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{{#Wiki_filter:-
{{#Wiki_filter:-
{                                                                                       GPU Nuclear, Inc.                     !
{
(                                                                                     U.S. Route #9 South                   l NUCLEAR                                                                       Post Office Box 388 Forked River. NJ 08731-0388 Tel 609 9714000 i
GPU Nuclear, Inc.
(
U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River. NJ 08731-0388 Tel 609 9714000 i
April 14, 1997 6730-97-2110 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
April 14, 1997 6730-97-2110 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555


==Dear Sir:==
==Dear Sir:==
==SUBJECT:==
==SUBJECT:==
Oyster Creek Nuclear Generating Staticn Docket No. 50 '219 Monthly Operating Report - March,1997 In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1, enclosed are two (2) copies of the Monthly Operating Data (Gray Book information) for the Oyster Creek Nuclear Generating Station.
Oyster Creek Nuclear Generating Staticn Docket No. 50 '219 Monthly Operating Report - March,1997 In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1, enclosed are two (2) copies of the Monthly Operating Data (Gray Book information) for the Oyster Creek Nuclear Generating Station.
Ifyou should have any questions, please contact Ms. Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.
Ifyou should have any questions, please contact Ms. Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.
Very truly yours, l
Very truly yours, Michael B. Roche Vice President & Director Oyster Creek j
Michael B. Roche Vice President & Director                                   !
MB"JBDeM/gl I
Oyster Creek                                               j MB"JBDeM/gl                                                                                                             ;
i Enclosures
i Enclosures
, (f cc:
                                                                                                                        , (f   '
Administrator, Region I(2 copies) i NRC Project Manager l
I cc:     Administrator, Region I(2 copies)                                                                             i NRC Project Manager                                                                                           l NRC Resident Inspector 9704220181 970331 PDR     ADOCK 05000219                                         lilllllll'lllllIll3I R                     PDR     ;
NRC Resident Inspector 9704220181 970331 PDR ADOCK 05000219 lilllllll'lllllIll3I R
PDR


                    - _ . _  - _.    .~   . _ -      - .    --          --    .  .-      - . _ - -      . . _ - . - -
.~
MONTHLY OPERATING REPORT                                                               i
MONTHLY OPERATING REPORT
?                                       Licensee Event Reports - March,1997
?
                                                                                                                                )
Licensee Event Reports - March,1997
l 1
)
LER 97-002 was filed March 27.1997 On January 22,1997, during calibration of the Reactor Building Ventilation Exhaust Radiation monitors, the trip setpoints of the monitors, which initiate a Reactor Building Ventilation Isolation and start the Standby Gas Treatment System, were inappropriately adjusted to values higher than allowed by Technical Specificat:ons.
LER 97-002 was filed March 27.1997 On January 22,1997, during calibration of the Reactor Building Ventilation Exhaust Radiation monitors, the trip setpoints of the monitors, which initiate a Reactor Building Ventilation Isolation and start the Standby Gas Treatment System, were inappropriately adjusted to values higher than allowed by Technical Specificat:ons.
This condition was not discovered until February 28,1997.
This condition was not discovered until February 28,1997.
Line 44: Line 46:
1
1


AVERAGE DAILY PGWER LEVEL NET MWe Docket Number .:                                     50-219 Unit:                                                 Oyster Creek #1 Report Date:                                         April 3,1997 Compiled By:                                         John D. Dougher Telephone Number:-                                   (609) 971- 2130 i
AVERAGE DAILY PGWER LEVEL NET MWe Docket Number.:
Month: March,1997 DAY         MW                         DAY               MW 1
50-219 Unit:
1          640                         16               643                         1 2         641                         17               640 3         640                         18               642 4         641                         19               640 5         641                         20               641 6         639                         21               640                       ,
Oyster Creek #1 Report Date:
1 7         617                         22               641 8         608                         23               641                       ,
April 3,1997 Compiled By:
I 9          612                         24               637 10         610                         25               643                       4 11         624                         26               641 12         635                         27               638 13         636                         28               640 14         640                         29               639 15         640                         30               638 31               639 i
John D. Dougher Telephone Number:-
(609) 971-2130 i
Month: March,1997 DAY MW DAY MW 1
640 16 643 2
641 17 640 3
640 18 642 4
641 19 640 5
641 20 641 6
639 21 640 1
7 617 22 641 8
608 23 641 9
612 24 637 10 610 25 643 4
11 624 26 641 12 635 27 638 13 636 28 640 14 640 29 639 15 640 30 638 31 639 i


    .                                      OPERATING DATA REPORT
OPERATING DATA REPORT OPERATING STATUS
                    ,                            OPERATING STATUS
: 1. Docket:
: 1. Docket:                                                   50-219
50-219
: 2. Reporting Period:                                           March,1997
: 2. Reporting Period:
March,1997
: 3. Utility
: 3. Utility


==Contact:==
==Contact:==
John D. Dougher     (609) 971- 2130                 ,
John D. Dougher (609) 971-2130
: 4. Licensed Thermal Power (MWt):                               1930
: 4. Licensed Thermal Power (MWt):
: 5. Nameplate Rating (Gross MWe):                               687.5 x 0.8 = 550                                     l
1930
: 6. Design Electrical Rating (Net MWe):                         650                                                   ,
: 5. Nameplate Rating (Gross MWe):
: 7. Maximum Dependable Capacity (Gross MWe):                   641
687.5 x 0.8 = 550
: 8. Maximum Dependable Capacity (Net MWe):                     619
: 6. Design Electrical Rating (Net MWe):
  - 9. If changes occur above since last report, give reasons:   None                                                 j
650
: 10. Power Level to Waich Restricted, If Any (Net MWe):       None
: 7. Maximum Dependable Capacity (Gross MWe):
: 11. Reason for Restricte. I/ Any:                             None MONTH           YEAR         CUMULATIVE
641
: 12. Report Period Hours                                       744.0       2160.0             239064.0
: 8. Maximum Dependable Capacity (Net MWe):
: 13. Hours Rx Critical                                         744.0       2160.0               163748.8
619
: 14. Rx Reserve Shutdown Hours                                     0.0         0.0                 918.2           l
- 9. If changes occur above since last report, give reasons:
: 15. Hours Generator On-Line                                     744.0       2160.0             160077.8           l
None j
: 16. Ut Reserve Shutdown Hours                                     0.0 .       0.0                       0.0 17, Gross Thermal Energy (MWh)                             1425300       4126272             278040353
: 10. Power Level to Waich Restricted, If Any (Net MWe):
: 18. Gross Electric Eenergy (MWh)                             490301       1420239             93349506
None
: 19. Net Electric Energy (MWh)                               472938       1370412             89578978
: 11. Reason for Restricte. I/ Any:
: 20. Ut Service Factor                                           100.0       100.0                   67.0
None MONTH YEAR CUMULATIVE
: 21. Ut Available Factor                                         100.0       100.0                   67.0
: 12. Report Period Hours 744.0 2160.0 239064.0
: 22. Ut Capacity Factor (MDC Net)                               102.7       102.5                   61.1
: 13. Hours Rx Critical 744.0 2160.0 163748.8
: 23. Ut Capacity Factor (DER Net)                                 97.8         97.6                   57.6
: 14. Rx Reserve Shutdown Hours 0.0 0.0 918.2 l
: 24. Ut Forced Outage Rate                                         0.0         0.0                       9.7
: 15. Hours Generator On-Line 744.0 2160.0 160077.8
: 25. Forced Outage Hours                                           0.0         0.0               17137.4
: 16. Ut Reserve Shutdown Hours 0.0.
: 26. Shutdowns Scheduled Over Next 6 Months (Type,Date, Duration):                                 None
0.0 0.0 17, Gross Thermal Energy (MWh) 1425300 4126272 278040353
: 27. If Currently Shutdown, Estimated Startup Date:                                                   N/A j
: 18. Gross Electric Eenergy (MWh) 490301 1420239 93349506
: 19. Net Electric Energy (MWh) 472938 1370412 89578978
: 20. Ut Service Factor 100.0 100.0 67.0
: 21. Ut Available Factor 100.0 100.0 67.0
: 22. Ut Capacity Factor (MDC Net) 102.7 102.5 61.1
: 23. Ut Capacity Factor (DER Net) 97.8 97.6 57.6
: 24. Ut Forced Outage Rate 0.0 0.0 9.7
: 25. Forced Outage Hours 0.0 0.0 17137.4
: 26. Shutdowns Scheduled Over Next 6 Months (Type,Date, Duration):
None
: 27. If Currently Shutdown, Estimated Startup Date:
N/A j


1
1 Oystcr Creck Station #1 Docket No. 50-219 REFUELING INFORMATION - MARCH.1997 Name of Facility:
  ..                                                                                                                  1
Oyster Creek Station #1 1
    ,                                          Oystcr Creck Station #1 Docket No. 50-219 REFUELING INFORMATION - MARCH.1997 Name of Facility:                                                       Oyster Creek Station #1                     ;
Scheduled date for refueling shutdown:
1 Scheduled date for refueling shutdown:                                   September 1998 Scheduled date for restart following refueling:                         October 1998 Will refueling or resumption of operation thereafter require             No a Technical Specification change or other license amendment?
September 1998 Scheduled date for restart following refueling:
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier,         !
October 1998 Will refueling or resumption of operation thereafter require No a Technical Specification change or other license amendment?
unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
: 1. General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by the NRC.
: 1. General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by the NRC.
The number of fuel assemblies       (a) in the core                         =
The number of fuel assemblies (a) in the core 560
560 (b) in the spent fuel storage pool       =       2236 (c) in new fuel storage vault           =       8 The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
=
(b) in the spent fuel storage pool 2236
=
(c) in new fuel storage vault 8
=
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present Licensed Capacity: 2645 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Present Licensed Capacity: 2645 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Full core discharge capacity to the spent fuel pool was lost after the 1996 refueling outage.
Full core discharge capacity to the spent fuel pool was lost after the 1996 refueling outage.


==SUMMARY==
==SUMMARY==
 
March 1997 l
.                                                March 1997                                                 l l
i During the month of March the plant generated 472,938 Mwh net electric which was 102.7% ofits MDC rated capacity.
I
.                                                                                                              1 l
1 i               During the month of March the plant generated 472,938 Mwh net electric which was             l 102.7% ofits MDC rated capacity.
I i
I i
4 l
4 l
l 1
i i
i l
a 1
i a
l 1


2 t
2 t
UNIT SHUTDOWNS AND POWER REDUCTIONS                                                                                     '
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
DOCKET NO:             50-219 UNIT NAME:             Ovster Creek DATE:                 March 31.1997 COMPLETED BY: ' David M. Enan TELEPHONE:             609/971-4818 REPORT MONTH: March.1997 TYPE                                                   METHOD OF SHUTTING           CORRECTIVE ACTIONS / COMMENTS No.     DATE       F: Forced       DURATION           REASON                 DOWN THE REACTOR OR S: Scheduled     thours)                           (1)   REDUCING POWER (2)
50-219 UNIT NAME:
Ovster Creek DATE:
March 31.1997 COMPLETED BY: ' David M. Enan TELEPHONE:
609/971-4818 REPORT MONTH: March.1997 TYPE METHOD OF SHUTTING CORRECTIVE ACTIONS / COMMENTS No.
DATE F: Forced DURATION REASON DOWN THE REACTOR OR S: Scheduled thours)
(1)
REDUCING POWER (2)
There were no significant shutdowns or power reductions during this reporting period.
There were no significant shutdowns or power reductions during this reporting period.


==SUMMARY==
==SUMMARY==
(1) REASON                                                                                           (2) METHOD
(1) REASON (2) METHOD a.
: a. Equipment Failure (Explain)   e. Operator Training & Lic Exam                                 1. Manual
Equipment Failure (Explain) e.
: b. Maintenance orTest             f. Administratist                                               2. Manual Scram
Operator Training & Lic Exam 1.
: c. Refueling                     g. Operational Error (Explain)                                 3. Automatic Scram
Manual b.
: d. Regulatory Restnction         h. Other(Explain)                                               4. Other (Explain)
Maintenance orTest f.
                                                    - _ _ _ _ - _ _ - - _ _ _ - _          _. ..            _    ..      . . _ _ _ .        .      .  . _ . _  - _ _ _ -}}
Administratist 2.
Manual Scram c.
Refueling g.
Operational Error (Explain) 3.
Automatic Scram d.
Regulatory Restnction h.
Other(Explain) 4.
Other (Explain)
-}}

Latest revision as of 20:38, 11 December 2024

Monthly Operating Rept for Mar 1997 for Oyster Creek Nuclear Generating Station
ML20137X823
Person / Time
Site: Oyster Creek
Issue date: 03/31/1997
From: Dougher J, Roche M
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6730-97-2110, NUDOCS 9704220181
Download: ML20137X823 (7)


Text

-

{

GPU Nuclear, Inc.

(

U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River. NJ 08731-0388 Tel 609 9714000 i

April 14, 1997 6730-97-2110 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Dear Sir:

SUBJECT:

Oyster Creek Nuclear Generating Staticn Docket No. 50 '219 Monthly Operating Report - March,1997 In accordance with the Oyster Creek Nuclear Generating Station Operating License No. DPR-16, Appendix A, Section 6.9.1, enclosed are two (2) copies of the Monthly Operating Data (Gray Book information) for the Oyster Creek Nuclear Generating Station.

Ifyou should have any questions, please contact Ms. Brenda DeMerchant, Oyster Creek Regulatory Affairs Engineer, at 609-971-4642.

Very truly yours, Michael B. Roche Vice President & Director Oyster Creek j

MB"JBDeM/gl I

i Enclosures

, (f cc:

Administrator, Region I(2 copies) i NRC Project Manager l

NRC Resident Inspector 9704220181 970331 PDR ADOCK 05000219 lilllllll'lllllIll3I R

PDR

.~

MONTHLY OPERATING REPORT

?

Licensee Event Reports - March,1997

)

LER 97-002 was filed March 27.1997 On January 22,1997, during calibration of the Reactor Building Ventilation Exhaust Radiation monitors, the trip setpoints of the monitors, which initiate a Reactor Building Ventilation Isolation and start the Standby Gas Treatment System, were inappropriately adjusted to values higher than allowed by Technical Specificat:ons.

This condition was not discovered until February 28,1997.

The safety significance of this event is considered minimal because the Reactor Building Isolation and Standby Gas Treatment System initiation would still have occurred, and offsite dose rates wou'd still have been maintained well below 10CFR20 limits.

The root cause of this event is personnel error. Corrective actions include resetting the monitors to the proper setpoint, verification that other improper calibrations had not been performed, and refresher training for all Instrument and Controls tecimicians.

1

AVERAGE DAILY PGWER LEVEL NET MWe Docket Number.:

50-219 Unit:

Oyster Creek #1 Report Date:

April 3,1997 Compiled By:

John D. Dougher Telephone Number:-

(609) 971-2130 i

Month: March,1997 DAY MW DAY MW 1

640 16 643 2

641 17 640 3

640 18 642 4

641 19 640 5

641 20 641 6

639 21 640 1

7 617 22 641 8

608 23 641 9

612 24 637 10 610 25 643 4

11 624 26 641 12 635 27 638 13 636 28 640 14 640 29 639 15 640 30 638 31 639 i

OPERATING DATA REPORT OPERATING STATUS

1. Docket:

50-219

2. Reporting Period:

March,1997

3. Utility

Contact:

John D. Dougher (609) 971-2130

4. Licensed Thermal Power (MWt):

1930

5. Nameplate Rating (Gross MWe):

687.5 x 0.8 = 550

6. Design Electrical Rating (Net MWe):

650

7. Maximum Dependable Capacity (Gross MWe):

641

8. Maximum Dependable Capacity (Net MWe):

619

- 9. If changes occur above since last report, give reasons:

None j

10. Power Level to Waich Restricted, If Any (Net MWe):

None

11. Reason for Restricte. I/ Any:

None MONTH YEAR CUMULATIVE

12. Report Period Hours 744.0 2160.0 239064.0
13. Hours Rx Critical 744.0 2160.0 163748.8
14. Rx Reserve Shutdown Hours 0.0 0.0 918.2 l
15. Hours Generator On-Line 744.0 2160.0 160077.8
16. Ut Reserve Shutdown Hours 0.0.

0.0 0.0 17, Gross Thermal Energy (MWh) 1425300 4126272 278040353

18. Gross Electric Eenergy (MWh) 490301 1420239 93349506
19. Net Electric Energy (MWh) 472938 1370412 89578978
20. Ut Service Factor 100.0 100.0 67.0
21. Ut Available Factor 100.0 100.0 67.0
22. Ut Capacity Factor (MDC Net) 102.7 102.5 61.1
23. Ut Capacity Factor (DER Net) 97.8 97.6 57.6
24. Ut Forced Outage Rate 0.0 0.0 9.7
25. Forced Outage Hours 0.0 0.0 17137.4
26. Shutdowns Scheduled Over Next 6 Months (Type,Date, Duration):

None

27. If Currently Shutdown, Estimated Startup Date:

N/A j

1 Oystcr Creck Station #1 Docket No. 50-219 REFUELING INFORMATION - MARCH.1997 Name of Facility:

Oyster Creek Station #1 1

Scheduled date for refueling shutdown:

September 1998 Scheduled date for restart following refueling:

October 1998 Will refueling or resumption of operation thereafter require No a Technical Specification change or other license amendment?

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

1. General Electric Fuel Assemblies - Fuel design and performance analysis methods have been approved by the NRC.

The number of fuel assemblies (a) in the core 560

=

(b) in the spent fuel storage pool 2236

=

(c) in new fuel storage vault 8

=

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present Licensed Capacity: 2645 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Full core discharge capacity to the spent fuel pool was lost after the 1996 refueling outage.

SUMMARY

March 1997 l

i During the month of March the plant generated 472,938 Mwh net electric which was 102.7% ofits MDC rated capacity.

I i

4 l

i i

a 1

2 t

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

50-219 UNIT NAME:

Ovster Creek DATE:

March 31.1997 COMPLETED BY: ' David M. Enan TELEPHONE:

609/971-4818 REPORT MONTH: March.1997 TYPE METHOD OF SHUTTING CORRECTIVE ACTIONS / COMMENTS No.

DATE F: Forced DURATION REASON DOWN THE REACTOR OR S: Scheduled thours)

(1)

REDUCING POWER (2)

There were no significant shutdowns or power reductions during this reporting period.

SUMMARY

(1) REASON (2) METHOD a.

Equipment Failure (Explain) e.

Operator Training & Lic Exam 1.

Manual b.

Maintenance orTest f.

Administratist 2.

Manual Scram c.

Refueling g.

Operational Error (Explain) 3.

Automatic Scram d.

Regulatory Restnction h.

Other(Explain) 4.

Other (Explain)

-