ML20247G980
| ML20247G980 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/31/1989 |
| From: | Hagan J, Jensen H Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8909190183 | |
| Download: ML20247G980 (15) | |
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.O PSIEG 1
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Hope Creek Generating station l
Septem'er 15, 1989 o
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Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT HOPE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 In compliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for August cre being forwarded to you with the summary of changes, tests, and experiments for August 1989 pursuant to the requirements of 10CFR50.59(b).
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Sincerely yours,
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J Hagan Ge eral Manager -
Hope Creek Operations gpbRAR:bjh Attachment C Distribution 85 P190183 890331
{Dh ADOCK 0500 4
f The Energy People 95 2173 (MA 12 68 3
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.INDEX 1
NUMBER SECTION-OF'PAGES
, Average. Daily Unit. Power Level.........................- 1
- Operating Data Report..................................
2 Refueling Information..................................
1 Monthly. Operating Summary..............................
1 Summary'of Changes, Tests, and Experiments.............
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t AVERAGE DAILY UNIT. POWER LEVEL-DOCKET NO.
50-354
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UNIT
__ Hope Creek
'l DATE 9/15/89 COMPLETED BY H.
Jensen TELEPHONE (609) 339-5261 MONTH August 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 931 17 869 2
923 18 866 3
914 19 856 4
933 20 859 5
887 21 831 6
910 22 858 7
733 23 818 8
1078 24 880 9
895 25 706 10 887 26 987 11 935 27 840 l
12 906 28 813 1
13 889 29 836 l
L 14 941 30 16 i
L 15 764 31 0
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16 1025 l
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j OPERATING DATA REPORT DOCKET NO.
50-354 UNIT
__ Hope Creek I
DATE 9/15/89 COMPLETED BY
_H.
Jensen i
TELEPHONE. (609) 339-5261
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' OPERATING STATUS 1.
REPORTING PERIOD AUGUST 1989 GROSS HOURS IN REPORTING PERIOD 744 2.
CURRENTLY AUTHORIZED POWER LEVEL'(MWt)
'3293 MAX.. DEPEND. CAPACITY (MWe-Net) 1031 DESIGN ELECTRICAL RATING-(MWe-Net) 1067 MAX. DEPEND. CAPACITY (MWE-GROSS) 1076 (1) 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 HOURS REACTOR WAS CRITICAL 697.2 5382.1 20,329.7 6.
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 7.
HOURS GENERATOR ON LINE 697.2 5,376.8 20,008.9 8.
UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.
GROSS THERMAL ENERGY GENERATED (MWH)
.1,944,509 16,935,924 62,939,637 10.
GROSS ELECTRICAL ENERGY GENERATED (MWH) 643,360__
_5,576,629 20,803,073 11.
NET ELECTRICAL ENERGY GENERATED (MWH).
611,534.
_5,332,595
.19,882,695-12.
REACTOR SERVICE FACTOR 93.7 92.3 85.9 13.
REACTOR AVAILABILITY FACTOR 93.7 92.3 85.9 14.
UNIT SERVICE FACTOR 93.7 92.2 84.6 15.
UNIT AVAILABILITY FACTOR 93.7 92.2 84.6 r
16.
UNIT CAPACITY FACTOR (Using MDC) 79.7 88.7 81.5 17.
UNIT CAPACITY FACTOR (Using Design MWe) 77.0 85.7 78.7 i
'18.
UNIT FORCED OUTAGE RATE 6.3 1.0 5.7 l
19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):
Refueling, 9/16/89, 55 days 20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF START-UP:
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(1) CHANGE SHOULD HAVE BEEN MADE ON 1/89 REPORT WHEN MDC (NET) WAS l
REVISED.
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OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-354 UNIT
. Hope Creek Unit 1_
DATE 9/15/89 COMPLETED BY H.
Jensen REPORT MONTH AUGUST 1989 TELEPHONE (609) 339-5261 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR-F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /
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DATE S SCHEDULED (HOURS)
(1)
POWER (2)
COMMENTS 7
8/30 F-46.8 A
3 REACTOR SCRAM ON REACTOR' VESSEL LOW WATER LEVEL DUE TO HCU AIR HEADER COPPER PIPE SOLDER JOINT FAILURE LER 89-018 i
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SUMMARY
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REFUELING INFORMATION l
COMPLETED BY: __Chris Brennan ~
DOCKET NO: 50-354 UNIT NAME: Hope Creek Unit l' DATE:19/15/89 l
TELEPHONE: 3193 EXTENSION: N/A Month-
' September 1989
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1.
Refueling information has changed from last month:
YES X
NO 2.
Scheduled date for next refueling:
09-16-89 3.
Scheduled date for restart following refueling.:_11-10-89 4.
A)
Will Technical Specification changes or other license l
amendments be required?
YES X
NO B)
Has the reload fuel design been reviewed by the Station Operating Review. committee?
1 YES X
NO if-no, when is it scheduled?
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Scheduled date(s) for submitting proposed licensing action:
I 5-03-89 1
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Important licensing considerations associated with refueling:
NRC Generic Letter 88-16 type submittal has been made and
_ ill be used for Cycle 3 operation.
Reactor Engineering l
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_ ill require an LCR for their control blade design change.
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Number of Fuel Assemblies:
A) Incole 764 B) In Spent Fuel Storage (prior to refueling) 232 C) In Spent Fuel Storage (after refueling) 496 8.
Present licensed spent fuel storage capacity:
1290 Future spent fuel storage capacity:
4006 9.
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
3-13-91 J
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1 HOPE CREEK GENERATING STATION HONTHLY OPERATING
SUMMARY
AUGUST 1989 Hope Creek entered the month of August operating at approximately 90% due.to end of cycle coastdown.
On August 30, after completing 175 days of continuous power operation, the reactor automatically scrammed on Reactor Vessel Low Water Level due to a hydraulic control unit air header copper pipe solder joint failure.
At months end, startup activities were under way.
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SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS l
I FOR THE HOPE CREEK GENERATING STATION 1-1-
j AUGUST 1989 1'
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4 The foll'owing 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 theLbasis for'any technical specification is reduced.
The DCP's did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.
These DCP'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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DCP Description of Design Change Package.
'4EC-1076/03 This DCP provided communication interfaces between the Safety Parameter Display System computer and field devices.
This DCP is part of the project to install a new Safety Parameter' Display System to satisfy the requirements of NUREG 0737.
4HC-0227 This DCP installed electronic' load weighing systems in place of the hydraulic load weighing systems.
These systems were installed on both the Monorail Auxiliary Hoist and the Frame Mounted Auxiliary. Hoist located on the Refuel Bridge.
The new weighing systems provide improved accuracy, reliability, and visibility.
4HM-0283 This DCP provided a controlled area for snubber testing activities.
This area includes an Isometric Snubber. Test Machine, a snubber laydown area, and a snubber rework area.
It is located in a section of the Turbine Building that allows access to the Reactor Building.
without interfering with either Turbine Building Equipment or refueling activities.
4HM-0338 This DCP deleted the Circulating Water System logic that causes all 4 of the pumps.to trip if 2 trip within 2 minutes of each other.
It also changed the "B" and "D" Circulating Water Pump Discharge Valves to fail closed valves.
These changes will improve system reliability.
4HM-0375 This DCP added an Electric Hot Water Heater to the Domestic Water System.
The new Electric Hot Water Heater will utilize the existing Steam Hot Water Heaters to store the heated water.
This DCP also added a booster pump to circulate water between the heaters.
This DCP will reduce fuel costs by eliminating the need to operate the Auxiliary Boiler during summer l
months.
4HM-0412 This DCP provided locked personnel barriers to the Containment Pre-Purge Clean Up Room and the Fuel Pool Water Suction Area.
These locked barriers will control ingress of personnel to f
high and potentially high radiation levels.
4HM-0416 This DCP installed a valve on the clean out flanges on the oil Separator Tank.
This will allow future clean out activities to be l
performed easier.
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. Thio DCP installed a. Oil Ropo Skimmer in a sump in the Redwaste System.
The oil skimmer will remove the light asphalt fractions that are boiled off during solid radwaste processing.
This oil rope will remove the oil and allow the condensate from the extruder-evaporator to be processed-in Radwaste without fouling the Deep Bed Demineralizers and Radiation Monitoring Instrumentation due to' oil contamination.
4HM-0427 This DCP moved the Chlorine Analyzer Suction Piping for the blowdown line analyzer for the Main Process Line to the Stilling Well.
This.
change will allow the sample pump to take a representative sample of the liquid discharging to~ river by eliminating the current eductor
.effect.
-4HM-0524/01 This DCP installed equipment pads at the Service Water Chlorination System, a cement pad for the Circulating Water Dechlorination System, and a bracket on the Circulating Water Chlorination System.
These foundations will allow for the permanent installation of the J
equipment cabinets for the Chemical Monitoring System.
4HM-0527 This DCP modified two testable swing check valves in the Condensate and Refueling Water Storage and Transfer System.
The modifications will permit valve disassembly and reassembly from the room sides of the valves.
4HM-0546 This DCP replaced seat rings on control valves used to control Reactor Feed Pump Turbine minimum flow.
This change is required due to high pressure and high temperature water flashing through the valve internals and impinging on the lowerfportion of the valve body, which causes erosion.
4HM-0580 This DCP installed tubing to allow for chemical tracer testing of the Feedwater Flow Venturls to determine their accuracy.
This includes both injection tubing and sample tubing.
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4HH-0611 This DCP installed a 1 inch isolation valve in the "B" Primary Containment Instrument Gas
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Compressor Text Return Suction Line.
The valve will prevent condensate from forming in this line and entering the compressor.
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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 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 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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.THR
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i 89-0057 This TMR bypassed a failed vibration Monitoring j
Probe for the Circulating Water Pump.
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probe is one of two installed on the pump.
-Bypassing the probe until a replacement probe can be installed-will eliminate a nuisance
-overhead annunciator alarm in the Control Room.
89-0064 This TMR raised the pressure regulator.setpoint of the Electro-Hydraulic Control System.
Raising the setpoint maintains-the Reactor Steam Dome Pressure at the rated value during coastdown.
89-0073 This TMR' lifted leads from a high temperature switch in the Filtration, Recirculation, and Ventilation System.
Lifting the leads will prevent the closing of isolation dampers due to erroneous. indication from the temperature element associated with the temperature switch.
89-0074 This THR relocated the upper stop on the Fuel Preparation Machine to allow ungrappling of new fuel bundles to be done above'the water.
This will allow the polar crane grappling equipment to remain dry, reducing the potential for the spread of contamination.
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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 DR did 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 impact.
The Safety Evaluation determined that no unreviewed safety or environmental questions are involved.
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'?89-0068' Subsequent to'the installation of en-Intermediate Range Monitor, the unit'was not able to meet the vendor,specified pressure test' acceptance criteria.
This does'not-affect the ability of the Intermediate Range Monitor-Detector and'the associated electronics to perform their intended safety functions.and may be used "as is".
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