ML20235X073

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Monthly Operating Rept for Sept 1987
ML20235X073
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/30/1987
From: Jensen H, Labruna S, Ritzman R
Public Service Enterprise Group
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8710190193
Download: ML20235X073 (22)
v • d • e


Text

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AVERAGE DAILY UNIT POWER LEVEL q l

l DOCKET NO.86-354 j Hope Creek GS J UNIT !j DATE 10/08/87 COMPLETED BY H. Jensen #g%A-l TELEPHONE (609) 339-5261 1 H? NTH September 1987

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i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net) d 1 1011 17 949 1 1

2- 933 18 '46 3 1018 19 0 i 4 1004 20 0 l

5 1020 21 0 6 996 __ 22 0 7 771 __ 23 0 8 997 24 0 9 1001 25 0 10 931 . _ _ _ _ 26 0 11 788 27 0 12 836 28 0 13 517 29 0 14 848 30 0 15 987 31 0 l

16 994 l

l 8710190193 B70930 , J-DR ADOCK0500gg}4 , t>

OPERATING DATR REPORT DOCKET NO.86-354 UNIT Hope Creek ,

DATE 10/08/87 )

COMPLETED BY H. Jensen gjp q TELEPHONE (609) 339-5261 q OPERATING STATUS j

1. REPORTING PERIOD Sept 1987 GROSS HOURS IN REPORTING PERIOD 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 i MAX. DEPEND. CAPACITY (MWe-Net) 1067 1 DESIGN ELECTRICAL RATING (MWe-Net) 1067 i
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) None l

l 4. REASONS FOR RESTRICTION (IF ANY)

THIS YR TO MONTH DATE CUMULATIVE l l S. NO. OF HOURS REACTOR WAS CRITICAL 413.5 5961.1 6249.1 1

6. REACTOR RESERVE SHUTDOWN HOURS 0 0 0
7. HOURS GENERATOR ON LINE 413.5 5920.7 6208.7
8. UNIT RESERVE SHUTDOWN HOURS 0 0 0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1,233,223 17,911,633 18,842,041 l 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 410,483 5,957,593 6,255,233
11. NET ELECTRICAL ENERGY GENERATED (MWH) 389,142 5,700,629 5,986,453
12. REACTOR SERVICE FACTOR 57.4 91.0 91.4
13. REACTOR AVAILABILITY FACTOR 57.4 91.0 91.4 l
14. UNIT SERVICE FACTOR 57.4 90.4 90.8
15. UNIT AVAILABILITY FACTOR 57.4 90.4 90.8 l
16. UNIT CAPACITY FACTOR (Using Design MDC) 50.7 81.6 82
17. UNIT CAPACITY FACTOR (Using Design MWe) 50.7 , 81.6 82 l
18. UNIT FORCED OUTAGE RATE O 5.2 5.0
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):

Refueling 1/31/88, 55 days

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

10/10/87 2 Data obtained in August is under management review.

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OPERATING DATA REPORT UNIT SHUTDOWNS AND' POWER REDUCTIONS DOCKET No.86-354 UNIT Hope Creek 4

DATE 10/08/87-COMPLETED BY R. Rif,zman REPORT MONTH Sept. 1987 TELEPHONE (609) 339-3737 METHOD OF.

SHUTTING -

DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /

NO. DATE S SCHEDULED (HOURS) (1) POWER (2)' COMMENTS 14 9/7 F 0 A 5 Turbine Valve Testing 15 9/13 F 0 A 5 Turbine Valve Testing 16 9/18 S 306.5 B 2 Planned )

Surveillance Outage l

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SUMMARY

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HOPE CREEK GENERATING STATION MONTHLY OPERATING-

SUMMARY

SEPTEMBER 1987 The Hope Creek Generating Station started the month at 100% power. .

While the Hope Creek - Keeney line outage continues the unit was able to operate 'at near 100% power until September 7, when power. was temporarily reduced to perform routine Turbine Valve Testing. Power was again temporarily reduced on the 13th for additional routine Turbine Valve Testing. At 5:30 AM on September 18, the reactor was-  !

manually scrammed from approximately 15% power to commence a planned l surveillance outage. The plant had been'on line for 18 days prior to '

the planned manual scram. The outage continued through the end of the month.

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SUMMARY

OF' CHANGES.,, TESTS,-AND. EXPERIMENTS s-

.. . "l i; FOR THE HOPE CP.yEK GENERATING STATION.

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DCP Description of Desian Chance Packace

'7148 This DCP refurbished the Circulating water Pump  !

Structure Trash Screens. This refurbishment repaired existing damage and added grounding wires to prevent further corrosion, which was primarily caused by stray currents. This DCP also added Cathodic Protection.

It did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This 1 DCP did not change'the plant effluent releases and did 1 not alter the existing environmental impact. {

Therefore, no unreviewed safety or environmental questions are involved.

I 4-HCO-86-0519 This DCP replaced-the locknuts in the Station Service l Water Ctrainers with locknuts from a different l manufacturer. The new style locknuts did not create a new safety hazard to the plant nor did they affect the safe shutdovn of the reactor. This DCP did not change the plant effluent releases and did not alter the .

existing environmental impact. Therefore, no I unreviewed safety 'or environmental questions are i involved.

4-HMM-86-0754 This DCP changed the Constant Level Oiler on the Service Water Screenwash Booster Pump' Bearing Housing. i The new oiler. utilizes a butterfly nut arrangement and is a more dependable method to maintain oil level. It did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact.

Therefore, no unreviewed safety or environmental questions are involved. )

1 4-HMO-86-0877 This DCP added a new relay and new contacts to the  ;

control scheme for the Emergency Instrument Air Compressor. This will eliminate unnecessary running of the compressor and is anticipated to prolong the compressor life expectancy. It did not create a new l safety hazard to the plant nor did it affect the safe l shutdown of the reactor. This DCP did not change the plant effluent releases and-.did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

4-EMC-86-0974 This DCP installed a new lightning protection mast on '

the Reactor Building dome. The new mast re-establishes the original degree of lightning protection and did not create a new safety hazard to l

the plant nor did it affect the safe shutdown of the I

reactor. This DCP did not change the plant effluent releases and did not alter the' existing environmental impact. Therefore, no unreviewed safety or '

environmental questions are involved.

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l pCP Description of Desian Chance Packace 4-HME-86-1088 This'DCP incorporated auxiliary contacts and breakers into the Electro-Hydraulic Control and Turbine Supervisory Instrumentation systems circuitry. These

' changes provide a more conservative logic scheme which ) '

provides. Jan improved reaction to equipment malfunction. They did'not create a new safety . hazard to the plant nor'did they affect the safe shutdown of ~J the reactor. .This DCP did not change the plant effluent releases and did not . alter the existing environmental impact.. Therefore, no unreviewed safety or environmental questions are involved.

4-HM-0003 This DCP added .2 unions to a Y-strainer in the (

Instrument Air Compressor Outlet Blowdown 'Line to 1 l facilitate removal of the strainer basket. Adding the I unions did not create a new safety hazard to the plant nor did it affect.the safe shutdown.of the reactor.

This DCP did not change the plant effluent releases ,

and did not alter the existing environmental impact. l Therefore, no unreviewed safety or environmental questions'are invol-red.

l 4-HM-0016 This DCP replaced the input isolators for enalog computer points in the Redundant Reactivity Control system. The new isolators will improve the accuracy of the loops monitoring Reactor Dome Pressure, Reactor Water Level, and Standby Liquid Control System Tank Level. Improving the monitoring accuracy did not create a new safety hazard to the plant nor did it  !

affect the safe shutdown of the reactor. This DCP did I not change the plant effluent releases .and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

4-HM-0020 This DCP changed-out level transmitters on the Service Water and Circulating Water Hypoch1crination Tanks. 1 The new level transmitters will improve the- accuracy of the level circuits and did not create a new safety l hazard to the plant nor did they affect the safe shutdown of the reactor. This-DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

4-HM-0021 This DCP relocated a jumper in .the Cooling Tower .

Sample Station Panel to make the Cooling . Tower i Blowdown High Residual pH Alarm functional. This DCP  ;

removed 2 Temporary. Modifications and did not create a ned safety hazard to the plant nor did it affect' the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the

. existing . environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

DCP Description of Desian Chance Packace 4-EM-0022 This DCP wired the Domestic' Water Tank.High and Low Level Alarms in series to provide an alarm in the Control Room when a1High or' Low Level-exists in either tank. This DCP removed a Temporary Modification 'and i eliminated an invalid alarm. as well as providing the operational alarm. This DCP did not create. 'a new safety hazard to the' plant nor did it affect.the safe shutdown of the reactor. This DCP did not change. the  !

plant effluent releases and did not alter the existing: l environmental impact. Therefore, no unreviewed safety l or environmental questions are involved.

'4-EM-0024 This DCP installed spring inserts into Liquid Radwaste Check Valves to reduce the amount of maintenance, to l

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reduce the-number of invalid alarms, and to . protect  !

equipment from premature- damage. Installing the  !

spring inserts did not create a new safety hazard to l the plant nor did it affect the safe shutdown of the

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reactor. This DCP did not change the plant effluent  ;

releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved, l 4-HM-0027 This DCP increased the Diesel Generator Crankcase Vacuum Pressure Alarm Setpoints to eliminate nuisance l alarms. Eliminating these alarms did not create a-new

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safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the i plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety i or environmental questions are involved.

4-HM-0029 This DCP reduced the number of Cooling Tower Blowdown Radiation Monitoring Sample Pump trips by eliminating the low flow trip, and adding voltage suppression to ,

the Low Sample Pump Flow Contact Output. Reducing the i number of sample pump trips did not create a new safety hazard to the plant nor did it affect the safe  ;

shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing l environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

4-HM-0030 This DCP changed the Main Steam Line Radiation  !

Monitoring Alarm and Trip Setpoints to be consistent I with the Full Power Background Main Steam Line l radiation readings obtained during the Power Ascension l Steam Production Test. This setpoint change complies i with the Technical Specifications and did not create a '

new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent re:aases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are I involved.

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i DCP Description of Desian Chance Packace

'4-HM-0045 .This DCP provided an alternate power supply to the Salem Unit 1 and 2 non-lE Circulating Water- Pump Motors. The source of this alternate power is Hope i Creek's 13KV ring bus. This DCP did not create a new I

. safety hazard to the plant nor did it affect the safe  !

shutdown.of the reactor. This DCP did not change the -

plant effluent releases and did not alter the existing I environmental impact. Therefore, no unreviewed safety- -

or environmental questions are involved.

4-HM-0057 This DCP removed the internals ' 'm the' check valve on  !

the suction to the Caustic Injec. >n Pumps. Removing the internals prevents the loss of flow to_the caustic Injection Pumps and enhances the operation of the )

system. Removing the - internals did not create a new safety hazard to the plant nor did it affect the safe shutdown'of the reactor. This DCP did not change the plant effluent releases and did not-alter the existing .

environmental impact. Therefore, no unreviewed safety  !

or environmental questions are involved.  :

4-HM-0058 This DCP revised the setpoints for the Turbine Building and Reactor Building Temperature Controllers to prevent the freezing of the coils. Revising these setpoints did not create a new safety hazard to- the plant nor did it affect the safe shutdown of the  !

reactor. This DCP did not change the plant effluent  ;

releases and did not alter the existing environmental I impact. Therefore, no unreviewed safety or environmental questions are involved.

4-HM-0068 This DCP upgraded Probe Multiplexer Cards in the Reactor Manual Control System, the Rod Position Information System, and GETARS. The new cards provide higher voltage to the Position Probe Reed Switches.

The higher voltage provides greater electrical wiping of the contact surface and a greater force for punching through any oxide film on the contact surface. This will increase the- lifetime of the l l Position Probe Reed Switches. ' Upgrading the multiplexer cards did not create a new safety hazard to the plant nor did it affect the safe shutdown - of the reactor. This DCP did not change the plan't effluent releases and did not alter the existing i environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

4-HM-0075 This DCP removed split 0-rings from Emergency Diesel Generator Thermostatic Flow. Control Valves. This was done to conform to NRC letter IN-82-56 and did not.

l create a new safety hazard to the. plant nor did. it l affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the. existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

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.DCP Description of Desian Chance Packace  ;

4-HM-0076 This DCP modified the following portions of the.

Condensate Polisher System: High Resin' Shutdown Mode, the Water Bump Cycle, alarm windows, and the method of i transferring to and from , service. vessels. These I changes increase .the information available .to the operators, limited contamination, reduced radwaste, 1 and did not. create a new safety . hazard to the plant l nor did they affect the safe shutdown of the reactor. .

This DCP did not change the plant effluent releases and did not alter the existing environmental impact.

Therefore, no unreviewed safety or environmental )

questions are involved. j 1

4-HM-0077 This DCP is Safeguards.Information and did not create a new safety hazard to'the plant nor did it affect the I safe shutdown of the reactor. This DCP did not change L the plant effluent releases and did not. alter the existing environmental impact. Therefore, no:

unreviewed safety .or environmental questions are i involved.

4-HM-0080 This DCP revised the setpoints for the Rotating 1 Machinery Vibration Monitoring system to eliminate continuous overhead annunciator alarms in the Control Room. Revising the setpoints did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change 'the plant effluent releases and did not alter the existing )

! environmental impact. Therefore, no unreviewed safety i or environmental questions are involved.

1 4-HM-0081 This DCP installs additional antennas to enable the  ;

use of UHF radios for communication between the Offgas  !

Control Panel Room and the Main Control Room. Adding the antennas did not create a new safety hazard to the plant nor did it affect the safe-shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or 1 environmental questions are involved.

i e-HM-0093 This DCP changed the wording on an annunciator window to agree with the design drawings. Changing the annunciator window wording did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change. the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety l or environmental questions are involved.

',LDCP ' Description of Desian Chance Packace 1-HM-0101~ This:DCP 1 changed the~setpoints;;for Instrument. Air

'N . Dryer' Shuttle Valves: Low ~ Flow. .lTheisetpoint". changes decrease the probabilitylofL a' loss ofoInstrumentD Air and.did-not' create r.a-new safety .hazardito.the plant!

norLdid it affectrthe safe shutdown ofzthe-' reactor.

.This DCP did not change the:Lplant" effluent releases and did not' alter: 'the existing environmental; impact.-

Therefore, .no. unreviewed:: safety- or- environmental questions'are involved.

4-HM-0104. .This DCP replaced the1 valve. trim on Instr' ument Rack Rotometers. The- installed trim. is' toos large,.

i replacing it is. economical' and ' allows for: better control of the flow rate. Replacing'theftrim did not1 create a.new safety hazard'Lto the; plant nor did it affect the safe shutdown of the reactor. This.DCP2did-not: change the ~ plant- effluent. releases 'and did. not' alter the existing ' environmental impact. Therefore,

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no unreviewed safety or environmental questions .are involved.

l '4-HM-0107 This DCP replaced -an Analyzer Window to reflect the actual labeling of the Control = Rod . Drive Units. 'It also added the location of LPRM' strings to the core map to aid. troubleshooting' of. Reactor Manual- Control System. This DCP did not create a new safety: hazerd to the plant nor did it affect the safe shutdown of the reactor. 'This DCP did not change' the plant effluent releases -and did not alter the existing  ;

environmental impact. . Therefore, no unreviewed safety l l

or environmental questions are involved. 1 1

4-MM-0114 This DCP added an instrument block valve to allow the j removal of a pressure. transmitter in the Nuclear  ;

Boiler' system .without isolating other. instruments.

Adding.the valve did not create a new safety' hazard to the plant nor did it affect the safe shutdown-of the i reactor. This DCP did not change the plant . effluent j releases and did not alter the' existing environmental  ;

impact. Therefore, no .unreviewed safety..

or  !

environmental questions are. involved..

4-HM-0116 This DCP corrected the . labeling and wiring forL smoke  ;'

detectors in the -Control Room Emergency' Filtration system. -These corrections.did not create-a'new' safety hazard to the plant nor did ~it> affect the~ safe shutdown of.the reactor. This~DCPJdid.not change .the plant' effluent' releases and did~not alter the' existing environmental impact. -Therefore, no unreviewed safety or environmental questions'are involved.

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DCP ~ Description of-Desian Chance Packace 4-HM-0117' This DCP' implemented time constant setpoint changes to '

the Power System Stabilizer component of the Automatic Voltage Regulator to provide for on-line ' calibration' and testing. This did not create a new safety hazard 1

-to the plant nor did.it affect the safe shutdown of the reactor. This DCP did not change the plant j effluent releases and 'did not ' alter the existing' j environmental impact. Therefore, .no unreviewed safety or environmental questions are involved, i j

4-HM-0118 This DCP replaced the existing Seal Oil Pump Motor, Gearbox, and Coupling with an upgraded assembly. This upgrade reduces vibration and did not create a new j safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the

' plant effluent releases and did not alter the existing q environmental impact. Therefore, no unreviewed safety 1 or environmental questions are involved, f 4-HM-0120 This DCP provided thermal overload bypass capability for the screen wash system to conform to Technical 1

, Specifications. This capability did not create a new l l safety hazard to the plant nor did it affect the safe l shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety i' or environmental questions are involved.

l 4-HM-0121 This DCP corrected nameplates for alarm. card test i switches on the Service Water Head Tank Panel Level l Instrumentation. Correcting the nameplates did not J create a new safety hazard to the plant nor did it i affect the safe shutdown of the reactor. This DCP did i not change the plant effluent releases and did not alter the existing environmental impact. Therefore, ,

no unreviewed safety or environmental questions are involved. i 4-HM-0126 This DCP' revised the circuitry of a Safety Auxiliaries Cooling system valve to include the Overload Bypass Contact as required by Technical Specifications.

Correcting the Overload Bypass Circuitry did not create a new safety hazard to the plant ner did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases' and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. ,

4-HM-0130 This DCP corrected a jumper and switch position in the Auxiliary Building Diesel Area Heating, Ventilation, and Air Conditioning System to conform with the original design intent. This DCP did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This DCP did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

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1 Safety Evaluation Description of Temporary Modification Recuest'(TMR)._ l l

87-0082 This Temporary Modification' Request (TMR) associated ]

with this Safety Evaluation installed hinge pin cover 1 gaskets 'on the. "B" and "C" Reactor Feed Pumps. l Discharge Check Valve due to leaking hinge pin covers. 1 Adding the gaskets did not create a new safety hazard 1 to the plant nor did it affect the~ safe shutdown of l the' reactor. This TMR did not change the plant ;j effluent releases and did not alter the existing H environmental impact. Therefore, no.unreviewed safety 1 or environmental,questionsLare involved. <

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87-0086 This Temporary Modification Request (TMR) -associated with this Safety Evaluation installed a steam hose :l from the Solid Radwaste Auxiliary Boiler to. the i

l j IJitrogen Vaporizer. This temporary hose allowed ~ the )

Auxiliary Boilers to be removed from service and did l not create a new safety hazard to the plant nor did it I 4 affect the safe shutdown of the reactor. This TMR id i not change the plant effluent releases and did not )'

alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions ~ are H involved. ]

87-0132 This Temporary Modification Request (TMR) associated with this Safety Evaluation provided for a boiler to ,

l l revulcanize demineralized liners. The power is tapped -l from a non-Q, non-1E breakers. Its installation did.

not create a new safety hazard to the plant nor did it l l

l affect the safe shutdown of the reactor. This THR did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, environmental questions are l no unreviewed safety or 3 involved. l 87-0135 This Temporary Modification Request (TMR) associated with this Safety Evaluation allowed the use of Teflon thermocouple wire until the refuel outage. The i existing wire is damaged and the Teflon wire has been l determined to be an acceptable substitute. . Using the wire temporarily did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. This TMR did. not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved. i i

Safety Evaluation ' Description of Deficiency Report (DR)

87-0076 Thf Safety Evaluation enlarged 2 bolt holes on. a S a' .ty Auxiliaries Cooling , System piping elbow .to fa ilitate fit-up of a valve. Enlarging. the bolt holes did not create a new safety hazard to the plant nor did it affect ~the safe- shutdown of the reactor.

The deficiency did not change. the' plant- effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

87-0077 This Safety Evaluation authorizes the use of Grade B bolts to attach divider plates to an Auxiliary Boiler Steam Drum. The Grade B bolts are an acceptable j substitute for Grade A bolts in thic application. and their use did not create a new safety hazard to the l

plant nor did it affect -the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing i environmental impact. Therefore, no unreviewed safety l or environmental questions'are involved.

I 87-0085 High pressure in the Steam Seal Evaporator caused the l Steam Seal Evaporator Shell Safety Valve to lift and reset several times. This may have caused defects in the valve. This Safety Evaluation authorized the use ,

of this valve until the next outage because its safety '

relief function is still acceptable. Continued use of the valve did not create a new safety hazard to the plant nor did it affect -the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

87-0088 The nameplates of differential temperature switch modules for the Reactor Core Isolation Cooling Room

. Cooler are incorrect ~. These switches are spares and l

did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact.

Therefore, no unreviewed safety or environmental questions are involved.

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S'afety Evaluation Description of Deficiency Report (DR) 87-0089 A penetration seal in the Reactor Core Isolation Cooling Pump Room is not adequate as a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire barrier. A periodic fire watch is in place until the z penetration seal is reworked. Using a fire watch did j not create a new safety hazard to the plant nor did it l affect the safe shutdown of the reactor ~. The H deficiency did not change the plant effluent releases I and did not alter. the existing environmental impact. l Therefore, no unreviewed safety or environmental j questions are involved.

1 87-0090 A penetration seal in the South Radwaste CableL Tray  !

Area does not provide adequate flood protection. No .

visible separation space; exists, making the leakage {

minimal. No safety' related equipment is located in this cable tray area. Dispositioning this deficiency.

i "use-as-is" did not create a new safety hazard to the  ;

l plant nor did it affect the safe shutdown of the )

reactor. The deficiency did not change the plant j effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety i or environmental questions are involved.

87-0091 Wiring deficiencies associated with the installation of a DCP were identified during the post-installation walk-down of that DCP. None- of the deficiencies create a new safety hazard to the plant nor'did they F affect the safe shutdown of the reactor. The deficiencies did not change the plant effluent releases and did not alter the existing environmental i impact. Therefore, no unreviewed safety or l environmental questions are involved.

1 87-0092 The leak-off pipe for the valve that isolates the ]

Nitrogen supply from the Nitrogen Vaporizer unit and )

the Containment 7,tmosphere Control system is bent. l The leak-off pipe is effectively isolated from system l pressure by the valve packing. Dispositioning this j deficiency "use-as-is" did not create a new safety i hazard to the plant nor did it affect the safe j shutdown of the reactor. The deficiency did not 1 change the plant effluent releases and did not alter j the existing environmental impact. Therefore, .no I unreviewed safety or environmental questions are ]

involved.  !

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Sefety Evaluation Description of Deficiency Report (DR)

'87-0094 A safety relief valve providing overpressurization protection for the Oil LCooler Refrigerant piping and ,

l equipment is missing its seal wire. This relief valve  ;

is. designed without any external. adjustment's'and its I integrity can be verified by the undisturbed outer l body. painting, signifying that the. valve has not -been j disassembled. The missing seal wire did not create a l new safety hazard to the plant.nor did it affect the i safe shutdown of the reactor. The deficiency did not I change the plant effluent releases and did not alter the existing environmental impact. Therefore, no '

unreviewed safety or environmental questions are involved. 1 87-0095 The " test" indicating circuit tor a low. flow i transmitter in the Station' Service Water system is-I malfunctioning. The transmitter operates correctly, therefore its continued use did not create a .new j safety hazard to the plant nor did it-affect the safe l shutdown of the reactor. This deficiency did not j change the plant effluent releases and did not alter j the existing environmental impact. Therefore, no )

unreviewed safety or environmental questions are 1 involved. j 87-0096 Two valves used to balance system flow through the 1 Safety Auxiliaries Cooling System Heat Exchangers have i damaged seats. The . valves could still . be I re-positioned over their full length of travel to satisfy a change in system flow. The damaged valve I

seats did not create a new safety hazard to the plant j nor did it affect the safe shutdown of the reactor.

The deficiency did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are-involved.

87-0097 An indicating switch in the "B" Travelling Water.

Screen ir 'roken. This switch is for indication only.

and has adequate back-up. Additionally, the Travelling Water Screen is inspected for operability l as .part of an operator's rounds. This broken l indicating switch did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

87-0098 Two valves in the Station Service Water system rusted in position. 'The valves are able to operate as designed. Allowing them to operate in this condition

, did not create a new safety hazard to the plant nor l did it affect the safe shutdown of the reactor. The l

deficiency did not change the plant effluent releases and did not alter the existing environmental -impact.

Therefore, no unreviewed safety or environmental questions are involved.

Safety Evaluation Description of Deficiency Report'(DR) 87-0099' Travelling Water Screen Spray Pressure Gage Isolation Valves. rusted in the'open position. The pressure l instruments associated with :these- valves provide indication only. The valves being rusted open.did not create a new safety hazard to the' plant nor did it affect the safe shutdown of the reactor. The deficiency did not. change the plant effluent releases and did not alter the existing-environmental . impact.

Therefore, no unreviewed safety or' environment.al questions are involved.

l 87-0100 An orifice in the Liquid Radwaste system is sized incorrectly, causing a. sample pump to operate beyond its design point. Throttling the associated discharge valve brought the pump back to its design point and did not create a new safety hazard to the plant nor did it affect the safe shutdown of the' reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact.

Therefore, no unreviewed safety or environmental questions are involved.

87-0101 The shaft gasket for the Waste Filter Holding Pump in the Liquid Radwaste system was replaced with an identical shaft gasket. However, the replacement shaft gasket was not purchased with a certificate of compliance. Using the replacement shaft gasket did not create a new safety hazard to the plant'nor did it affect the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact..

Therefore, no unreviewed safety or environmental questions are involved.

87-0102 Insulation on wires leading to the Reactor Core Isolation Cooling Steam Line Drain Pot High Level Switch is cracked. The wire will be repaired using a Raychem. splice and may remain in service "as-is" until the repair can be completed. The cracked insulation did not create a new safety hazard- to the plant nor did it affect the safe. shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact. i Therefore, no unreviewed safety or environmental )

questions are involved.

87-0103 A snubber in the Core Spray system is too short. It is still able to continue to function properly and its continued use did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor. The deficiency did'not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.  ;

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!,' . .f Safety ~ Evaluation Descrip' tion of' Deficiency'RecortV(DR) l j

.87-0104; ;A pipe. clamp on>a; snubber in the: Residual Heat' Removal- "

systemfis. misaligned and4 1imits;thb ; rotation of' the- l

, snubber. The snubber ' strokelis'not,>1imitedtand :the. j snubber cansfunctioniproperly. .'<The'.fcontinued use .of

~

' q the snubberLdid noticreate'a.newLsafety hazard t'o .the plant nor. did- it: affect the -safe' shutdown- of :the q reactor. The deficiency did'not. ;changeL the plant effluent releases: and did! not alter. the~ existing- i environmental, impact; ' Therefore,,noLunreviewed safety '

or. environmental. questions are" involved.

'87-0105 The installed spring. pack ifor a . valve in Lthe ' Hig'h : -

Pressure Coolant LInjection' Lube Oil- ' Cooling' Water system cannot' attain its, desired. thrus t-'. The valve.

can still perform.'its' intended. accident fmitigation f unction-'and f its . continued use did not create a new safety hazard.to?the. plant nor did'it: affect:the. safe shutdown of- the' reactor. The deficiency' did not ch'ange the plant effluent. releases and did not l alter.

the existing environmental impact. Therefore, no unreviewed' safety or environmental.' questions. are involved.

87-0106 A Rocemont Card File Lock on a Residual Heat' Removal' '

relay cabinet was discovered to be malfunctioning during the performance .of a functional test.- The individual cards are held in place by screws co' the broken lock did not create-a new safety hazard to the plant nor did it affect the safe shutdown ,f the reactor. The deficiency did not change- the . plant effluent releases and- did not- alter; the existing environmental impact. Therefore, no unreviewed safety '

or: environmental questions are involved..

87-0107 A snubber rod end in the: Residual Heat Removal system' was sheared due to water bammer-. The' snubber has been.  :

reworked and a DCP will provide- blanks in the ' lines for a more positive 1 seal. Using. the snubber ~in' its current configuration - did t ot create a new safety.

hazard to the plant nor did it . affect 'the safe shutdown of the reactor. 'The deficiency. :did< not' change the plant effluent- releases'and.did'not~ alter the existing environmental impact. Therefore,' no unreviewed safety or environmental questions are involved.

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. 1 5afety Evaluation Description of Deficiency Report (DR) 87-0108 The portion of the valve stem that attaches to the .

valve' handwheel and stem nut of a vent and drain valve 1 in the Residual' Heat Removal system is broken ,off. l Since.the valve is operable by using a wrench instead j of the handwheel, its continued use did not create a new safety hazard to the' plant nor did it affect. the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact.. Therefore, no unreviewed safety or environmental questions are involved.

'1 87-0109 A safety relief. valve providing overpressurization protection for the Evaporator Refrigerant is missing its. seal wire. This relief valve is designed without i any external adjustments and.its integrity can be verified by the undisturbed outer body painting; '

signifying that the valve has not been disassembled.

The missing seal wire did not . create a new safety hazard to the plant nor did it affect the safe i

shutdown of the reactor. 'The deficiency did not I l change the plant effluent releases and did not alter I the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.

87-0115 A safety relief valve providing overpressurization l protection for the Evaporator is missing its seal I wire. This relief valve is designed without any external adjustments and its integrity can be' verified by the undisturbed outer body painting; signifying that the valve has not been disassembled. The missing seal wire did not create a new safety hazard to the plant nor did it affect the safe shutdown of the .

I reactor. The deficiency did not change the plant l effluent releases and did not alter the ' existing i environmental impact. Therefore, no unreviewed safety  !

l or environmental questions are involved. {

87-0117 Wiring for the CRIDS and GETARS computer points were found to be incorrectly landed. A DCP is being written to correct the deficiency. This wiring provides indication only and did not create a new safety hazard to the plant nor did it affect the safe

, shutdown of the reactor. The deficiency did not l change the plant effluent -releases and did not alter the existing environmental impact. Therefore, no unreviewed safety' or- environmental questions are involved.

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' Safety Evaluation Description'of Deficiency ReDort lDR)~

'87-0118L The"as-built weld l configuration laf ' structural. steels in the Control . Rod Drive ShieldingLBlockL differs 'from~

.as-designed. ~However~ the. as-builttis equivalents ' to.

as-designed and. need snot; be-' changed. The. design drawingLwill'be' changed
to reflect theiactual. plant.

y configuration. : Retaining. the.as-built,1 configuration f did:not create a new. safety hazard. tolthe. plant 'nor' ,

did it' affect the' safe 1 shutdown of the. reactor. .The'

' deficiency.did not: change 1the'plantieffluent . releases and did not? alter' thea' existing' environmental . impact.

Therefore,.c no .unreviewed-l safety orf environmental i questionsrare involved.

87-0119 The standby Liquid Contro11 System. Squib 1 Valve; Trigger.

Body and -Inlet Fitting were received'Lthrough- the Bechtel receiving' system instead of through the Public Service receiving system. At theftime of the: Jreceipt-of these parts, Bechtel had"a Public Service ' approved Quality Assurance program in place. The receipt of' those parts under: the 'Bechtel- Quality. .' Assurance program-did not create a new safety hazard tu) the plant-nor did it affect- the 'safeochutdown. of: the reactor. The deficiency did not change 'the . plant effluent releases. and did ,not alter- the existing-environmental impact. . Therefore, no'unreviewed: safety or environmental questions arel involved..

87-0130 The lantern ring in a Safety and Turbine Auxiliaries

~

Cooling System. valve was discovered to ~be damaged-during valve repacking. The lantern ring jLs used - to f evenly disperse the lubricant tinto the packing. Due.

to the ' evolution of new packing materials' (e.g.,

self-lubricating packing),- this_. capability. is not used; allowing:the lantern.-ring to be-removed rather than ta) be replaced.. -Removing the lantern ~ ring Edid-not create a new safety: hazard to.the plant'nor did it affect- the ' safe shutdown of -the' reactor. The deficiency did;not change the plant effluent releases and did not alter the existing. environmental , impact.

Therefore, no unreviewed- safety- oi- environmental-questions are involved.

'87-0134 The arc. barriers on 2 terminal' blocks in the . Safety Auxiliaries Cooling System Control are broken off.

.One of the terminal blocks is a spare; the.other has a" -

mounting screw . recessed 'well below- the termination lug,- surrounded by plastic / ceramic material ~._. The'

' design of the' terminal . blocks limits:the 1 possibility of an arc strike. Using these: terminal blocks "as-is" did not create a 'new safety hazard to the plant nor? -

did it: affect-the. safe shutdown of the reactor. The, deficiency did not change;the plant' effluent. teleases and did not alter. the' existing environmental impact.

Therefore, no -unreviewed safety or . environmental' questions are involved.

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. SnfEtv Evaluation Description of Deficiency Report '(DR) 1

. 87-0136 The steam deflectorLplate in the Steam Jet Air Ejector After Condenser separated from its- welds, breaking several tubes. _The tube separator plate may be used as-is while the steam impingment plate requires rework. .This disposition of the DR did not create a L

new safety hazard to the plant nor did it' affect the safe shutdown'of the reactor. .The deficiency did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no.

unreviewed safety or . environmental questions are involved.

~

l ~ 87-0137 Nine small holes were inadvertent 1y drilled. in .the L

diaphragm plate seating surface of-a Reactor Water Cleanup Heat Exchanger. The holes do not' prevent the heat exchanger from performing as designed and did not create a new safety hazard to the. plant nor did it affect the safe shutdown of the reactor. The deficiency did not change the plant effluent releases and did not alter the existing environmental impact.

Therefore, no unreviewed safety or environmental questions are involved. j i 87-0138 The diaphragm seating surface on- a Reactor Water Cleanup Heat Exchanger is low, causing a void between the diaphragm and the strongback. A stainless steel l shim plate will be installed to fill the void. This repair does not affect.the function of the system and did not create a new safety hazard to the plant nor did it affect the safe shutdown of the' reactor. The i

deficiency did not change the plant' effluent. releases I

and did not alter the existing environmental impact.

Therefore, no unreviewed safety- or environmental questions are involved.

87-0143 The cable for the Reactor Water Cleanup Outboard Isolation Valve was damaged. Repairing this cable did not create a new safety hazard to the plant nor did it affect the safe. shutdown of the reactor. The deficiency did not change the-plant effluent releases and did not alter the existing environmental impact.

Therefore, no unreviewed safety or environmental ]

questions are involved. j l

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  • O PSEG Public Service Electric and Gas Company P.O. Box L Hancocks Bridge, New Jersey 08038 Hope Creek Operations October 15, 1987 "w

U. S. Nuclear Regi11atory Commission y Document Control Desk O ui Washin;; ton , DC 20555 to gj O a

Dear Sir:

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MONTHLY OPERATING REPORT U HOPE CREEK GENERATING STATION UNIT 1 O DOCKET NO. 50-354 9 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for September are being forwarded to you. In addition, the summary of changes, tests, and experiments for September 1987 are included pursuant to the requirements of 10CFR50.59(b).

Sincerely yours, 1

M S. LaBruna General Manager -

Hope Creek Operations

, RAR:tib Attachment C Distribution l

The Energy oeople 95 2 t73(11M) b 67

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