ML20062N736

Monthly Operating Rept for Dec 1993 for Pilgrim Nuclear Power Station

ML20062N736
Person / Time
Site:	Pilgrim
Issue date:	12/31/1993
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-006, 94-6, NUDOCS 9401210032
Download: ML20062N736 (7)

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BOSTON EDISON Pilgrirn Nuclear Power Stauon Rocky Hill Road Plymouth, Massachusetts 02360 E. S. Kraft, Jr.

Vee PresJent Nuclear Operations eno st iion oirector January 13, 1994 BEco Ltr. #94-006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293 DECEMBER 1993 MONTHLY REPORT In accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. Should you have any questions concerning this report please contact me directly.

M. /bLo & , ,1 E. S. Kraf l Jr. #

WJM/bal/9409 Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector

• 9401210032 931231 r L,,

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.. i OPERA (ING DATA REPORT l

. :t DOCKET NO. 50-2 DATE- January 1,- 94  ;

COMPLETED BY: W. Munro a TELEPHONE (508) 830-8474 QPgP.ATING STAI[IS NOTES .

1. Unit Name Pilgrim I 12; Reporting Period December 1993 .;

Licensed Thermal Power (MWt)

-3. 1998  :

4. . Nameplate Rating (Gross MWe) 11g .

5. Design Electrical Rating (Net MWe) f51

6. Maximum Dependable Capacity (Gross MWe) 125 i

7. Maximum Dependable Capacity (Net MWe) 12H *

8. If Changen Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give .l Yeasons: i None l

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9. ' Power Level To Which Restricted, If.Any (Net-MWe): None ,

.10. Reasons For Restrictions, If Any: _1146. }

t Ihis Month Yr-to-Date Cumulative i

11. Hours In Reporting Period 744.0 8760.0 184632.'O l

12. Number of Hours Reactor Was Critical 744.0 7082.2 112941.5 13; Reactor Reserve' Shutdown Hours 0.0 0.0 0.0' i 14, Hours Generator On-Line 744.0 6802.6 108789.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 1

16. -Gross' Thermal Energy Generated (MWH) 1427184.0 13135920.0 191144736.0:  !

17. Gross Electrical Energy Generated (1901) 490790.0 4511940.0 64645934.0- .l

18. Net Electrical Energy Generated (MWH) 472417.0 4340778.0 62133694.0 l

19. Unit Service Factor '100.0 78.6 '58.9  !

20 Unit Availablility Pe.'7r 100.0 78.6 58.9  ;

21. Unit Capacity Factor '

ig MDC Net) 94.8 74.0 50.2 -i

22. Unit Capacity Factor ag DER Net) 96.9 75.7 51.4

23. Unit Forced Outage Rato 0.0 4.0 11.8 l

24. Shutdowns scheduled over next 6 months (type, date, and duration of each) - None 'l

25. If shutdown at end of report period, estimated date of startup - Unit operating I I1 r

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.j JLVERAGE DAILY UNIT R(ffCR LEVEL j r

DOCKET NO. 50-293 ~i DATE January 13, 1994 l t

COMPLETED BY: W. Myjug TELEPHONE (508) 830-8474 f l

MONTH December 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(MWe Net) (MWe-Net) P i

1 666 17 603 i 2 667 18 664' 3 665 19 614 ,

4 666 20 665 5 665 21 664 ,

6 664 22 663 7 663 23 666 8 661 24 664 '

f 9 662 25 664  !

-l 10 661 26 664  ;

11 661 27 663 ,

12 660 28 663 t

13 383 29 664 ,

14 400 30 666 >

15 624 31 664 16 466  !

This format listo the average daily unit power level in MWe Net for each day in the f reporting month, computed to the nearest whole megawatt. .j I

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f BOSTON EDISON COMPANY PILGr.IM NUCLEAR POWER STATION 4

DOCKET NO. 50-293 QPEPATIONAL

SUMMARY

FOR DECEMBER 1993

.i The unit started the reporting period at approximately 100 percent core thermal power (CTP). This power level was essentially maintained until December 13, 1993, when reactor l power was reduced to approximately 30 percent (CTP). This power reduction was  !

necessitated by macrofouling during a winter storm which adversely affected the main condenser vacuum. While at reduced power, maintenance was performed on the "A" train Third Point Feedwater Heater, to repair an external steam leak. On December 17, following the storm, 100 percent CTP was achieved. On December 19 reactor power was briefly reduced l to approximately 55 percent CTP to perform a backwash of the main condenser. Following t the backwash reactor power was increased to 100 percent CTP at approximately 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> <

where it was maintained for the remainder of the reporting period.

e SAFETY RELIEF VALVE CHALLENGES  !

I MONTH OF DECEMBER 1993 i

i Requirement: NUREG-0737 T.A.P. II.K.3.3 j There were no safety relief valve challenges during the reporting period. .

An SRV challengo is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal LNDS) or control switch (manual). Ref. BECo 2tr. #81-01 date

, 01/05/81.

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A BEFUEbWG INFORMATION The following r'efueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 18, 1978:

1 For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilised in the request  ;

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1. The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293. {

2. Scheduled date for next refueling shutdown: April 1, 1995 l

-i 3 '. Scheduled date for restart following next refueling: June 5, 1995 j

4. Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6'. i

5. See #6. .

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6. The new fuel loaded during the '993 refueling outage was of the same design as loaded in the previous refuelang outage and' consisted of 140 assemblies. [

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7. (a) There are 580 fuel assemblies in the core.  ;

(b) There are 1629 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel ascemblies. The  ;

actual usable spent fuel storage capacity is 2320 fuel assemblies.

(b) The planned spent fuel storage capacity is 2320-fuel assemblies. ,

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 691 fuel assemblies. ,

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