: _Chris_Brennan DOCKET NO: 50-354 UNIT NAME: Hope Creek Unil_1.

DATE: _J/15/90 TELEPHONE: 1193 EXTENSION: N/A I L

Month January 1990

1. Refueling information has changed from last month:

YES NO X i

2. $cheduled date for next refuelingt 01/19411___

3. Scheduled date for-restart following refueling _A2/.25/91_ <

4. A) Wil). Technical Specification changes or other licenso 1MJ amsndments be required?

YES , NO X _

, B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

i YES .__ NO X If nc, when is it scheduled? 02/01/91

5.  ; Scheduled date(s) for submitting proposed licensing action: N/A

6. Important licensing considerations associated with refueling:

-Amendment 34 to the Hope Creek Tech Specs allows the cycle

-specific qperatina limits to be incorporated into the CORE

-OPERATING LIMITS _EEPORT; a submittal is therefore not ,

tequired.

7. Number of Fuel Assemblies:

A)-Incore ___764 _ _ _

B) In Spent Fuel Storage (prior to refueling) _496 C) In Spent Fuel Storage (after refueling) 744

8. Present licensed spent fuel storage capacity: 1290 Future spent fuel storage capacity: 4006 .

l 9. Date of last refueling that can be I discharged to spent fuel pool assuming the present licensed capacity: 03-05-91 l

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HOPE CREEK GENERATING STATION t'

4 MONTHLY OPERATING SUMMERY  !

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.; ; DECEMBER 1989-  ;

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Hope Creek entered the month of December. operating at=1004 power.

l' On December 29, during a surveillance test, the plant automatically

' shutdown.due to a failure of.a limit switch in the-Main Turbine -,

Thrust Bearing-Wear Detector. This failure caused a. turbine trip l

. which in~ turn caused a reactor' scram. The plant had completed its  :

L dist day of continuous power operation. On December 31st, the l Plant-remained in shutdown, repairing s a leak on a recirculation _

instrument line.  ;

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? .i SUNNARY OF CHANGES, TESTS, AND EXPERINENTS FOR THE HOPE CREEK GENERATING STATION DECEMBER 1989 l

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i The following Design Change Packages (DCP's) have been evaluated to determine:

1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or

2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or

3) if the margin of safety as defined in the basis for any technical specification is reduced.

The DCP's did not create a new safety hazard to the plant nor did the,y affect the safe shutdown of the reactor. The DCP's did not cuange the piant effluent releases and did not alter the existing i environmental impact. The safety Evaluations determined that no unreviewed safety or environmental questions are involved.

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DCP Description _of_Desion_ Chance Packace 4EC-1002/07 This DCP provided permanent walls in the Reactor Building to establish a clean area to perform Control Rod Drive maintenance work.

Air flow is being forced from areas of low containment to areas of higher containment.

This DCP is part of a larger project establishing an improved Control Rod Drive Rebuild'and Maintenance Facility.

4HC-0029 This DCP replaced the Off-Gas Hydrogen Analyzers and the associated pumps, valves, and instrumentation with new analyzers and a new system to more accurately analyze the hydrogen ,

content of the off-gac sample from the recombiner units. This DCP also added new  ;

oxygen analyzers. i t

4HC-0035 This DCP added Drywell/ Suppression Chamber Supplementary Oxygen Analyzers to the Leak Detection System.and the Containment G Atmosphere Monitoring Hydrogen Oxygen Analyzing '

System Panel. The additional analyzers provide  ;

an alternate acceptable method to monitor ,

oxygen concentrations.

4HC-0125/02 This DCP installed the electrical, instrumentation, and control power portions of -

a larger modification to add a third Reactor Auxiliaries Cooling System Pump. The additional pump will increase the reliability ,

and availability of the Reactor Auxiliaries Cooling System.

4HC-0181 This DCP installed a new communications console in the Control Room and in the simulator. This modification, along with other DCP's, will provide Artificial Island with an integrated radio communication package. i 4HC-0320/02 This DCP replaced seal connectors and cable assemblies installed on limit switches and solenoid valves of the Main Steam Isolation Valves with quick-disconnect assemblies. The original installation required rebuilding limit switches every refuel outage and rebuilding .

solenoid valves every other refuel outage for Environmental Qualification considerations.

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. ' pgE Description of Desian Chance Package 4HC-0324/01 This DCP provided the support activities for ',

4HC-0324/02 and provided for the restoration and disposition of all damaged commodities.

l 4HC-0324/02 This DCP provided for the lifting of a portion of the Turbine Building floor and the  !

replacement of slide bearing assemblies. This ,

DCP was required due to the degradation of the -

urethane material portion of the bearing  ;

assemblies.

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-4HC-0328 This DCP modified piping and nozzles in the Cooling Tower Hot h'ater Distribution Piping -

-System. These modifications will improve the Cooling Tower's thermal performance, and are based on vendor recommendations.

4HC-0333/01 This DCP rowired a multiplexer to return it to l its original configuration. A previous i modification provided this multiplexar with an  ;

uninterruptable power supply. That modification was roquired during the Loss of Offsite Power Test to record Reactor Protection System GETARS points. This DCT disconnected s the uninterruptable power supply and reconnected the multiplexer to its original Reactor Protection System power supply.

4HM-0258 This DCP replaced some of the valve packing in selected valves in the Condensate, Feedwater, +

and Reactor Core Isolation Cooling Systems.

Split carbon sleeves were installed in lieu of ,

the. packing to reduce the probability of valve leakage.

4HM-0307 This DCP installed a run timer for every sump pump that inputs into the Radwaste System.

This will allow for the identification of the most used sumps, facilitating action to reduce the amount of liquid entering the Radwaste System.

4HM-0311 This DCP revised Instrument Calibration Data Cards for Fire Protection Level Switches.

These modifications account for the slope in the Fire Tank mounting slabs and the relative elevation of the level switches that are mounted in the Fire Protection Pump House.

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s RCE pescription__of Desigp Chance __Packace  !

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H 4HM-0384 This DCP installed an isolation valve in both the "A" and "B" Turbine First Stage Pressure

$ Sensing Lines. These isolation valves will ,

remain open during normal plant operatione and will be used to allow Inservice Testing of i Excess Flow Check Valves during outages.

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'4HM-0406 This DCP replaces relays in the Jet Pump Instrumentation System with another model  ;

relay. The new relays are more suitable for a low voltage, low current contact application.

4HH-0408, This DCP provided a floor penetration near the North.Radwaste Hatch. The penetration is  ;

required to run an oxygen line between '

elevations.

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4HM-0524/04 This DCP added a Chlorine Analyzer, Controller,

-pH Analyzer, and Data Acquisition Module to allow for improved monitoring and control of  :

the Dechlorination System.

4HM-0524/05 This DCP replaced the Circulating Water Chlorination Pumps with smaller pumps and improves control of the system by allowing operation in the upper end of the pump stroke.

'm . 4HM-0528 This DCP replaced the Brush Holder Assembly on the Alterrex Exciter with an improved assembly.

The new assembly facilitates on-line i

maintenance and reduces the potential for a i scram during maintenance due to loss of L excitation. .

1 4HM-0531 This DCP replaced torque tube style level transmitters in the Extraction Steam System with differential pressure cells to monitor level in the Feedwater Heaters. This DCP will t eliminate hi/hi level trips caused by flashing 1 during a turbine trip.

4HM-0533 This DCP added a test connection and removed the valve internals from a Reactor Core Isolation Cooling Check Valve to facilitate the Local Leak Rate Test for a Reactor Core Isolation Cooling System Minimum Flow Bypass Valve.

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,DCP Description _of__Desian_ Chance Packace  ;

I e 4HM-0537 This DCP replaced the carbon steel piping in the "A" Reactor Feed Pump Turbine Low Pressure Steam Supply Drain Line with stainless steel piping. The stainless steel piping is more i l' resistant to erosion and corrosion than carbon steel piping.

4HM-0538 This DCP removed the temporary encapsulations on the "C" Reactor Feed Pump Turbine Low Pressure Steam Drain Line and replaced the i b-

^l damaged piping with stainless steel piping. )

The stainless steel piping is more resistant to I erosion and corrosion.

4HM-0545 Tnis DCP removed the temporary encapsulations on the "B" Reactor Feed Punp Turbine Low Pressure Steam Drain Line and replaced the .

damaged piping with stainless steel piping.

The stainless steel piping is more resistant to erosion and corrosion. ,

p 4HM-0553 This DCP relocated the connection point for the Narrow Range Level Instrumentation on Feedwater Heater Shells. The new connection will eliminate the high activity that was being detected by the instrumentation.

,4HM-0606- This DCP rotated the valve bodies for valves in

. the containment Atmosphere Control System.

Rotating them will permit proper Local Leak Rate Testing of the associated containment .

penetrations.

i 4HH-0610 This DCP replaced a relief valve in a Reactor Water Cleanup Non-Regenerative Heat Exchanger with a different model relief valve. No direct replacements for the original valve were available.

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L 4HM-0629 This DCP installed temperature monitoring

! devices on various components in the Drywell To provide data to determine Environmental Qualification life expectancies.

DCP Description _of Desian Chance Package Is t 4HM-0661 This DCP changed the piping material l

! classification for-the Radwaste Demineralizer L Systens to allow the use of polypropylene line i b pipe instead of the original Saran lined pipe.

The original pipe is no longer manufactured because it had a tendency to crack.

$ 4HM-0724 This DCP replaced the closed circuit television

!: cable for the Radwaste 7.5 Ton Crane. The new.

cable has an equal capacity, but more l flexibility. ,

i 4HX-0269 This test DCP installed temporary instrumentation to monitor steady state vibration levels of the Reactor Recirculation ,

System Pump Suction Elbows. The test results l' provided by.this DCP will be used to trend the frequency levels and the associated strains and  :

accelerations in the Reactor Recirculation t System.

t V i 4HX-0675 Thf.s experiment DCP installed ultrasonic flow transducers and thermocouples on the drain linen to determine the efficiency of the Main Turbine Moisture Seperators. A dedicated  ;

monitor will also be installed to compile and process the data.

f5HC-0004 This DCP modified radio equipment in the firehouse and in the security areas of Salem .

and Hope Creek Generating Stations. This DCP is 't I

part of a communications system upgrade that will provide an integrated radio communications t package for Artificial Island, i

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The following Temporary Modification Requests _(TMR's) have been

' evaluated to determine:

-1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety .

previously evaluated in the safety analysis report may be l increased; or 1

2)- oif a possibility for an accident or malfunction of a-i different type than any evaluated previously in the safety

, analysis report may_be created; or 3 )- if the margin of safety as defined in the basis for any technical specification is reduced.

The THR's did not create a new safety hazard to the plant nor did they affect the safe' shutdown of the reactor. The TMR's did not change the' plant' effluent releases and did not alter the existing environmental ~ impact. The Safety Evaluations determined that no

, unreviewed safety or environmental questions are-involved.-.

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j lJ " Safety' Evaluation pescription of1 Temporary Modification-Request ,

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'89-162. This TMR bypassed a failed vibration monitoring probe for;the "B" Reactor Recirculation Pump.-

There are two probes installed on the pump, >

indication-in the Control Room will be provided'by the other probe-until the failed

. one can-be replaced. This.THR eliminates a; i nuisance overhead annunciator.89-176 This THR removed the. overload heaters from c Reactor Water Cleanup Discharge Valves. These valves are high-low pressure interfaces between 1 the: primary coolant and the Reactor Water

'W Cleanup; System discharge to the Main Condenser '

and'the equipment' drain. . This will prevent'the' ,

valves from opening during an Appendix R fire.  !

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L The following Deficiency Report (DR) has been evaluated to determine:

1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or-

2) .if'a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may.be created; or

. 3) if the margin of safety as defined in the basis for any technical specification is reduced.

- The DRfdid not. create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The DR did not change the plant effluent releases and did not alter the existing environmental i'mpact. .The Safety Evaluation determined that no unreviewed' safety or environmental questions are involved.

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SAFETY' EVALUATION DESCRIPTION OF_ DEFICIENCY REPORT-I

.89-165 ,When the "B" Traveling. Screen Spraywash Pump was disassembled forLa routine internal inspection, it was discovered that T the impeller hadJexperienced extensive

. wear. No spare impe11ers were available; therefore. .the worn' impeller-was repaired

. . - and.will be used until a new impeller is available.

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