ML20245A332

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Monthly Operating Rept for Mar 1989 for Hope Creek Unit 1
ML20245A332
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/31/1989
From: Jensen H
Public Service Enterprise Group
To:
Shared Package
ML20245A335 List:
References
NUDOCS 8904250152
Download: ML20245A332 (20)
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t INDEX

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j' SECTI.QR OF PAGES l l 1

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Average Daily Unit Power Leve1......................... 1 1 i

Operating Data Report.................................. 2 1 l

Refueling Information.................................. 1 )

t Monthly Operating Summary.............................. 1 Summary of Changes, Tests, and Experiments............. 13 1 1

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0904250152 890331 I N PDR ADOCK 05000354 >

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4 AVERAGE DAILY UNIT. POWER LEVEL DOCKET NO. __50-354 UNIT _jiqpe Cte.eg-DATE _4U 4/49 COMPLETED.SY H. Jensen TELEPHONE ._L6,Q9) 339-52,h.1 iONTH 11e!n.ch_.1939_

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 (MWe-Net)- (MWe-Net) l 1 Q_ 17 1Q51 2 Q 18 851 3 0 19 1pb8 4 Q_ 20 lgQDO 5 _ Q 21 1Q49 6 Q 22 1Q23 7 289 23 1934 8 877 __ 24 1Q.33 9 1911 25 1Q.49 30 1Q2& 26 1Q4.0 11 1_Q96 27 1.Q34 12 1RS1 28 102.2-13 1Q35 29 101Q 14 1Q29 30 1_01 2 15 1Q48 31 1Q15 ,

16 1Q43

, OPJBATJMG_ DATA RE.P_Q_31 DOCKET NO.86-354 UNIT Hopp Creek DATE .,,_4_/14]89 1

i COMPLETED BY __E _Je_asen TELEPHONE _L6.09.) 339-5261 OPERATING STATUS

1. REPORTING PERIOD tierch.J289 GROSS HOURS IN REPORTING PERIOD 744_
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) __3293 MAX. DEPEND. CAPACITY (MWe-Net) 10.31 DESIGN ELECTRICAL RATING (MWe-Net) 1067
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) Norle 4 REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE S. NO. OF HOURS REACTOR WAS CRITICAL 604x2 _b757.9 _1h 705.5

6. REACTOR RESERVE SHUTDOWN HOURS 0.O O_s O O_, O
7. HOURS GENERATOR ON LINE ,_.599.O L 752,6 __1 h 3 8 4_ ,_7 l
8. UNIT RESERJE SHUTDOWN HOURS Opm O ,_O 0 ,_0_
9. GROSS THERMAL ENERGY GENERATED (MWH) 1.m21ft,834 5t676 142p_.,, 5,LAS_Qd@4_,_
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) - 6 2 4 , 4 6 0___ _ L 815,729 11t 102,_123._,
11. NET ELECTRICAL ENERGY GENERATED (MWH) 596,_231 __L212_,252__ 16 342,352_,,
12. REACTOR SERVICE FACTOR 8 1., 2 81,, 4_ 83_ah_
13. REACTOR AVAILABILITY FACTOR 8.12 2 81,f_ ,. 83m6
14. UNIT SERVICE FACTOR 8px5 8 L_1..__. 82.0
15. UNIT AVAILABILITY FACTOR 80.5 8bJ 82.0 2
16. UNIT CAPACITY FACTOR (Usino MDC) 77 u7 80.5__ 79.3
17. UNIT CAPACITY FACTOR (Using Design MWe) 75.tj 77s8 76.6
18. UNIT FORCED OUTAGE RATE 1.,,_O O.3 6, 7
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):

Refueling 9/16/89. 50 days

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

N/A

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.I OPERATING DATA' REPORT [

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. _59-354 UNIT ._tippe Creek Urtil_1._

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j DATE 4.114/f9 l

COMPLETED BY }is_JS_D.sen REPORT MONTH tiar_ch 19._q9 TELEPHONE ,_1609).339-5261

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i METHOD OF .

I SHUTTING'  !

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TYPE REACTOR OR j F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) POWER (2)- . COMMENTS l t l 2 3/01 S 139.O' B 4' Continuation of i l Scheduled Midcycle l Outage l 3 3/06 F 6.0 A 9 Generator Taken ,

j Off-line Due to l 1 Loading' Problems I

l N 4 3/18 F 0 5 5 Power Reduction 1 for "C" Secondary Condensate Pump '

l Maintenance l l l

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SUMMARY

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HOPE CREEK GENERATING STATION MONTHLY OPERATING'

SUMMARY

MARCH 1989 q l

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Hope Creek entered the. month of March shutdown with a planned maintenance and surveillance outage in progress. The outage was completed on March 6 and the reactor achieved criticality on the i i same day. On March 7 the plant reached 100% power. Power was I reduced on March 18 to perform maintenance on C secondary condensate pump. Later the same day, the plant returned to 100%

power. On March 31 the plant completed its 25th day of continuous power operation.

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SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS i l

FOR THE HOPE CREEK GENERATING STATION  ;

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'1 MARCH 1989

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The fo,.lo' wing Design Change Packages (DCPs) have been evaluated- to determine:

1) if the probability of occurrence or the consequences of an acc3 dent or malfunction of equipment importent to safety )

previously evaluated in the safety analysis report may be I increased; or ]

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2) if a possibility for en accident or malfunction of a different ,

type than any evolueted previously in the safety analysis report i may be created; or l

3) if the margin of safety as defined in the basis for any technical  ;

specification is reduced.  !

None of the DCPs created a new safety hazard to the plant nor did they affect the safe shutdown -of the reactor. These DCPs did not change '

the plant effluent releases and did not alter the existing l environmental impact. The Safety Evaluations determined that no l unreviewed safety or environmental qu'.Stions are involved,

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PAf RtAc.CiEtion._of RRaign Change Peckop.t l 4-HMJ-86-0583 This DCP changed the setpoints on low suction 4 l

pressure switches for the Asphalt Recirculation  !

Pumps in the Solid Redweste System. The previous l setpoint caused the pumps to trip on low suction j l

l pressure when being started due to the esphelt l l cooling if the pumps had not been operated. j recently. The new setpoint will allow the pump to start while still protecting the pump in the event of a suction line plug.

4-HCM-86-1259 This DCP added a Flesh Tank on the Condensate Return Line to the solid redweste boiler, as well as associated valves and instrumentation. The addition of the Flash Tank solves the following problems: the Condensate Feed Tank is not large enough to collect all of the condensate from the .

l Solid Redweste Steam Heating System and the I

( condensate fleshes to steem, creating the need for j additional space.

I 4EC-1002/11 The DCP installed the air handling units in the i

Control Rod Drive Maintenance and Repair areas of I the Reactor Building. The' air handling units will l cool the rooms and have been installed in support I of the new Control Rod Drive Rebuild / Maintenance J l

Facility.

4EC-1002/14 This DCP instelled a platform to allow easy access to the Disassembly and Cleaning Machine Tenk. The platform has been installed in support of the new Control Rod Drive Rebuild / Maintenance Facility.

4EC-1024/05 This DCP instelled platforms and ledders to l provide access to the Main Steem Isolation Velves.

The platforms and ledders will facilitate maintenance and ensure compliance with OSHA q regulations.

4EC-1030/11 This DCP installed steel beams, lifting lugs, and j stiffener plates to several rooms in the Remeter i Building. This modification will allow for the j removal of floor plugs, the "C" Residual. Heat Removal Pump, and en equipment access panel. The l DCP complies with NUREG-0612, Control of Heavy Loads of Nuclear Power Plants, i 4HC-1055/04 This DCP installed the Control Rod Drive Remote Handling Machine, associated equipment, and audio-visual communication eauipment. The Remote ,

Handling Machine will reduce exposure, i contamination, and man-hours associated with Control Rod Drive change-out. j l

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QCf RM9C ption i of Cle_s190_Ctenge Pa9Appe_.

4EC-1055/05 This DCP installed rails, a leveling tray, and Support structure components to prepare for the installation of the Control Rod Drive Remote Handling Machine.

4HC-DO59/01 This DCP installed a bypass line and isolation valves for air dryers in the Instrument Air System. This allows for the installation of new air dryers at a later date.

4HC-0116/02 This DCP replaced Tober transmitters in the Safety Auxiliaries Cooling System Accumulators with Rosemount transmitters. The Tober transmitters were improperly sized and did not allow proper calibration. Therefore, they were a source of constant nuisence alarms in the Control Room.

4HC-0126/02 This DCP programmed the GETARS computer to accept additional inputs to monitor the Redundant Reactivity Control System / Standby Liquid Control System interface to a Bailey panel. This provides for continuous monitoring of the interposing relays between the Redundant Reactivity Control System and the Standby Liquid Control System.

4HC-0126/03 This DCP programmed the GETARS computer to accept additional inputs to monitor the Redundant Reactivity Control System / Standby Liquid Control System interface to a Bailey panel. This provides for continuous monitoring of the interposing relays between the Redundant Reactivity Control System and the Standby Liquid Control System.

4HC-0127 This DCP re -routed the drain line from the Turbine Building Se:mple Penel. The drain line will be merged with the line from the Reactor Feed Pump Seal Laakeae to the Condensate Drain Tank instead of going to the Dirty Radweste Drain. This will reduce the volume of effluent that the radweste system has to process.

4HC-0129 This DCP provided electrical power and compressed air to Radiation Protection's sorter / Shredder /

i Monitor. The Sorter / Shredder / Monitor is used for the disposal and volume reduction of Dry Nonradioactive Weste.

4HC-0147 This DCP restored the capability of the Main Turbine Electro-Hydraulic Control System to operate the Main Turbine in the Partiel Arc Steam Admission Mode. This DCP will allow the Turbine Generator to produce en additional 5 megawatts electric at rated conditions. This increase is power in power is attributed to reduced throttling losses.

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1 QCP e De sgrJp_tjy ,91._.ReAIRD_ChaDgp Pa.pkage 4HC-0151/04 This DCP replaced a Service Water elbow on' the  !

Reactor Auxiliaries Cooling System Heat Exchanger "B" Outlet line. It also added flanges and j modified a hanger. The replaced elbow had j previously been patched.

4HC-018e This DCP installed a full flow bypass line around the Reactor Water Cleanup Regenerative Heat Exchangers. This will allow the full-flow of - the j reactor coolant exiting the Reactor Water Clean-up Filter Demineralizers to bypass -the Heat Exchangers. The DCP increases the rate at which the reactor decay heat can be removed by the Non-Regenerative Heat Exchangers during refueling or cold shutdown.

4HC-0241 This DCP revised the Reactor Water Clean-up Filter Demineralized logic to add a loss-of-eir interlock and an inlet-valve bypass arrangement to allow slow vessel pressurization following precoating.

It also eliminates potential damage to the hold pump and filter element by an early detection system.

4HC-0247 This DCP added a relief valve on the . Chemical Cleaning Outlet line off of the Reactor Water Clean-up Filter Demineralizers. The relief valve discharges to the Clean-up Backwash Receiving Tank, preventing the overpressurization of the line and avoiding leakage from the Reactor Water Clean-up System to the Chemical Weste Tank.

4HM-0012 This DCP added a reset switch to the Self Test Controller Central Processing Unit in the Redundant Reactivity Control System. The reset switch will allow the operator to ' escape from a j CPU' lockup without removing power to the locked-up j penel. This will improve the performance of the j installed electronics and promote a longer time j between failures. j l

4HM-DO49 This DCP installed time delay relays in the Liquid )

Redweste System. The time delay relays will o prevent overflowing in the Precoat Tank and will reduce Solid Redweste generation' caused by the I loss of precoat while placing a partially depleted precoat back in service. This will also enhance ,

system performance by reducing downtime. l l

4HM-DO54 This DCP re-sized an orifice in the Liquid Radweste system. The incorrectly sized orifice required the valve to be throttled to avoid pump run-out during recycle operations to the Condensate Storage Tank.

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4HM-0138' This DCP soldered resistors -on High-Powery Output Isolator Cards end soldered shields on High ' Power.

Input Isolator: Cards. . A '.1 affected cards'were? in-the Redundant; Reactivity. Control _ System. This will improve ~the= electronic components . resistance l to vibration' and therefore ' increase: ;the reliability of the circuit ' boards. 'and- -the Redundant Reactivity Contro11 System. j 4HM-0153 This DCP installed ' floor-grates. over open? valve pits in' Solid Radweste Rooms. .The: floor grates are required forc personnel protection in these areas which are zoned:ss high radiation areas.

4HM-0207 This DCP. installed pig-tail leaders onto the Solid Redweste Television-Camera: coaxial cables. .This will reduce the stress- caused by the movement: of the cables at the cameras.and control units.

4HM-0211 This DCP upgraded the Redundent Reactivity Control System hardware and firmware. 'These upgrades will.

improve reliability- and prevent inadvertent actuations.

4HM-0288 This DCP raised the setpoint for low Instrument' Air Header Pressure annunciation in the Control Room. This will . provide the operator with adequate response time in the event of- gradual loss of Instrument Air.

4HM-0358 This DCP replaced the spool piece in the -Resin Separation and Cation Regeneration Vessel 1with' a larger spool piece. The. original spool piece was too short.

4HM-0377 This DCP revised the setpoints for the Cleanup Backwash Receiving Tank Level. Switches. The change will correct for the effeet of the spray nozzle operation.

4HM-0385 -This DCP installed manual valves that: isolate the

, solenoid valves used while performing tests. The valves will enable maintenance. personnel to- work.

on the solenoids or on the pressure switches without endangering the plant or their.-own safety.

4HM-0403 This DCP installed portable. oil storage tanks in the Turbine Building. This- enr.bles lubrication oil to be stored in the Turbine Building. The DCP also installed additional fire detectors-to ensure early warning signals. l 1

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I QC.E s QeAsrintlAD J2.f_.Qgsi2D Change _Eng_htpSt 4HM-0411' This DCP removed the cepability to sample Particulate and Iodine in Containment Atmosphere from the Post-Accident Sampling System. This.

capability was not required; its removal reduces l both corrective maintenance- and surveillance  !

testing.

4HM-0425/01 This DCP installed the pipe connections. for a 1 Turbo-Too Oil conditioner skid. The skid will. be ]

This DCP removed the capability to sample j Particulate and Iodine in' Containment Atmosphere ]

from the Post-Accident Sampling System. This capability was not required; its removel' reduces l both corrective maintenance and surveillance l testing. )

I 4HM-0427 This DCP moved the Chlorine Analyzer Suction i

Piping for the Blowdown Line Analyzer; from the l

Main Process Line to the Stilling Well. This' I

change will allow the sample pump to take a l l representative sample of the liquid discharging to' i I the river by eliminating the current eductor effect.

4HM-0439 This DCP increased the Motor-Generator Exciter Cover Opening to permit easier access to the uppermost brush. This will facilitate maintenance of the brushes.

4HM-0466 This DCP replaced electromechanical breaker fail relays in the Main Generator with solid state relays and reduced the relay settings. This will allow Salem and Hope Creek Stations to operate at maximum megawatt output simultaneously and maintain system grid stability during nor:'a l ' and transient operations.

4HM-0493 This DCP added a time delay relay between the High-Water Level Trip Unit and the trip relay for each of the water level channels. This will prevent-the ringinv phenomenon exhibited by the Reactor Water Level Transmitters from causing a trip of l the Reactor Feed Pump Turbinas subsequent to a l Main Turbine trip. I 4HM-0513 This DCP removed the lower body drain valves from j the Recirculation Pump Isolation Maintenance Valves. The removal of the lower body drain i valves removes a moment arm that is a source of stress on the valve body to drain valve interface 1 I

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PNP _ _ Qeactiplion of D e s i.g D _ C h a n_ g e P a g h a g e.

4HM-0532' This DCP replaced the pressure gauges in the

. Asphalt Recirculation Pumps. This change' was required because the viscosity of the asphalt caused the suction gauges to operate under a vacuum.

4HM-0571 This DCP installed a removable. personnel access barrier to prevent. unauthorized ' personnel from entering the turntable' rooms 1 and being unnecessarily subjected to high radiation ~ zones.

4HM-0584 This DCP installed a new valve body on a valve in the Feedwater System. The test connection on the new valve body is located on the bottom of the valve instead of the top as the previous valve-body.

4HM-0585 This DCP removed the close limit contacts function from valve operators in the Residual Heat Removal System. This change allows the Control Room Operators to throttle the valve operators over the entire range of operation in the close direction.

4HM-0587 This DCP installed supports to strengthen the impingement plate at the exhaust of the Steam Jet Air Ejectors in the After-Condensers. The previous design did not exhibit sufficient i strength.

4HM-0588 This DCP added stiffener plates to a hanger in the Feedwater System to strengthen the support in the event of water hammer or other unanticipated I loads.

4HM-0589 This DCP removed interference between the pipe hanger support steel at- a combined intermediate a valve and an Electro - Hydraulic Control pipe.

Eliminating the piping interference will reduce Electro-Hydraulic Control pipe stress and improve the reliability of the Electro-Hydraulic Control System.

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4HM-0601 This DCP installed resistors across the oil level switches for the Reactor Recirculation Motor Bearing Reservoirs so the Control . Room 'can j distinguish between a high or low level alarm. j l

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1 The following Temporary Modification Requests (TMR'S) have been evaluated to determine:

1) if the probability of occurre'/:e or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safet> analysis report may be i increased; or
2) if a possibility for en accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or l j
3) if the margin of safety as defined in the basis for any technical Specification is reduced.

1 The THR'S did not create a new safety hazard to the p1, it 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 j impact. Tia Safety Evaluation determined that no unreviewed safety or j environmental questions are involved.

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l SAfsty_gyglystjpn p_tscriplipo_r.L of Temporary Modification Regues1.

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l 89-0006 This TMR provides a 480 volt Non-1E temporary '

l power source to a 480 volt AC Non-1E Motor Control J l Center during the "C" 4.16 Kv Class 1E bus outage.

l This modification is to be used only when' "C" I channel is inoperable and the plant is in operational conditions 4.5, and *. i l i l 89-0007 This TMR provided a 480 volt Non-1E temporary j power source to a 125 volt DC battery charger l l

l during the "C" 4.16 kv Class 1E bus outage. This l modification is to be used only when "C" Channel. ]

l is inoperable and the plant is in operational )

conditions 4,5 and

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l 89-0008 This TMR provided a 480 volt Non-1E temporary

( power source to a 125 volt DC battery charger during the "C" 4.16 kv Class 1E bus outage. This modification is to be used only when "C" Channel ,

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89-0009 This TMR provided a 480 volt Non-1E temporary power source to f

a 120 volt AC Class 1E Security 1 Inverter during the "C" 4.16 kv Class 1E bus I outage. This modification is to be used only when "C" Channel is inoperable and the plant is in operational conditions 4, 5, and * .

89-0014 This TMR removed the overload heaters from the circuit breaker- for a Residual Heat Removal Outboard Shutdown Cooling Isolation Valve.

Removing the overload heaters complies with the 10CFR50.59 Appendix R requirements.

89-0016 This TMR lifted leads in control panels to remove the power source from the Residual Heat Removal i Testable Check Bypass Valves. Lifting the leads complies with the 10CFR50.59 Appendix R Requirements.

89-0017 This TMR Jumpered two level switches to satisfy the level logic in the Solid Redweste System. A level switch was failed and could not be replaced due to en obstruction. If redweste levels start to rise, it will be detected as the affected level switch is at the end of the extruder. Levels will rise in other domes first.

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$_Rfsty;_%yalga119.0 QSApriRkipn of T e mp_orpry_fiogi t i c a t i o_n R e qu e s t  ;

s (TMR1 89-0018 This TMR eliminated the High Level Steam Dome Interlock on the extruder / evaporator to allow the i processing of redweste. This modification is )

required because the High Level Probe Trips have been unreliable and have caused spurious extruder l trips.  !

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. l The foll6 wing Deficiency Requests (DR'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 en accident or malfunction of a different type than any evaluated previously in the safety analysis report f 1

may be created; or

3) if the margin of safety as defined in the basis for any technical specification is reduced. 1 The DR's did not creat? a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. The DR's did not change the plant effluent releases and aid not alter the existing environmental i impact. The Safety Evaluations determined that no unreviewed refety or environmental cuestions are involved.

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S A f e.t Y J v a 1.y a t i g.O Qe.Acripflon of_Qefigiency_Etegnt: (DR1 89-0020 A steam leak was discovered on the Seal Flange Inlet to a relief valve on the Steam Seal Evaporator. This Safety Evaluation authorized placing a clamp over the flanges at the inlet to the relief valve.

89-0021 A steam leak:was discovered on the Seal Flange-Inlet to a relief valve on the "B" Moisture Separator. This Safety Evaluation authorized placing a clamp over the flanges at the inlet to the relief valve.

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