ML20116P018: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:-               ..          _        ...                .
{{#Wiki_filter:-
      .                                                                                                                        1 DOCKET NO.: 50-354 UNIT: Hone Creek DATE: 8/07/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1106 OPERATING DATA REPORT OPERATING STATUS
DOCKET NO.: 50-354 UNIT: Hone Creek DATE: 8/07/96 COMPLETED BY:
: 1.     Reporting Period July 1996 Gross Hours in Report Period               744 2       Currently Authorized Power Level (MWt)                               3293 Max. Depend. Capacity (MWe-Net)                                       1031 Design Electrical Rating (MWe-Net)                                   1067
R. Harris TELEPHONE: (609) 339-1106 OPERATING DATA REPORT OPERATING STATUS 1.
: 3.     Power Level to which restricted (if any) (MWe-Net)                   Rone
Reporting Period July 1996 Gross Hours in Report Period 744 2
: 4.       Reasons for restriction (if any) l l
Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWe-Net) 1067 3.
This Month       Yr To Date         Cumulative                 .
Power Level to which restricted (if any) (MWe-Net)
: 5.      No. of hours reactor was critical                   744.0           3249.2             70173.1-6       Reactor reserve shutdown hours                       0.0               0.0               0.0                   i
Rone 4.
: 7.     Hours generator on line                             744             3091.4             69033.0
Reasons for restriction (if any)
: 8.     Unit reserve shutdown hours                         0.0               0.0               0.0
This Month Yr To Date Cumulative 5.
: 9.     Gross thermal acrgy genrated (MWH)               2417604           9680632         2204548_82
No. of hours reactor was critical 744.0 3249.2 70173.1-6 Reactor reserve shutdown hours 0.0 0.0 0.0 i
: 10. Gross electrical energy generated (MWH)           799780           3231451           73057073
7.
: 11. Net electrical energy generated (MWH)             770485         '3074084             69791319                 l
Hours generator on line 744 3091.4 69033.0 8.
: 12. Reactor service factor                             100.0             63.6               83.3
Unit reserve shutdown hours 0.0 0.0 0.0 9.
: 13. Reactor availability factor                         100.0             63.6               83.3                 I
Gross thermal acrgy genrated (MWH) 2417604 9680632 2204548_82 10.
: 14. Unit service factor                                 100.0             60.5               81.9
Gross electrical energy generated (MWH) 799780 3231451 73057073 11.
: 15. Unit availability factor                           100.0             60.5               81.9
Net electrical energy generated (MWH) 770485
: 16. Unit capacity factor (using MDC)                   100.4             58.3               80.3
'3074084 69791319 12.
: 17. Unit capacity factor (using Design MWe)             97.1             56.4               77.6
Reactor service factor 100.0 63.6 83.3 13.
: 18. . Unit forced outage rate                                 OJ               M                   19                   l
Reactor availability factor 100.0 63.6 83.3 14.
: 19.       Shutdowns scheduled over next 6 months (type, date, & duration):
Unit service factor 100.0 60.5 81.9 15.
: 20.       If shutdown at end of report period, estimated date of start-up:
Unit availability factor 100.0 60.5 81.9 16.
9608230100 960815 PDR       ADOCK 05000354 R                         PDH
Unit capacity factor (using MDC) 100.4 58.3 80.3 17.
Unit capacity factor (using Design MWe) 97.1 56.4 77.6
: 18.. Unit forced outage rate OJ M
19 19.
Shutdowns scheduled over next 6 months (type, date, & duration):
20.
If shutdown at end of report period, estimated date of start-up:
9608230100 960815 PDR ADOCK 05000354 R
PDH


DOCKET NO.: 50-354 UNIT: Hope Creek i
DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 8/07/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1106 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTII JULY 1996 METHOD OF SHUTrlNG DOWN THE
DATE: 8/07/96       l COMPLETED BY: R. Harris       I TELEPHONE: (609) 339-1106 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS                             l MONTII JULY 1996                                                         l METHOD OF SHUTrlNG DOWN THE                       )
)
TYPE                     REACTOR OR                       !
TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.
F= FORCED DURATION REASON REDUCING         CORRECTIVE NO. DATE   S= SCHEDULED   (HOURS)   (1)   POWER (2)     ACTION / COMMENTS n/a l
DATE S= SCHEDULED (HOURS)
l I
(1)
                                                                            \       i
POWER (2)
ACTION / COMMENTS n/a I
\\
i


l 1
DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 8/07/96 COMPLETED BY:
DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 8/07/96 COMPLETED BY: R. Harris TELEPHONE: (609)339-1106 AVERAGE DAILY UNIT POWER LEVEL MONTil JULY   1996 DAY   AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)                     (MWe-Net) 1               1037           17             1062 1
R. Harris TELEPHONE: (609)339-1106 AVERAGE DAILY UNIT POWER LEVEL MONTil JULY 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
2                1031           18             1008               ]
(MWe-Net) 1 1037 17 1062 2
3               1028           19             1040 4               1053           20             1056 5               1040           21             1061
1031 18 1008
* 6                1033           22             1060               1 7               1015           23             1060 8               1033           24             1055 9               1036           25             1053'-
]
10               1026           26             1056 11               1040           27             1023               l 12               1040           28             1047 13               1035           29             1036 14               1016           30             1039 15               1024           31             936 16               1025
3 1028 19 1040 4
1053 20 1056 5
1040 21 1061 6
1033 22 1060 1
7 1015 23 1060 8
1033 24 1055 9
1036 25 1053'-
10 1026 26 1056 11 1040 27 1023 12 1040 28 1047 13 1035 29 1036 14 1016 30 1039 15 1024 31 936 16 1025


1
1
)       .
)
DOCKET NO.: 50-354 UNIT: Ilone Creek i
DOCKET NO.: 50-354 UNIT: Ilone Creek i
DATE: 8/07/96       l COMPLETED BY: L. Keplev         )
DATE: 8/07/96 COMPLETED BY:
TELEPliONE: (609) 339-1106 l
L. Keplev
REFUELING INFORMATION                                             I
)
:                                                                                                      l l    MONTH JULY 1996                                                                                   1 j     1. Refueling information has changed from last month:                                           l l                          Yes                             No       X                                   I 1
TELEPliONE: (609) 339-1106 REFUELING INFORMATION l
2   Scheduled date for next refueling (RF07):                       9/6/97
MONTH JULY 1996 j
: 3. Scheduled date for restart following refueling:                   11/5/97
1.
)     4A. Will Technical Specification changes or other license amendments be required?
Refueling information has changed from last month:
Yes                             No       X B. Has the Safety Evaluation covering the COLR been reviewed by the Station Operating
l Yes No X
.          Review Committee (SORC)?
2 Scheduled date for next refueling (RF07):
l                         Yes       ,_,,
9/6/97 3.
No       X If no, when is it scheduled? To Be Determined for Cycle 8 COLR
Scheduled date for restart following refueling:
: 5. Scheduled date(s) for submitting proposed licensing action:
11/5/97
Ngtt required.
)
: 6. Important licensing considerations associated with refueling:                               l l         N/A                                                                                   1
4A. Will Technical Specification changes or other license amendments be required?
:    7. Number ofFuel Assemblies:
Yes No X
;          A. Incore                                                           764 B. In Spent Fuel S'orage                                           1472                     j
B.
: 8. Present licensed spent fuel storage capacity:                       4006 i         Future spent fuel storage capacity:                                 4006
Has the Safety Evaluation covering the COLR been reviewed by the Station Operating Review Committee (SORC)?
: 9. Date oflast refueling that can be discharged                   5/3/2006 to spent fuel pool assuming the present licensed capacity:     (EOC13)
l Yes No X
'                          (Does allow for full-core oft-load)
If no, when is it scheduled? To Be Determined for Cycle 8 COLR 5.
Scheduled date(s) for submitting proposed licensing action:
Ngt required.
t 6.
Important licensing considerations associated with refueling:
l N/A 1
7.
Number ofFuel Assemblies:
A. Incore 764 B. In Spent Fuel S'orage 1472 j
8.
Present licensed spent fuel storage capacity:
4006 i
Future spent fuel storage capacity:
4006 9.
Date oflast refueling that can be discharged 5/3/2006 to spent fuel pool assuming the present licensed capacity:
(EOC13)
(Does allow for full-core oft-load)
(Assumes 244 bundle reloads every 18 months until then)
(Assumes 244 bundle reloads every 18 months until then)
(Does nqt allow for smaller reloads due to improved fuel)
(Does nqt allow for smaller reloads due to improved fuel)


)
)
DOCKET NO.: 50-354 UNIT: Hor >e Creek DATE: 8/07/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1106 MONTHLV OPERATING  
DOCKET NO.: 50-354 UNIT: Hor >e Creek DATE: 8/07/96 COMPLETED BY:
R. Harris TELEPHONE: (609) 339-1106 MONTHLV OPERATING  


==SUMMARY==
==SUMMARY==
 
MONTil JULY 1996 The Hope Creek Generating Station remained on-line for the entire month and operated at essentially 100% power for the month of July 1996 except one load reducticn identified below.
MONTil JULY 1996
Power was reduced to 87% on July 7,1996 starting at 0301 hours to perform monthly turbine valve testing. The load reduction was extended 22 minutes due to the load dispatcher's minimum generation alert. The unit was returned to 100% power on July 7,1996 at 0640.
                            . The Hope Creek Generating Station remained on-line for the entire month and operated at essentially 100% power for the month of July 1996 except one load         .
At the end of the month the unit had been on-line for 129 days.
reducticn identified below.                                                           !
i
l
\\
                            . Power was reduced to 87% on July 7,1996 starting at 0301 hours to perform monthly     i turbine valve testing. The load reduction was extended 22 minutes due to the load dispatcher's minimum generation alert. The unit was returned to 100% power on July 7,1996 at 0640.
* At the end of the month the unit had been on-line for 129 days.                       i 1
l
                                                                                                          \


DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/07/96 COMPLETED BY: L.Kepley TELEPHONE: (609) 339-1106
DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/07/96 COMPLETED BY: L.Kepley TELEPHONE: (609) 339-1106
Line 97: Line 128:
==SUMMARY==
==SUMMARY==
OF CIIANGES, TESTS, AND EXPERIMENTS FOR THE IIOPE CREEK GENERATING STATION MONTII JULY 1996 The following items completed during June 1996 have been evaluated to determine:
OF CIIANGES, TESTS, AND EXPERIMENTS FOR THE IIOPE CREEK GENERATING STATION MONTII JULY 1996 The following items completed during June 1996 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
1.
: 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
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.
: 3. If the margin of safety as defined in the basis for any technical specification is reduced.
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 specification is reduced.
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant efiluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant efiluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
._}}
.}}

Latest revision as of 22:06, 12 December 2024

Monthly Operating Rept for Jul 1996 for Hope Creek Unit 1
ML20116P018
Person / Time
Site: Hope Creek 
Issue date: 07/31/1996
From: Harris R
Public Service Enterprise Group
To:
Shared Package
ML20116P013 List:
References
NUDOCS 9608230100
Download: ML20116P018 (6)


Text

-

DOCKET NO.: 50-354 UNIT: Hone Creek DATE: 8/07/96 COMPLETED BY:

R. Harris TELEPHONE: (609) 339-1106 OPERATING DATA REPORT OPERATING STATUS 1.

Reporting Period July 1996 Gross Hours in Report Period 744 2

Currently Authorized Power Level (MWt) 3293 Max. Depend. Capacity (MWe-Net) 1031 Design Electrical Rating (MWe-Net) 1067 3.

Power Level to which restricted (if any) (MWe-Net)

Rone 4.

Reasons for restriction (if any)

This Month Yr To Date Cumulative 5.

No. of hours reactor was critical 744.0 3249.2 70173.1-6 Reactor reserve shutdown hours 0.0 0.0 0.0 i

7.

Hours generator on line 744 3091.4 69033.0 8.

Unit reserve shutdown hours 0.0 0.0 0.0 9.

Gross thermal acrgy genrated (MWH) 2417604 9680632 2204548_82 10.

Gross electrical energy generated (MWH) 799780 3231451 73057073 11.

Net electrical energy generated (MWH) 770485

'3074084 69791319 12.

Reactor service factor 100.0 63.6 83.3 13.

Reactor availability factor 100.0 63.6 83.3 14.

Unit service factor 100.0 60.5 81.9 15.

Unit availability factor 100.0 60.5 81.9 16.

Unit capacity factor (using MDC) 100.4 58.3 80.3 17.

Unit capacity factor (using Design MWe) 97.1 56.4 77.6

18.. Unit forced outage rate OJ M

19 19.

Shutdowns scheduled over next 6 months (type, date, & duration):

20.

If shutdown at end of report period, estimated date of start-up:

9608230100 960815 PDR ADOCK 05000354 R

PDH

DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 8/07/96 COMPLETED BY: R. Harris TELEPHONE: (609) 339-1106 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTII JULY 1996 METHOD OF SHUTrlNG DOWN THE

)

TYPE REACTOR OR F= FORCED DURATION REASON REDUCING CORRECTIVE NO.

DATE S= SCHEDULED (HOURS)

(1)

POWER (2)

ACTION / COMMENTS n/a I

\\

i

DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 8/07/96 COMPLETED BY:

R. Harris TELEPHONE: (609)339-1106 AVERAGE DAILY UNIT POWER LEVEL MONTil JULY 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1037 17 1062 2

1031 18 1008

]

3 1028 19 1040 4

1053 20 1056 5

1040 21 1061 6

1033 22 1060 1

7 1015 23 1060 8

1033 24 1055 9

1036 25 1053'-

10 1026 26 1056 11 1040 27 1023 12 1040 28 1047 13 1035 29 1036 14 1016 30 1039 15 1024 31 936 16 1025

1

)

DOCKET NO.: 50-354 UNIT: Ilone Creek i

DATE: 8/07/96 COMPLETED BY:

L. Keplev

)

TELEPliONE: (609) 339-1106 REFUELING INFORMATION l

MONTH JULY 1996 j

1.

Refueling information has changed from last month:

l Yes No X

2 Scheduled date for next refueling (RF07):

9/6/97 3.

Scheduled date for restart following refueling:

11/5/97

)

4A. Will Technical Specification changes or other license amendments be required?

Yes No X

B.

Has the Safety Evaluation covering the COLR been reviewed by the Station Operating Review Committee (SORC)?

l Yes No X

If no, when is it scheduled? To Be Determined for Cycle 8 COLR 5.

Scheduled date(s) for submitting proposed licensing action:

Ngt required.

t 6.

Important licensing considerations associated with refueling:

l N/A 1

7.

Number ofFuel Assemblies:

A. Incore 764 B. In Spent Fuel S'orage 1472 j

8.

Present licensed spent fuel storage capacity:

4006 i

Future spent fuel storage capacity:

4006 9.

Date oflast refueling that can be discharged 5/3/2006 to spent fuel pool assuming the present licensed capacity:

(EOC13)

(Does allow for full-core oft-load)

(Assumes 244 bundle reloads every 18 months until then)

(Does nqt allow for smaller reloads due to improved fuel)

)

DOCKET NO.: 50-354 UNIT: Hor >e Creek DATE: 8/07/96 COMPLETED BY:

R. Harris TELEPHONE: (609) 339-1106 MONTHLV OPERATING

SUMMARY

MONTil JULY 1996 The Hope Creek Generating Station remained on-line for the entire month and operated at essentially 100% power for the month of July 1996 except one load reducticn identified below.

Power was reduced to 87% on July 7,1996 starting at 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br /> to perform monthly turbine valve testing. The load reduction was extended 22 minutes due to the load dispatcher's minimum generation alert. The unit was returned to 100% power on July 7,1996 at 0640.

At the end of the month the unit had been on-line for 129 days.

i

\\

DOCKET NO.: 50-354 UNIT: Hope Creek DATE: 08/07/96 COMPLETED BY: L.Kepley TELEPHONE: (609) 339-1106

SUMMARY

OF CIIANGES, TESTS, AND EXPERIMENTS FOR THE IIOPE CREEK GENERATING STATION MONTII JULY 1996 The following items completed during June 1996 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 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 specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant efiluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

.