ML20234D523
| ML20234D523 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/31/1987 |
| From: | Jensen H, Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709220115 | |
| Download: ML20234D523 (8) | |
Text
-
k
~ AVERAGE DAILY UNIT POWER' LEVEL
)86-354 DOCKET NO.
.H pe Creek' Gen. Station UNIT.
' 9/99/97 DATE H.'Jensen-g Y
COMPLETED,BY' 09).339-5261 TELEPHONE.
Aug. 1987 MONTH-DAY-AVERAGE DAILY POWER LEVEL DAY.
AVERAGE DAILY POWER LhVEL (MWe-Net)
(MWe-Net) 605-18 7
g7 862 885 2
8:
994 997 3
19 982 l'005 4
20 928 956:
5 23 999 989 6
22 99 1008 7
23 996 1015 8
24 977 1020 9
25 f
993 1013 to 26 l00l 1943 11
-27 999 1906 12.
.gg 0
1011 46
.\\
.13 -
29 1006 13 1
14 30
'994 836 15 31 i
44 Ik%k e7o922oi15 e70831" PDR ADOCK 05000354 Ah
..l
'R
- PDR, u
4
2---______;_____
OPERATING DATA' REPORT 86-354.
DOCKET NO.-
UNIT HOPE Creek Gen. Sta.
' M h ]
DATE.
Uu/ u u/ u /
COMPLETED BY H.
Jensen TELEPHONE (buy)349-dz61-OPERATING STATUS 744 Aug. 1987 GROSS HOURS.IN REPORTING. PERIOD 1.
REPORTING PERIOD 1067 2.-
CURRENTLY AUTHORIZED POWER LEVEL (MWt)
Ave /
MAX. DEPEND. CAPACITY-(MWe-Net) 1U0/
DESIGN ELECTRICAL RATING (MWe-Net)
.None 3
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net) h 4.
REASONS FOR RESTRICTION (IF ANY) c' THIS YR TO 6h0.0 h
.6
.6 5.
NO. OF HOURS REACTOR WAS CRITICAL U
0 0
6.
REACTOR RESERVE SHUTDOWN HOURS 654.9 5507.2 5795.2 7.
HOURS GENERATOR ON LINE 0
0 0
8.
UNIT RESERVE SHUTDOWN HOURS 9.
GROSS THERMAL ENERGY GENERATED (MWH) 2,089,005 16,678,410 17,608,818-10.
GROSS ELECTRICAL ENERGY GENERATED (MWH) 682,010 5,547,110' 5,884,750 11 NET ELECTRICAL ENERGY GENERATED (MWH) 650,901 5,311,487 5,597,311 12 REACTOR SERVICE FACTOR
'90.1 95.1 95.4 i
13.
REACTOR AVAILABILITY FACTOR 90.1 95.1 95.4 14.
UNIT SERVICE FACTOR 88.0 94.4 94.7 15.
UNIT AVAILABILITY FACTOR 88.0 94 4 94.7 q
16.
UNIT CAPACITY FACTOR (Using Design MDC) 82.0 85.4 85.7 82.0 85.4 85.7 17.
UNIT CAPACITY FACTOR (Using Design MWe) 18.
UNIT FORCED OUTAGE RATE 12.0 _
5.5 5.3 19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION) :
SURVEILLANCE 9/18/87,16 days REFUELING 1/31/87, 55 days 20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE;OF STARTUP:
.N/A
~
OPERATIN0' DATA REPORT.
UNIT SHUTDOWNS AND~ POWER' REDUCTIONS86-354 DOCKET NO.
UNIT'NAME Hope Creek Gen. Sta.
09/08/07 DATE ensen COMPLETED BY (609)339-5261 REPORT MONTH TELEPHONE
'4 METHOD OF l
SHUTTING DOWN THE TYPE REACTOR OR l
F FORCED DURATION REASON REDUCING CORRECTIVE ACTION /
{
l NO.
DATE S SCHEDULED (HOURS)
(1)
POWER (2)
COMMENTS'
)
l
\\
11 8/0 1 F
4.8 H
4 Continued from j
.last month Incorrect
' Operatiori of, an Inverter by j
l an Equipment' l
Operator:in j
preparation for' H
preventive maintenance 12 8/15 F
41.4 A
3 Automatic Scram "C" Reactor Feed Pump Diaphragm Rupture.
13 8/2!
l F
42.9 A
3 Automatic Scram Turbine Control
'I l
Valve Fast Closure When Testing #5 Combined-Intermediate i
Valve 3
SUMMARY
l r-
i a
MONTHLY OPERATING.
SUMMARY
AUGUST'1987
SUMMARY
'OF UNIT-OPERATIONS The Hope 1 Creek Generating 1 Station startedithe month'with
.a startup in progress, synchronizing the generator at 0455' on the first.
.While the
' Hope Creek-KeeneyL line:
' outage' continues, the unit'was able to operate at 100%: power 'with some reductions' required by the load dispatcher. lOn August 16,Jan: automatic. Reactor-Scram occurred due' to the C' RFPT' diaphram rupture.-
The unit was brought. back 'online.- on August'17 and-continued to.
operate'until August 29, when' another automatic Reactor' Scram occurred.
This scram' was due to a turbine? trip' initiated by a spurious pressure spike in.the Emergency Trip System header.during the-testing.of'~a.
Combined Intermed4 ate Valve.
The unit. was restarted 'on August 30 and was operating at 100%: power at months end.-
]
l R-001 RAR:t1b l
l l
t l
l d
l 1
l L
______.___.-.___m-
i
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS.
5 FOR THE HOPE CREEK GENERATING STATION j
AUGUST 1987 I
I l
i 1
l l
w
Safety Evaluation Description of Temporary Modification Reauest (TMR) 87-0070 The Temporary Modification Request (TMR) associated with this Safety Evaluation added a recorder to monitor the Standby Liquid contrn1 Automatic Start Circuitry.
This recorder will help to locate the circuit problem if the Standby Liquid Control system initiates without a valid signal.
The addition of this recorder 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.
f i
Therefore, no unreviewed safety or environmental questions are involved.
87-0083 The Temporary Modification Request (THR) associated with this Safety Evaluation added transmitters on the blowdown lines of existing station transmitters and pressure points.
The additional transmitters are required to support the ASME Turbine Performance test and did not create a -new safety hazard to the plant nor did it 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, no unreviewed safety or environmental questions are involved.
87-0084 The Temporary Modification Request (TMR) associated with this Safety Evaluation added a clamp and furmanite compound to seal a steam leak.
The steam leak is downstream of a flow orifice on a drain line to the condenser.
It is anticipated that the THR will be removed during the next "C"
Reactor Feed Pump Turbine outage.
This TMR did not create a new safety hazard to the plant nor did it 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, no unreviewed safety or environmental questions are involved.
' f i
Safety Evaluation Description of Deficiency Report (DR) 87-0068 This Deficiency Report identified the need to repair the insulation on two wires feeding a temperature switch in j
the Emergency Diesel' Generator system.
The insulation will be repaired 'using Raychem.
heat shrink tubing.
The damaged 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 envi'ronmental impact.
Therefore, no unreviewed safety or environmental questions are involved.
87-0072 A Desuperheater in the' Solid Radwaste system has not been.able to reduce the superheat per design.
This Safety
[
Evaluation authorizes the boring out of' l
l the Atomizing Steam Nozzle.
This will 1
increase steam flow and improve performance.
Boring out the nozzle 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.
87-0075 This Deficiency Report identified a l
pinhole leak in a section of Service I
Water piping.
The Safety Evaluation authorized the repair of this pipe by using a mechanical attachment to contain the leak.
This attachment will remain
]
in place until the pipe can be replaced.
The pieces of equipment located closest to the leak are the Safety Auxiliaries Cooling System Pumps.
The pumps have l
drip-proof motors and are mounted on pedestals to protect them
- during, flooding.
Therefore this 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.
}
l L
I
k
., ~. -
'OlPSIEG i
Public Service Electric and Gas Cornpany P.O. Box L Hancocks Bridge, New Jersey 08038 Hope Creek Operations l
September 15,.1987 U.
S. Nuclear' Regulatory Commission Document Control Desk Washington, DC 20555 l
l l
j
Dear Sir:
MONTHLY OPERATING REPORT' l
HOPE. CREEK GENERATING STATION UNIT 1 J
DOCKET NO. 50-354 I
In compliance with Section.6.9,, Reporting = Requirements for the Hope Creek Technical Specifications, the operating. statistics for I
August are being forwarded to you.
In addition, the summary ~ of changes, testo, and experiments for August 1987 are included pursuant to the requirements of 10CFR50.59(b).
Sincerely yours,
",1 gn S.
LaBruna
.j General Manager -
]
Hope Creek: Operations i
l RAR:tlb j
Attachment i
C Distribution
-)
1 i
\\
i 1
.rE1.f
.The Energy People t.
' 954t73 1M) 5+87-
_