ML20215E585
| ML20215E585 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/1987 |
| From: | Labruna S, Pfizinmaier M Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706220034 | |
| Download: ML20215E585 (13) | |
Text
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i AVERAGE DAILY UNIT POWER LEVEL 86-354 DOCKET No.
Hope Creek Gen. Station UNIT 06/03/87 DATE M.
Pfizenmaier COMPLETED BY (609) 339-5261 TELEPHONE "Y'
MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net)
(MWe-Net) l 941 933 37 926 935 18 I
928 924 39 932 937 4
20 l
21 5
921 6
22 945 933 7
23
%8 8
24 927 928 25 g
932 9
26 10 946 11 27 4
922 28 12 938 826 29 930 807 30 885 15 31 16 I
po86 R885 S$8SkR4 Is d a
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OPERATING DATA REPORT j
DOCKET NO.86-354 i
UNIT Hope Creek Gen. Sta.
DATE 06/03/87 1
COMPLETED BY M.
Pfizenmaier i
TELEPHONE (6091339-5261 OPERATING STATUS 1.
REPORTING PERIOD Mav 1987 GROSS HOURS IN REPORTING PERIOD 744 I
2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 MAX. DEPEND. CAPACITY (MWe-Net) 1067*
DESIGN ELECTRICAL RATING (MWe-Net) 1067 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 744 3452 3740 6.
REACTOR RESERVE SHUTDOWN HOURS 0
0 0
7.
HOURS GENERATOR ON LINE 744 3427.1 3715.1 8.
UNIT RESERVE SHUTDOWN HOURS 0
0 0
9.
GROSS THERMAL ENERGY GENERATED (MWH) 2.208.593 _10.198.393 11.128.791 10 GROSS ELECTRICAL ENERGY GENERATED (MWH) 73 5. 898 3.429.058 3.726.698 11.
NET ELECTRICAL ENERGY GENERATED (MWH) 705.208 3.286.429 3.572.253 12.
REACTOR SERVICE FACTOR 100 95.3 95.6 13.
REACTOR AVAILABILITY FACTOR 100 95.3 45.6 14.
UNIT SERVICE FACTOR 100 04.6 on 15.
UNIT AVAILABILITY FACTOR 100 44 6 49 16.
UNIT CAPACITY FACTOR (Using Design MDC) 88.8 85 RR 6 17.
UNIT CAPACITY FACTOR (Using Design MWe) 88.8 AS RR_A 18.
UNIT FORCED OUTAGE RATE D
Ra 9
19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION):
Scheduled - Surveillance 09/17/87, 15 days 20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 0
Estimated Value.
Actual value to be determined in July or August 1987.
(
OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No.86-354 UNIT NAME Hope Creek Gen. Sta.
DATE 06/03/87 COMPLETED BY M.
Pfizenmaier REPORT MONTH May 1987 TELEPHONE (609)339-5261
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METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /
NO.
DATE S SCHEDULED (HOURS)
(1)
POWER (2)
COMMENTS None I
I t
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SUMMARY
See attached I
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I e
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HOPE CREEK GENERATING STATION MONTHLY OPERATING
SUMMARY
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J MAY 1987 l
The Hope Creek Unit entered the month operating at 90% power with
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this output being the administrative limit established by the Electrical System Operator based on electrical system stability considerations.
Varying limits are placed on the output of the Hope Creek and Salem Generating Stations as a result of the loss of the Hope Creek /Keeney 500KV transmission line.
(See the Monthly Operating Summary, March 1987, for additional details.)
The unit operated at essentially these established limits throughout the month and did not experience any reportable shutdowns or power reductions.
On May 31, the unit completed its 91st day of continuous power operation.
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SUMMARY
OF CIIANGES, TESTS, AND EXPERIMENTS FOR TIIE IIOPE CREEK GENERATING STATION MAY 1987 l
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jlCE Descriptip2.qf Design Change Egghgg 4-EMC-86-0070 This DCP installed additional hangers on the Cooling Tower Hot Water Distribution Piping.
These hangers provide additional protection to prevent the piping from falling and damaging the piping, fill sheets,
- nozzles, and other parts.
This DCP did not create a new safety hazard to the plant nor did it affect the safe i
shutdown of the reactor.
It did not change I
the plant effluent releases and did not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
4-HMJ-86-0597 This DCP modified the power supply failure alarm circuits in Vibration Monitoring Panels to provide normally closed contacts for the control room overhead annunciator.
The pre-DCP configuration indicated Vibration Monitoring System Power Supply Failure when the Power Supplies were functioning correctly.
l This wiring change resolved the discrepancy 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 releases and did not alter the existing environmental inpact.
Therefore, no unreviewed safety or environmental questions are involved.
4-EMJ-86-0969C This DCP corrected various
- legends, mimics, and naaeplates in the Main Control Room to conform to design documents and to meet NUREG 0700 requirements.
These deficiencies were discovered during an as-built walkdown.
Correcting these deficiencies reduced the probability of operator error and did not create a
new safety hazard to the plant nor did it affect the safe shutdown of the l
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 DCE
.DescripliDD D1 ESEigD.ChaDgg Package 4-EMC-86-0988 This DCP provided for the surface preparation and painting of floors, walls, and structural steel in the Turbine Building.
The pretreatment included a
decontaminative surfacer.
This painting provide an upgrade in coating material quality and did not create a new safety hazard to the plant nor did it i
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.
e
Hafety Evaluation Description of Deficiency Report (DR) 87-0017 This Deficiency Report identified a
switch as being inoperable.
The function of this switch is to annunciate the Fuel 011 Filter Differential Pressure High window.
There are local indicators to verify the actual differential pressure; therefore, operating the plant until a
replacement switch could be obtained 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.
87-0022A A
non-adjustable pressure switch on a
Diesel Generator is set to close at 380 PSlG and to open at 440 PSIG.
FSAR Sections 9.5.6.2 and 9.5.6.5 indicate that the Diesel Generator Starting Air Compressor will cycle between 380 and 425 PSIG.
Since the switch met the Tech Spec limit of closing at 380 PSIG, it did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
The deficiency did not create a new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
It did not change the plant effluent releases and did not alter the existing environmental impact. Therefore, no unreviewed safety or environmental questions are involved.
87-0022B The Diesel Generator "A"
Lube Oil Keepwarm Temperature Thermostat could not be calibrated within the required range.
This acts as a temperature switch and is utilized for annunciation only.
Because there is also a
local temperature indicator, operating the plant until a
replacement could be obtained did not create a new safety hazard to the plant I
nor did it affect the safe shutdown of l
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.
e HCE Description af Deficiency Report IDEl 87-0022C Corrosion due to the loss of epoxy phenolic lining was observed on the "B"
f Service Water Strainer.
This Safety Evaluation determined that the strainer is able to perform its designed function in its slightly degraded condition.
The strainer will be repaired during the next planned outage or upon further degradation of the strainer.
The corroded strainer 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.
87-0025 This Deficiency Report deals with a
calibration check performed on a
Rosemount narrow range pressure transmitter.
The calibration check was satisfactory.
However, the vendor manual specified accuracy of the pressure transmitter is
+.25%,
and the most accurate piece of test equipment available at the time with a sufficiently high range was only able to calibrate the transmitter within
+1%.
This Safety Evaluation determined that since the transmitter is used only to provide a
signal to a recorder and is not
" safety related" it could be used as is and did 1
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.
o
DCE D92.9.tlD11DD DL DefLDlDR9Z Report 1 DEL 87-0030 Electro Thermal Links installed in a
Carbon Dioxide Fire Damper Assembly were not wired in accordance with the manufacturers instructions.
The purpose of the Electro Thermal Links is to close the dar.ipe r s in case of a
fire alarm.
However, the current method of wiring did not prevent the Electro Thermal Links from fulfilling their intended function; i
therefore, they did not create a
new safety hazard to the plant nor did they 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.
87-0032 SE-Foam was used in penetration seals after its shelf-life had expired.
- However, a
sample of the material was taken at the start of each shift to determine
- density, color, and cell-structure.
The results of these sample tests were acceptable.
Therefore, the use of this foam 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.
87-0033 Silicone Foam was used in Fire Rated penetration seals without having the required certificate of compliance The manufacturer of the foam was contacted and provided the required certificate.
The use of the foam 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.
DCE Dsscription af Deficiency Report (DR) 87-0036 A
480V Feeder Cable to a Service Water Exhaust Fan had a cut in its insulation.
The problem was corrected by repairing the insulation.
The repair did not degrade the original design or properties of the Feeder Cable 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.
87-0037 A
Reactor Water Cleanup Heat Exchanger developed a
crack in the Channel Head Diaphragm Weld.
This Safety Evaluation authorized repair of the weld and installation of a full face gasket on top of the diaphragm.
The gasket was installed as a precaution in the event of a
future failure of the diaphragm seal weld.
The Reactor Water Cleanup system automatically isolates on-a high flow mismatch between the suction flow and the sum of the return and blowdown flows.
This deficiency did not affect differential flow isolation capability; therefore, it 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.
87-0038 During the performance of a
preventive maintenance procedure, power supplies in the Reactor Recirculation system were discovered to be in an out-of-calibration condition.
All of power supplies available in the storeroom were also out of tolerance and non-adjustable.
This Safety Evaluation provides justification for relaxing the tolerance.
The power supplies 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 IlgE s rl p i l s n p.f Temporary Modification Saigty Evaluation Request JTMR) 87-0019 The Temporary Modification Request (TMR) j associated with this Safety Evaluation
{
added a
connection to a flange and ran i
hoses from the connection.
The connection and hoses provided a back-up water supply to hose stations in the l
Auxiliary Diesel Building and did not increase the probability of a fire.
It did not affect the
- deluge, carbon
- dioxide, or fire detection systems.
It 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 l
alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
87-0031 The Temporary Modification Request (TMR) associated with this safety Evaluation jumpered out a terminal and printer from the Fire Detection system.
The terminal was returned for repairs.
Therefore, the i
jumper was required to maintain the l
system in an operable condition.
This TMR did not impact alarm receipt capabilities and did not create a
new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
It did not change the plant effluent releases and did not alter the existing environmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
87-0039 The Temporary Modification Request (TMR) associated with this Safety Evaluation jumpered out a terminal and printer from the Fire Detection system.
The terminal was returned for repairs.
Therefore, the jumper was required to maintain the j
system in an operable condition.
This i
TMR did not impact alarm receipt capabilities and did not create a
new safety hazard to the plant nor did it affect the safe shutdown of the reactor.
It did not change the plant effluent releases and did not alter the existing environmental impact.
Therefore, no 1
unreviewed safety or environmental questions are involved.
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O PSIEG
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Public Service Electric and Gas Company P.O. Box L Hancocks Bridge, New Jersey 08038 Hope Creek Operations June 15, 1987 U.
S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
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 May are being forwarded to you.
In addition, the summary of
- changes, tests, and experiments for May 1987 are included pursuant to the requirements of 10CFR50.59(b).
Sincerely yours,
$, [ A6Rurid S. LaBruna General Manager -
Hope Creek Operations WJM:tlb Attachment C Distribution The Energy People
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9k2173 f I ? M; $ 87