ML20245F236
| ML20245F236 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/31/1989 |
| From: | Hagan J, Jensen H Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8906280067 | |
| Download: ML20245F236 (10) | |
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. Public Service Electric an'd Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038
' Hope Creek Generating Station i June 15, 1989 U.
S. 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
- May are being forwarded to you with the summary of changes, tests, and experiments for May 1989 pursuant to the
. requirements of 10CFR50.59(b).
Sincerely yours,
. Haga' General ager -
Hope Creek Operations
. RAM AR:bjh.
Attachment
.C Distribut' ion 8906200067 890531 PDR ADOCK 05000354 R
PNV g
The Eneroy People
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- INDEX-
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NUMBER SECTION OF PAGES Average' Daily. Unit.: Power Level.........................-
1 d
Operating Dat'a Report..................................-
2 Refueling Information....'..............................
1 1
Monthly operating' Summary...........................'...
1 Summary of. Changes, Tests, and Experimer's.............
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c AVERAGE DAILY, UNIT POWER LEVEL p,
DOCKET'NO. __50-354 UNIT' ~_liqpe ' Creek
(
DATE akL1Ala9 I
COMPLETED BY:
__H.'Jengen TELEPHONE
_LkQ9) 339-524) ~
i :-
MONTH _Mey-
'1989 DAY. AVERAGE DAILY POWER LEVEL DAY' AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) l--
1 1944 17 1939 2
1R32 18 1028 3
1Q34 19-1920 4
1041 20 10.16 5
101.5 21 1Q23 6
1p48 22 1040 7
1QAp 23 1Q25 8-1069 24 1Q33 9
LQ29 25 1032
'10 1053 26 1R27 11-1_Q46 27 ZJ2 1
12 1Q43 28
_2p9 l
13 1RJ1 29 7Q0 14 1051 30 LQJ5 I
15' 1R27 31 982 j
l 16
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'E OPERATING DATA REPORT l
DOCKET NO. '50-354 7p 1
UNIT Hope Creek DATE 6/15/89
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COMPLETED BY' H.
Jensen TELEPHONE (609) 339-5261 p
. OPERATING STATUS l '.
REPORTING PERIOD May 1, 1989 GROSS HOURS IN REPORTING-PERIOD 744 n:
1.
2.
CURRENTLY AUTHORIZED POWER LEVEL (MWt) 3293 o
l MAX. DEPEND. 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 j
MONTH DATE CUMULATIVE l
5.
NO. OF HOURS REACTOR WAS CRITICAL 744.0 3,220.9 18,168.5 j
i 6.
REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 7.
HOURS GENERATOR ON LINE 744.0 3,215.6 17,847.7 8.
UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.
GROSS THERMAL ENERGY GENERATED (MWH) 2,340,889 10,358,249 -56,361,962 10.
GROSS ELECTRICAL ENERGY GENERATED (MWH) 777,610 3,422,599 18,649,043 11.
NET ELECTRICAL ENERGY GENERATED (MWH) 745,333 3,275,181 17,825,281 12.
REACTOR SERVICE FACTOR 100.0 88.9 84.7 13.
REACTOR AVAILABILITY FACTOR 100.0 88.9 84.7 14.
UNIT SERVICE FACTOR 100.0 88.8 83.2 15.
UNIT AVAILABILITY FACTOR 100.0 88.8 83.2 16.
UNIT CAPACITY FACTOR (Using MDC) 97.2 87.7 80.6 j
17.
UNIT CAPACITY FACTOR (Using Design MWe) 93.9 84.7 77.9 18..
UNIT FORCED OUTAGE RATE O.0 0.2 6.2 19.
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATIONS:
Refueling, 9/15/89, 50 days 20.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
N/A l
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OPERATING DATA REPORT'.
O UNIT SHUTDOWNS AND POWER REDUCTIONS b
DOCKET NO'
_#_O.3 54 UNIT
_tiope Creek Unit 11 DATE
_.tl>L1_5/$9 COMPLETED BY
_.ti3 Jenpen REPORT MONTH May 1989 TELEPHONE
( 609_) 339-5261
' METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F. FORCED DURATION REASON REDUCING CORRECTIVE ACTION /
NO.
DATE S SCHEDULED (HOURS)-
(1)
POWER (2)
COMMENTS 5
6/27 S
O H
5 Load Following for Fuel Conservation
SUMMARY
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REFUELING INFORMATION l
COMPLETED BY:
Chris Brennan DOCKET NO: 50-354 UNIT NAME: Hope Creek Unit 1 DATE:
6/15/89 TELEPHONE: 3193 EXTENSION: N/A Month June 1989 1.
Refueling-information has changed from last month:
YES X
NO 2.
Scheduled date for next refueling:
09-15-89 3.
Scheduled date for restart following refueling: 11-05-89 4.
A)
Will Technical Specification 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?
8-01-89 5.
Scheduled date(s) for submitting proposed licensing action:
5-03-89 6.
Important licensing considerations associated with refueling:
NRC Generic Letter 88-16 type submittal has been made and will be used for Cycle 3 operation.
Reactor Encineerina will recuire an LCR for their control blade desian chance.
7.
Number of Fuel Assemblies:
A) Incore 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 I
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-H' OPE CREEK GENERATING STATION MONTHLY-. OPERATING
SUMMARY
'MAY 1989-Hope Creek entered the. month of May operating at 100% power.
'On-May 27 reactor power was reduced to 70% to conserve nuclear fuel.
By, conserving fuel, lthe upcoming power coastdoun would be Jdelayed.
On May 30, power was returned to 100%.
On May 31, the plant completed its 86th day of' continuous power operation.
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SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS p,
1-j..
FOR THE HOPE' CREEK-GENERATING' STATION
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MAY'1989'
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The following Temporary Modification Recuests (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 -en 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
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, i
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Safety' Evaluation Description of Temporary Modification Recuest (THR) 89-0024:
.This TMR' installed thermocouple'on the "A"
and "B"
Liquid Radwaste.
Collector sTanks.
The
- thermocouple.williallow the-tankLtemperatures' to be monitored from outside the tank rooms.
This is desirable because the tanks.are' located,inta.high radiation area.
i-E Vibration
=89-0030 This TMR bypassed one of -then two p
p Monitoring Probes for the Circulating Water Pump.
The, probe which is.being bypassed. failed and -was causing a nuisance overhead annunciator alarm-in
.l the Control Room.-
The THR will remain in place until a new probe can be installed.
'89-0031 This THR. installed thermocouple-on the "B"
Reactor Water Cleanup Pump' Seal Cooling Line 'to and from the external heat exchanger and.the l
I Reactor ' Auxiliaries -Cooling System Line which l
cools the heat exchanger.
It alao'added temporary recorders.
This modification will allow the
'l monitoring of the pump seal cavity performance i
'from outside the' pump room.
This; is desirable j
because the pump is located in a high radiation area.
89-0033 This TMR repaired a cracked solder joint in the Reactor Building Instrument Air Header.
The
. repair was accomplished by reinforcing the joint with a high-pressure clamp and by adding piping restraints to prevent further degradation.
89-0034~
This TMR installed a jumper across the Low Water-Level Switch Contacts on the Steam Seal Evaporator until a-level transmitter can be installed.
This modification prevents a
nuisance alarm in the Control Room.
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