ML18347A798
| ML18347A798 | |
| Person / Time | |
|---|---|
| Site: | Palisades  (DPR-020) |
| Issue date: | 03/06/1978 |
| From: | Adams W Consumers Power Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18347A798 (9) | |
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consumers Power company Palisades Nuclear Plant: Route 2, Box 154, Covert, Michigan 49043 March 6, 1978 USNuclear Regulatory Commission Mail and Records Section Washington, D.C., 20555 Re:
LICENSE REPORT OF MONTHLY OPERATING DATA DPR-20, DOCKET NO. 50-255 Gentlemen:
Enclosed is a copy of the Monthly Operating Data for the Palisades
~~~~~the month of February 1978.
William E. Adams, General Engineer cc:
JGKeppler, NRG RBDeWitt DAB ix el CVWaits DEVan Farowe, Div. of Radiological Health Lansing, Mich.
AKozlowski, Mich. Dept. of Labor RCallen, Mich. Public Service Comm., Lansing, Mich.
Document Control -
(2) 950-22.35.10
DOCKET NO. 50-255 UNIT:
Palisades DATE:
3-1-78 MONTH:
February 1978
SUMMARY
OF OPERATING EXPERIENCE FOR PERIOD JANUARY 1, 1978 THROUGH FEBRUARY 28, 1978 1-1-78 1-6-78 1-6-78 1-23-78 1-30-78 2-6-78 2-14-78 2-16-78 2-21-78 2-24-78 2-27-78 The Plant was on line, operating at 90% Reactor Power and generating 702 MWe.
The Unit was taken off line and the reactor shutdown for a scheduled 84 day outage to permit refueling, performance of required surveillance, maintenance and modifications.
Completed testing of all 24 Main Steam Relief Valves.
LER 78-002 provides details of test results.
Completed repairs to Primary Coolant Pump P-50B seal.
Completed reactor internals inspection.
Completed removal of incores from reactor vessel.
Completed Eddy-Current testing of Steam Generator tubes.
Completed repairs to atmospheric* steam dump valves.
Completed removal of surveillance capsule No. A-240 from the reactor vessel.
Completed sleeving work (including Eddy Current testing of sleeved tubes) in both Steam Generators.
Completed refueling of the core.
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OPERA TING DAT A REPORT OPERA TING ST A TUS I. Unit Name:
Palisades Plant Notes
- 5. Design Electrical Rating (Net MWe): -------.,..-~8_0_5_
-le 6_ 75
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
- 635 *
, 2.. Reporting Period:
- 3. Licensed Th~rmal Power (MWt):
- 4. Nameplat_~ Rating (Gross MWe):
2-1~78 to 2-28-78 2530 811. 7 DOCKET NO.
DATE COMPLETED BY TELEPHONE 50-255 3-1-78 DIBollnow 616-764-8913
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe ):
- 10. Reasons For Restrictions, If Any:
- 11. Hours 111 Reporting Period
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve.Shutdown Hours
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours 1_6. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH) *
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net)" *
- 22. Unit Capacity Factor (Using DER Net)
This Month -
672 0
0 0
0 0
8 0
0 0
0
- 23. Unit Forced Outage Rate 0
Yr.-to-Date Cumulative 1 416 34 327 12 4. 9 __
__::2:...:.9....z.*.=...5;:;:..24..:......:...::. 3 270,336 50,292,000 81;640 15,668.250 76,464 14,689,831 8.8%
. 51.5%
8. 8 % -----51-.
5-%
8.5%
42.6%
6.7%
33~6%
0 40.4%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date. and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION.
April 1, 1978 Forecast
- Achi~~ed
- Based on Condenser Backpressure Limitations (9/77)
- r e
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-255 UNIT Palisades DATE 3-1-78 COMPLETED BY DIBollnow 616-764-8913 TELEPHONE MONTH February 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
0-
. -~
17 2*
0 0
18 3
0 0
19
- 4.
0 20 0
5 0
21 0
0 0
6 22 7
0 0
8
.23 0
24 0
0 0
9 25 IO 0
26 0
11 0
27 0
0 0
12 28 13 0
29 0
14 0
30 0
0 0
15 31 0
16 INSTRUCTIONS
-.\\ ';:
On this format, list the average daily unit power level in MWe-Net for each day in the reporting 1m>nth. Compute to
. the nearest whole megawatt.
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- I':
(9/77)
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- 1 780106
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C*1 UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH February 1978,
-OJ.
- 0.
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1291. 2 Reason:
- c
.1 A-Equipment Failure (Explain)
B-Maintenance or Test C' -Refueling D-Regulatury R.estriCtion Licensee
.. Event.
Report#
None
- E-Opcrator Training & License Examination F-Administrative G,Operational Error (Explain)*
II-Other (Explain)
- 3 Method:
I-Manual i::
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Eu 0 u 2-Manual Scram.
- 3-Automatic Scram.
4-0ther (Explain)
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE.
Cause & Correc:tivc Action to Prevent Recurrence 50-255 Palisades 3-1-78 I
DIBollnow 616-764-8913 No't: Applicable 4
s
. ~....
Exhibit G
- Instructions for Preparation of Data Entry Sheet's for Licensee Event Repl(rt (LER) File (NUREG-0161)
Exhibit 1-Same Sotm:c
- REFUELING INFORMATION REQUEST
.l.
Name of facility.
-Palisades Plant, Docket 50-255, License DPR-20.
- 2.
Scheduled date for next refueling shutdown.
- Cycle 2 - May l976 to January l978.
Outage 6-78 to approximately 4-6-78
- Cycle 3 - April l978 to ~pproximately May l979*
- Outage
~ Approximately 80 days.
- 3.
Scheduled date for restart following refueling.
- See Item 2.
- 4.
Will refueling or resumption of operation thereafter require a Technical Specificat~ons change or other license amendment?
If answer is yes, what, in general, will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (ref 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
- Cycle 3 Operation -
Technical Specifications changes were required for steam generator operating allowances.
Reload* fuel design was handled by a 10 CFR 50.59 review.
Technical Specifi-cations were not required.
Cycle 4 Operation - Technical Specifications changes will likely be required for steam generator operating allowance.
- 5.
Scheduled date(s) for submitting proposed.licensing action and supporting information.
- Steam generator related Technical Specifications changes are submitted after steam generator inspection work is completed during each inspection outage.
Reload fuel design submittals will generally occur approximately 60 days prior to an outage, if required.
1
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- 6.
Important licensing considerations associated with refueling, eg, new or different fuel design or supplier, unreviewed design or performance analysis methods,*significant changes in fuel design, new operating procedures.
- None are currently planned.
- 7.
The number of fuel assemblies (a) in the core arrd (b) in the spent fuel storage pool.
- a.
204.
- b.
798.*
- Modifications of the spent fuel storage facility are currently in progress to expana the capacity from 276 to 798 assemblies.
This project will be complete in 1978.
Amendment No 29 dated 6-30-78 licenses the spent fuel
~torage facility to 798 assemblies.
- 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.
- See Item 7.
- 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
- Approximately 1985.
2
REFUELING INFORMATION REQUEST
- 1.
Name of facility.
- Palisades Plant, Docket 50-255, License DPR-20.
- 2.
Scheduled date for next refueling shutdown.
- Cycle 2 - May 1976 to January 1978.
Outage
- l-6-78 to approximately 4-6-78
- Cycle 3 - April 1978 to approximately May 1979.
Outage
~Approximately 80 days.
- 3.
Scheduled date for restart following refueling.
- See Item 2.
- 4.
Will refueling or resumption of operation thereafter reQuire a Technical Specifications change or other license amendment?
If answer is yes, what, in general, will these be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety Questions are associated with the core reload (ref 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
- Cycle 3 Operation -
Technical Specifications changes were reQuired for steam generator operating allowances.
Reload fuel design was handled by a 10 CFR 50.59 review.
Technical Specifi-cations were not reQuired.
- Cycle 4 Operation - Technical Specifications changes will likely be reQuired for steam generator operating allowance.
- 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
- Steam generator related Technical Specifications changes are submitted after steam generator inspection work is completed during each inspection outage.
Reload fuel design submittals will generally occur approximately 60 days prior to an outage, if reQuired.
1
- 6.
Important licensing considerations associated with refueling, eg, new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
- None are currently planned.
- 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
. - a.
204.
- b.
798.*
- Modifications of the spent fuel storage facility are currently in progress to expana the capacity from 276 to 798 assemblies.
This project will be complete in 1978.
Amendment No 29 dated 6-30-78 licenses the spent fuel storage facility to 798 assemblies.
- 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 nuinber of fuel assemblies.
- See Item 7.
- 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
- Approximately 1985.
2