ML20081K401

Corrected Monthly Operating Rept for Oct 1983

ML20081K401
Person / Time
Site:	FitzPatrick
Issue date:	10/31/1983
From:	Jackie Cook POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20081K400	List: JAFP-83-1119, Forwards Corrected Monthly Operating Rept for Oct 1983 ML20081K401
References
NUDOCS 8311090415
Download: ML20081K401 (8)

Text

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OPERATING DATA REPORT DOCKET NO. 50-333 DATE Nov. 1983 COMPLETED BY T rnnk TELEPHONE (315)352-3840 s

OPERATING STATUS Fitzoatrick Notes

l. Unit Name: _

s 2. Reporting Period: 831001-831031

3. Licensed Thermal Power (MWt): 2436

4. Nameplate Rating (Gross MWe). ,883 S. Design Electrical Rating (Net MWe): 821

6. Maximum Dependable Capacity (Gross MWe): 830

7. Maximum Dependable Capacity (Net MWe): 810

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: <

None

9. Power Level To Which Restricted,1f Any (Net MWe): None

10. Reasons For Restrictions,if Any:

d This Montk Yr.-to-Date Cumulative

11. Hours In Reporting Period ,

7As 7296 72433

12. Number Of Ilours Reactor Was Critical 745 4809.1 51064.8

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 745 4720.1 49735.9

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thennal Energy Generated (MWH) 1805808 10712808 104236666

17. Gross Electrical Energy Generated (MWH) 606960 3605810 36040590

18. Net Electrical Energy Generated (MWH) 587740 3493395 34357780 r 19. Unit Service Factor 100% 64.7% 68.7%

! 20. Unit Availability Factor 100% 64.7% 68.7%

l 21. Unit Capacity Factor (Using MDC Net) - 97.4% 59.1% 62.2%

96.1%

22. Unit Capacity Factor (Using DER Net) - 58.3% 57.8%

0 6.6% 14.9%

l 23. Unit Forced Outage Rate l 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

None i

l 25. If Shut Down At End Of Report Period. Estimated Date of Startup.

I

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY i COMMERCIAL OPEr ATION B311090415 831107 l PDR ADOCK 05000333 l R PM L i

I AVERAGE DAll.Y UNIT POWER LEVEL i

DOCKET NO. . sn-113 Fitzpatrick WIT Nov. 1983 DATE COMPLETED.8Y J. Cook TELEPHONE (315)342-3840 ,

P

) MONTH d

• h" 1981

[ . DAY AYERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) .

(MWe.Neil I I 7R9 -

17 794 I 785 -

793 2 ,,

3 785 .

,, 792 4 784 795 20 5 781 - 21 795

6 786 22 792 7 781 791 23 3 786 24 790

[i 9 791 25 792 10 792 26 789

$ . .I l 794 27 790 11 12 795 g 776 o

793 i ., 13 29 776 14 789 30 790

l. 791 792 15 31 I6 793 ,

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SUMMARY

The Fitzpatrick plant operated at Near Full Thermal Power i

for this entire reporting period.

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r-P NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT NARRITIVE

SUMMARY

OF OPERATING EXPERIENCE OCTOBER, 1983 The unit operated at near full thermal power for this entire reporting period.

At the end of the reporting period, the unit is operating at approximately 792 MWe.

0

POWER AUTHORITY OF THE STATE OF NEW YORK

, JAMES Ae FITZPATRICK NUCLEAR POWER PLANT -

SAFETY RELATED ELECTRICAL a MECHANICAL MAINTENANCE

SUMMARY

K DATE SYSTEM HOW DETECTED CAUSE OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 9/28 03 22846 N/A Normal Use Rebuilt Drive 12 CRD 3737 9/23 03 16291 N/A No'rmal Use Rebuilt Drive 15 CRD 3249 -

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9/19 03 22984 N/A Normal Use Disasser ied & Inspected 24 CRD 3719 9/22 03 16277 N/A Normal Use Rebuilt Drive 20 CRD 3719 9/21 03 16279 N/A Normal Use Rebuilt Drive 30 CRD 3101 ,

9/19 03 22978 N/A Normal Use- Rebuilt Drive 12 CRD 3050 .

9/30 14 22943 OPS Normal Wear Adjusted Packing 3 MOV SA 10/6 70 21391 OPS Normal Wear Adjusted Packing 2 TCV121A 10/6 70 21392 OPS Normal Wear Adjusted P ac k ir.g 4 WAC705A

POWER AUTHORITY OF THE STATE OF NEW YORK

~

JAMES A. FITZPATRl6K NOCLEAR POWER PLANT SAFETY RELATED ELECTRICAL a MECHANICAL MAINTENANCE

SUMMARY

R DATE SYSTEM HOW DETECTED CAUSE OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE

~

10/27 03 29249 OPS Limit Switch Out of Adjusted Limit Switches 2 ADV 37 Adjustment 10/21 23 29233 S.T. Broken Valve Stem Replaced Valve _ Stem - Stoned 66 HOV 1 ,

Ridge in Cylinder 10/27 23 29246 S.I. Foreign ifaterial in Cleaned Limitorque, 51 MOV 60 Limitorque Lubricated 10/24 24 27792 OPS Burned Up Solenoid Heplaced Solenoid 4 RX Track Bay Door 10/20 70 26770 OPS Motor failure Motor Rewound by G.E. 20 AHU 3A 11/2 23 26447 Visual Defective Weld Replaced Weld ,

24 FE-80

POWER AUTHORITY OF THE STATE OF NEW YORK -

JAMES A. FITZPATRICK _ NUCLEAR POWER PLANT -  !

F MAINTENANCE

SUMMARY

f I & C OCTOBER. 1983 {

t-EST l'

E DATE SYSTEM ENT ,# HON DETECTED C ON M 10N E TIME f 4 .

RECURRENCE HOURS t.

10/1/83 07 27657 OPS Broken Wire; ' Monitor Won't Replace Broken  ;

RBM-B Bad Relays Come In Wire, Relays 60 10/7/83 02 26391 JIC Instrument Check Instru- Perform Align-FT-110G,H Drift ment Zero ment & Calibrat 14 10/8/83 03 27611 -

Select SW For i:

ROD 02-23 OPS Switch Worn Out 02-23 Inoper- Replace Switch 8 l; 4

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able .

10/11/82 07 27731 Channels on Ma- Rechecked; l TIP #2 OPS Possible Com- chine #2 Worked OK 7

, puter Problem Aborted 10/18/82 07 27602 Bad Logic Board Chart Rec er- Replaced Board  ;

TIP FLUX A OPS Relay & Wire ratic & NO Relay & Wire 42 ,

STAT CH i i

10/18/82 07 27658 Bad Board Circut Won't REPL Z-28 REM  :

RBM-A OPS #Z-28 Decrease 5% Key In Con- 32 }

nector 10/21/82 03 27625 Defective Rod Can't Select Replace Rod

~

CR SEL MAT OPS Select Switch Lower h of Select SW 10-15 18 Rods l 10/25/82 07 29234 Diodes Failed Core Top Pro- Change Two

, TIP #2 OPS Due To Age blem; CH #1 & Diodes 12 i #3 j 10/27/82 03 29248 Valve Out of Excessive Made Adjustment A0V-35 OPS Adjustment Closing Time on Valve 7 6

Datennyomwn, ,1983 JAMES A. FITZPATRICK NUCLEAR POWER PLANT POWER AUTHORITY OF THE STATE OF NEW YORK REFUELING INFORMATION

1. Tha date of the next scheduled refueling outage is Februarv ,1985 -

2. Tha scheduled date for restart following refueling is May ,1985 .

3. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

YES y If yes, describe in general what these will be and go to question S.

New Minimum Critical Power Ratio onerating limita mnv hn vnnnfrna. T F n ow enn1 enrichments are introduced, New Maximum Average Planar Linear Heat Generation Limits will be required.

- NO If no, answer question 4. .:

4. ANSWER ONLY IF ANSWER TO 3. ABOVE IS NO.

Has the reload fuel design and core configuration been reviewed by the Plant Safety Rtview committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)? <

YES NO The next scheduled review date is ,19 .

5. ANSWER ONLY IF ANSWER TO 3. ABOVE IS YES.

Tha scheduled date for submitting proposed licensing action and supporting information

.is 3,nnary ,19 85 .

-6. Answer the of'llowing important licensing considerations YES N0 m) New fuel design? x b) New fuel supplier? X c) Are there any new unreviewed design or performance analysis methods? X

=

d) Are there any new operating procedures? lf-e) Other x Specify:

7. There are normally 560 fuel assemblies in the core during operation, presently there cre" s60 in the core.

8. a) There are 816 fuel assemblies of the licensed allowable 2244 in the spent fuel pool.

b) An increase in the licensed storage capacity:

~

X is not being contemplated at this time.

is not planned at this timq for an additional fuel assemblies, has been requested for an additional fuel assemblies.

9. December ,19 90 is the last possibic refueling date that can be projected at this time given the presently licensed spent fuel pool storage capacity.

9

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