ML20235J338
| ML20235J338 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/31/1989 |
| From: | Hagan J, Jensen H Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8902240247 | |
| Download: ML20235J338 (13) | |
Text
.__
- ,.;. p.
AVERAGE DAILY UNIT POWER LEVELL l.
s DOCKET NO.
50-354 UNIT Hope Creek ij I
DATE 2/15/89 i
l
' COMPLETED BY H Jensen i
i TELEPHONE (609)'339-5261 HONTH January 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1012 17 1030 2
995 18.
1022 3
1022 19
'986 4
1018 20 1029 l 1012 21 999 6
970 22 1008-7 955 23 1009 8
1014 24 1032 9
1007 25 1004 10 1006 26 1009 11 1024 27 1003 12 1010 28 1018 13 1009 29 1010 14 1007 30 1012 15 1013 31 1012 16 989
~2.
The above-values are only available from station meters which read low due to a design problem scheduled for correction by the second quarter of 1989.
f3 gos noocuosoo<g434
%g e90224o247 s90131 a
OPERATING DATA REPORT l.
DOCKET No.
50-354 UNIT Hope Creek DATE 2/15/89 COMPLETED BY H. Jensen
/4!
TELEPHONE (609) 339-5261 OPERATING STATUS 1.
REPORTING PERIOD January 1989 GROSS HOURS IN REPORTING PERIOD 744 2.
CURRENTLY AUTHORIZED POWER LEVEL (MVt) 3293 UAX DEFEND. CAPACITY (MWe-Net) 1031 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 744.0 744.0 15,691.6 6.
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 7.
HOURS GENERATOR ON LINE 744.0 744.0 15,376.1 8.
UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
)
9.
GROSS THERMAL ENERGY GENERATED (MVH) 2,441,854 2,441,854 48,445,568 10.
GROSS ELECTRICAL ENERGY GENERATED (MVH) 810,292_
810,292 16,036,736 11.
NET ELECTRICAL ENERGY GENERATED (MWH) 776,592 776,592 15,326,692 12.
REACTOR SERVICE FACTOR 100.0 100.0 84.5 13.
REACTOR AVAILABILITY FACTOR 100.0 100.0 84.5 14.
UNIT SERVICE FACTOR 100.0 100.0 82.8,
15.
UNIT AVAILABILITY FACTOR 100.0 100.0 82.8 16.
UNIT CAPACITY FACTOR (Using MDC) 101.2 101.2 80.0 17.
UNIT CAPACITY FACTOR (Using Design NVe) 97.8 97.8 77.3 18.
UNIf FORCED OUTAGE RATE 0.0 0.0 7.0 1
19.
SHUTDOWNS SCHEDULED OVER ;! EXT 6 MONTHS (TYPE, DATE, & DURATION):
f
- Midcycle, 2/18/89, 17 days i
20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
N/A I
i l
I l
\\
l l
l c
4 i
b,,,:., :.
OPERATINGLDATA REPORT
~
UNI.T SHUTDOWNS.AND' POWER REDUCTIONS.
I DOCKET.NO. _S.0-354 UNIT
_Fj opA_Cr e ek '_ _ Uni t ' 1._
DATE' _2/JJ/J9 COMPLETED BY-
_H.
Jens_en REPORT ~ MONTH _,_JennuAty 1_93 9_
TELEPHONE- (609) 339-526J METHOD OF SHUTTING DOWN THE
. TYPE REACTOR OR F FORCED DURATION REASON REDUCING CORRECT.IVE ACTION /
NO.
DATE S SCHEDULED
-(HOURS)
(1)
POWER (2)
COMMENTS NONE
?
I
SUMMARY
L y
h REFUELING INFORMATION-
'I COMPLETED BY: -Chris Brennan DOCKET NO.: 50-354 UNIT NAME: Hope' Creek Unit 1 DATE: 2/15/89 f.
TELEPHONE: (609) 339-3193 Month January 1989 1.
Refucling information hasLehanged from las't month:
_l
.YES NO X
2.
Scheduled date for next refueling:
09-22-89 3.
Scheduled date for restart following refueling:
11-07-89' 4.
A)
Will Technical Specificatioti changes or other license amendments be required?
YES X
NO B) Has the reload fuel design been reviewed by the Station Operating-Review Committee?
YES NO X
If no, when is it scheduled?
5-07-89 5.
Scheduled date(s) for submitting proposed licensing action:
6-07-89 6.
Important licensing considerations associated with refueling:
Information not presentiv available 7.
Number of Fuel Assemblies:
'A) Incore 764 B) in Spent Fuel Storage 232 I
8.
Present licensed spent fuel storage capacity:
1108 I
Future spent fuel storage er.pacity:
4006 i
l 9.
Date of last refueling that can be discharged to spent fuel pool assuming the present licensed capacity:
11-07-89 l
i 1
)
\\*
)
-]
HOPE CREEK GENERATING STATION-
'l H0HTHLY OPERATING
SUMMARY
January 1988-Hope Creek entered the month of January operating at 100% power.
On January 31,. the plant completed its 83rd day of power operation.
1 1
l 1
i i
I
(
l
n-7..;
)
.1 I
i
SUMMARY
OF CHANGES, TESTS, AND' EXPERIMENTS.
FOR THE HOPE CREEK GENERATING STATION January 1989 l-l l
l:
l-L I~
l.'.
1 I
l L
,n.
I
.The following Design Change Packages: (DCPs) have been evaluated to I-
' determine:
'i 1).
if the probability of occurrence or the-consequences of.an 4
~
L
' accident or malfunction of equipment important to safety previously evaluated' in the safety analyris' 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' i
l 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 I
environmental impact.
The Safety Evaluations determined that. no unreviewed safety or environmental questions are involved.
i
.i l
cDCP
' Description of Desian Chance Package
.u.
s 4EC-1024/13
.This DCP installed' permanent platforms and ladders
.for the Residual Heat Removal Pump Motors and 'the'.
Core Spray' Pump Motors.
This will facilitate I
maintenance, surveillance' ' testing, and the chemical addition' process as well as. improving personnel < safety.
4HM-0163 This DCP reduced the trip setpoints of the Primary and' Backup Pressure Switches for the Backup Stator Vater Pump, Reducing the setpoints will eliminate i-false automatic -starts.of -the Stator Cooling-L Pumps.
The original' setpoint calculation was based on a' higher than actual discharge pressure.
4HM-0363 This is a document-only DCP that corrected errors on two vendor drawings.
The drawings reflect.the logic used by
'the Circulating' vater Hypochlorination. Limit Switches for injection valves.
4HM-0390 This DCP modified 2 hangers located on. Reactor Building 77' elevation, on the Service Water Outlet from 'the-Reactor. Auxiliaries'.
Cooling System..These hangers provide Seismic support to
'l the line where it. penetrates the Secondary.
l Containment and returns to the Cooling Tower.
{
This DCP did not impact the seismic / structural
{
design of the hanger, but inproves access to -the j
piping.
l 4HM-0437 This DCP raised the Thrust. Position Alarm Setpoints for the Reactor Feed Pumps.
The' 4
original setpoints were too low, causing a
continuous overhead annunciator alarm in-the 1
Control Room.
4HM-0479 This DCP corrected the Instrument Calibration Data Card for the Seal Oil to Hydrogen Pressure Differential Control Valve.
The revised setpoint is in conformance with vendor recommendations.'
4HM-0494 This DCP encapsulated a cracked weld at a Main Condenser Penetration.
The encapsulation device I
will seal any leakage and strengthen the penetration transition piece.
4HM-0514 This DCP installed a set of flanges on the Steam Supply Line to one of the First Stage Air Ejectors l
on the "B" Steam Jet Air Ejector.
The flanges will facilitate maintenance.
1
)
4UM-0517 This DCP encapsulated a steam leak on the "C"
f Reactor Feed Pump Turbine Steam Supply Drain Line.
l The encapsulation device adds integrity to the line, but will not overstress it.
_ __m
p-
~
DCP Description of Desian chance'Packace
- l.,
4HM-0525 This DCP encapsulated a section of..the "A" Reactor-4 Teed Pump. Turbine Low. Pressure Steam Supply Drain-Line-which experienced wall thinning.
The encapsulation device will prevent steam' leaks, and
- improve integrity, but will not-overstress the
- pipe.
.' 4HM-0 5 3 4.
This DCP encapsulated a section of the "B" Reactor
' Feed Pump Turbine Low Pressure Steam Supply _ Drain.
l Line which, experienced wall thinning.
The encapsulation device will prevent steam leaks,.and' improve integrity, but: will not -overstress the l..
pipe.
1 i
\\ ^
- L.
s.
4',
.The following. Temporary. Modification' Requests- (TMR'S)' have Ibeen-evaluated to determine:
k;
- 1)'
if the probability of occurrence or the consequence < of :an.
accident-or malfunction of-equipment !important. to safety' previously, evaluated. in the' safety analysis l report may be
-increased; or u
- 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 8
3) if the margin of safety as defined in the basis for any technical specification is reduced.
The TMR'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 Evaluation determined that no unreviewed safety or environmental questions are involved.
= _ _ - - _ _ _ _ - -
Safety Evaluation Description of Temocrary Modification Recuest (TMR) 89-0003 This TMR added the #6 Main Generator Phase B Stepup Transformer Cooling Fan and Pump in place of the #5 Fan and Pump.
The #5 Cooler was taken out of service due to a suspected loose object in the cooler outlet area.
l 89-0005 This TMR replaced cameras in the Solid Radwaste System with a newer model that is more reliable, i
..,S
- bt c ',4 :
INDEX
.w 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.............
6 1
1 I
=o, He PSIEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 U
Nuclear Department Febrtiary 15, 1989 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT HOTE CREEK GENERATING STATION UNIT 1 DOCKET NO. 50-354 i
In ecmpliance with Section 6.9, Reporting Requirements for the Hope Creek Technical Specifications, the operating statistics for Jcnuary are being forwarded to you with the summary of changes,
- tests, and experiments for January 1989 pursuant to the requirements of 10CFR50.59(b).
l 4
Sincerely yours,
[
Hagan j
General Manager -
Hope Creek Operations 7ORAR:blf Attachment C Distribution 4
)
4 The Energy People I
j l
j 9s-2ics n uov; 3 2 84