ML20115C142
| ML20115C142 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/30/1992 |
| From: | Hagan J, Hollingsworth, Zabielski V Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9210190181 | |
| Download: ML20115C142 (11) | |
Text
.
s.
)
1 0 PSEG Public Service Electnc and Gas Company-P O. Ror 236 Hancocks Briope, New Jersey 08038' Hope Creek Generating Station -
t.
l
.L i
' October 15, 1992'
-i d'
F
. U.
S.
Nuclear Regulatory Commission Document-Control-Desk Washington, DC 20555
Dear Sir:
f i-t MONTHLY OPERATING REPORT i
- HOPE-CREEK GENERATION: STATION UNIT 1-DOCKET NO. 50-354 In compliance with Se'ction 6.9, Reporting-RequirementsLfor-the Hope Creek Technical Specifications, the__ operating.
l statistics for September are being. forwarded to.you along_with l-the summary of changes, tests, and experiments.-for September 1992 persuant to.the requirements of 10CFR50.59(b).
'E l-Sincere
- yours, l
5 J.
ag in' Gen al M anager_ '-
l (f
Hop.Cre
-Operations Q RAR:ld Attachments-
_C Distribution--
4
[
e k-j s
jL-.
J
)sunam 9210190181 920930 n
rR axCw xxx,.
ng,n PDR 1-
' J- -,
,/-~,-,..,
, ~. _ _. _.... _ _ _ _.. _. _. _ _ _.. _.___ _. _ _ _ _ _ _ _ _ _ _. _ _ _ _. -
f
\\
i i
J INDEX i
i a
NUMBER SECTION OF PAGES i
1 Average Daily Unit Power Loyol.
1 operating Data Report'.
2 j
i Refueling Information.
1 Monthly operating Summary.
1 Summary of Changes, Testre, and Experiments.
4 i
I 6
i i
(
)
'i 9
)
b e
wr..',,,,,,,,-
, mi.,., r, w, l, d, i.,,,,-, L,..,
,,..e v.,
s.
l,.
..,-.v
.,,-w m.<,-+n
...,.n
,,,..m
.-_.._... _._=-_ - __ _ -__...-
AVERAGE DAILY UNIT POWER LEVEL 4
DOCKET NO.
50-354 UNIT llope_.f'Ieek j
i DATE 10/15/92 4
COMPLETED BY V.
Zabielski TELEPilONE (609) 339-3506 4
l i
MOWTH Srptember 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWo-Not)
(MWo-Not)
{
3.
1042 17.
2 i
2.
1036 18, 2
3.
1035 19.
A 4.
1028 20.
2 5.
1Q22 21.
D 6.
1043 22.
2 3
7.
1019 23.
2 t
8.
1031 2C.
A 9.
1010 25, 2
10.
1010 26.
A 11.
Ef' 27.
p 12.
2 28.
p 13.
A 29.
Q' 14.
D 30.
A
.15.
D 31.
Ulh I
16.
2
{
1
- 1 J.,, ~,.. ~
n
J j.
1 OPERATING DATA REPORT i
DOCKET NO.10-354 j
UNIT Uppe Creek
'g k og -
DATE 10/15/92 y
i COMPLETED BY V.
Zabielski Vid TELEPHONE f6091 339-3506 OPERATING STATUS
}
1.
Reporting Period September 1992 Gross Hours in Report Period 11Q 2.
Currently Authorized Power Level (Mh6.)
3293 i
Max. Depend. Capacity (MWo-Net) 1931 i-Design Electrical Rating (MWo-Net) 1111 1
-l j
3.
Power Level to which restricted (if any) (MWo-Net)
Eqng
^l 4.
Reasons for restriction (if any)
This Yr To 1
Month Date Cumulgtrig 5.
No. of hours reactor was critical 267.0 5804.5 42.965.8 4
j 6.
Reactor reserve shutdown hours AAA ExQ Ax2 i
i 7.
Hours generator on line 266.6 5742 9 12 316.6 4
{
8.
Unit reserve shutdown hours 222 Dag 212 9.
Gross therm-1 energy generated 237.402 18.508.361 124.505.506
]
(MWH)
- 10. Gross electrical energy 281.500 6.145.590 44.498.084 i
generated (MWH)
- 11. Not electrical energy generated 263.244-
,5.868.532 12 520'081 1
1
- 12. Reactor service factor 11J1 88.3 Aita i
- 13. Reactor availability factor 37.1 88.3 84.8 j
- 14. Unit service factor J7.0 87.3 Sj2l 15.-Unit availabilit, factor 2249 87.3 83.5 l
- 16. Unit cal,acity factor (using MDC) 35.5 86.6 1111 i
- 17. Unit capacity factor 34.3 83.7 Igxg (Using Lesign MWe) j
- 18. Unit forced outage rate azQ 122 Lixq
- 19. Shutdowns scheduled over next 6 months (type, date, & duration):-
None
- 20. If shutdown at end of report period, estimated date of start-up:
i 11/11/92 k
1
.. -. _,. _ - ~. --- _ -
I i.
OPERATING DATA REPORT
)
UNIT S!!UTDOWNS AND POWER REDUCTIOllS JOCKET NO.
50-354 UNIT Hope Creek DATE 10/15/92 i
COMPLETED BY V.
Zabielski_,_
TELEPllONE (609) 339-3506 1
MONTil SeDtember 1992 5
METHOD OF Sil0TTING DOWN Tile TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE i
l NO.
DATE S= SCHEDULED (HOURS)
(1)
POWER (2)-
-ACTION / COMMENTS 7
9/12 S
453.4 C
1 followed 4th hafuel Outage by 2 4
t I
i I
i j
1 i
Summary t
i
]'
REFUELING INFOR!!ATION DOCKET NO.
1.0-354 UNIT Hope Crack i
DATE
,10/15/92 COMPLETED BY S.
Ilo111ngsworth TELEPl!ONE (609) 339-1051.
MONTl!
Eqptember 19El 1.
Refueling information has changed from last month:
Yes No 3
2.
Scheduled date for next refueling:
9/12/92 1
3.
Scheduled dato for restart following refueling:
11/11/92 i
4.
A.
Will Technical Specification changes or other license amendments be requirod?
1 Yes No l
B.
lias the reload fuel design boon roviewed by the Station Operating Reviers Committoo?
f Yes X
No If no, when is it scheduled?
5.
Scheduled date(s) for submitting proposed 11cer. sing action:
HJA f
6.
Important licensing considerations associated with refueling:
- Same fresh fuel as current cycle:
no new considerations 7.
Number of Fuel Assemblies:
A.
Incore 764 B.
In Spont Fuel Storago (prior to refueling)-
lfR C.
In Spent Fuel Storago (after refueling) 1qqa 8.
Present licensed spent fuel storage capacity:
Aang Futuro spent fuel storage capacity:
4006 9.
Date of last refueling that can be discharged 11/4, 201Q to spent fucl pool assuming the present (EOC16) licenced capacity:
(does not' allow for full-core offload) av-.
r e
.n.e
1, i
110*'2 CREEX GENERATING STATION MONTHLY OPERATING
SUMMARY
September 1992 i
.I Ilope Creek entered the month of September at approximately 100%
l Coastdown began at 1651 on September 6 with the unit power.
operating until September 11 without experiencing any shutdowns or reportable power reductions.
On September 11 at 1700, shutdown for the Fourth Refueling Outags commenced.
At 0303 on September 12, a manual soram was initiated.
The plant had been on line for 4
89 consecutive days.
At months end the refueling outage was in j
progress.
I 4
i s
J h
i 8
I 4
1 4
i.
1 a
s j
s e-
-,%a v,-_m.
e
,.,.-.,,-_c,..m.e
--.[,,
y-..-
%.u.y~-g nr r
w-+
SUMMARY
OF CHANGES, TESTS,. AtlD EXPERIMENTS FOR Tile 110P3 CREEK GENERATING STATION SEPTEMBER 1992 i
m___-.___.m_
4 4
The following items 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 tha safety analysis report may no incrocsed; or 2.
If a possibility for an accident or ma7 function 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 10CFR50.59 Safety Evaluations showed that those items did not create a now safety hazard to the plant nor did they affect the safe shutdown of-the reactor.
These items did not change _the plant effluent releases and did not alter the existing environmental impact.
The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
.t
____m__
4 DEE Descrintion of Safety Evaluation 4EC-3185/01 This DCP installed differential pressure gauges across the profilter and afterfilter of the Instrument Air Dryers.
This installation will enable operations to observe the filter condition during routino inspections.
This DCP complies with the recommendations of INPO SOER 81-09.
The Instrument Air and the Servico Air systems have no safety related functions other than the integrity of the piping through the containment penetration.
This DCP is limited to the Instrument Air Dryer Filters and will not adversoly affect their operation; Therefore, this DCP does not involve any Unroviewed Safoty Questions.
4EC-3227/01 This DCP provided permanent rigging points to.nllow the removal and reinstallation of the High Pressure Coolant Injection Turbine Stop Valvo.
This DCP established a safo load path and does not alter any assumptions previously made in evaluating tho consequences of activities described in the UFSAR.
Thorofete, this DCP does not involvo any Unroviewed Safety Questions.
This DCP modified the Filtration, ion Panels andRecirculation, 4EC-3234/02 and Ventilation System Recirculat removed previously installed TMRs.
The work included removing the panel doors, installing a drip angle to the top of the panol, and installing spray covers with the associated supports.
This DCP does not change the function of the Filtration Recirculation, and Ventilation System Recirculatkon System.
This DCl> provides additional cooling for the components-in the-Recirculation System heater control panels.
It does not alter the operation of the system in meeting its accident mitigation function.
Therafore, this DCP-does not involve any Unreviewed safety Questions.
4EC-3266/01 Those DCPs revised the Primary containment 4EC-3266/02 Isolation System logic to provido for an indication 4EC-3266/03 of the Primary Containment Isolation System being 4EC-3266/04 armed when a tripping signal is initiated by the Nuclear Steam Supply ShLtoff System section of the Radiation Protection System.
These DCPs provided an added indication of the trip status when a Nuclear Steam Supply Shutoff System signal trips the Primary Containment Isolation System channel.
No other functional changes are associated with this DCP.
Therefore, this DCP does not involve any Unreviewed Safety Quentions.
1
i IME Descriotion of Safety Evaluation 92-021 This THR replaced a Reactor Vessol Lovel Transmitter with a= pressure transmitter that I
provides the Control Room with Reactor level i
indication when level is greater than the vessel head top nozzlo.
The transmitter outputs only to Control Room-level indication and a local alarm.
The.to is no effect on sotpoints or other instruments.
The range of i
the new instrument is greater than the previous malfunction.providing earlier indication of a instrument, i
Therefore,.this TMR does not involve any Unroviewod Safety Questions.92-022 This TMR removed a spool piece from the Drywell Equipment Drain Sump punp and from the Drywell i
Floor Drain Sump pump.
This allows an adaptor to i
be installed that will allow a temporary hose to bo connected and run to the Torus through a nearby j
Loss of Coolant Accident Doancomer.
This TMR also jumpered out open permissivos for associated "alves. -This TMR allows for normal undervensel drainago during the refueling outage.
l This TMR will only be installed during tho
{
refueling outtge and will be removed prior to j
ontering Hot Shutdown after the refueling outage.
During the time that this TMR is installed, the i
level controls, instrumentation, and alarms are functional and are not affected by this TMR.
Therefore, this TMR does not in'.rolve any Unreviewed Safety Questions.
I f
1 1
s l
1 d
j 4
4 w
u
-i,
-m-.,
..-,, - ~.
y y
+.,,g.
, n y 7,
,-y-w,-