ML20042E304

Monthly Operating Rept for Mar 1990 for Pilgrim Nuclear Power Station.W/900413 Ltr

ML20042E304
Person / Time
Site:	Pilgrim
Issue date:	03/31/1990
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-054, 90-54, NUDOCS 9004200583
Download: ML20042E304 (7)

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M sosronemson Pilgrim Nuclear Power Station Rocky Hdt Road <

Ptymouth, Massachusetts 02300 .

Nuclear operatens April 13, 1990 BECo Ltr. #90-054 U.S. Nuclear Regulatory Commission Attention: Docement Control Desk Hachington, DC 20555 License No. DPR-35 Docket No. 50-293_

Subject:

March 1990 Monthly Report

Dear Sir:

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.

l K.L. Highfil lP HJM:bal j Attachment cc: Regional Administraior, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 I

Senior Resident Inspector.

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gy/r 9004200583 900331 ADOCK0500g~3 g [

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• AVERAGE DAILY UNIT POWER LEVEL

'**- 50-293 DOCKET NO.

UNIT Pilarim 1 DATE April 13. 1990 W. Munro COMPLETED BY TELEPHONE (508) 747-8474 MONTH March 1990,_

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,

(MHe-Net) (MHe-Net)  ;

1 664 . 17 .

0 2 664 18 0 3 663 __ 19 0 .

4 664 20 0 5 664 21 0 6 664 22 0 ,

7 663 23 0 8 662 24 0 9 607 25 0 10 295 26 0 '

I 11 25 27 0 j 12 0 28 0 13 0 29 A e 14 0 30 0 i

15 0 31 0 _

l 16 0 This format lists the average daily unit power level in MWe-Net for each day '

in the reporting month, computed to the nearest whole megawatt.

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o OPERATING DATA REPORT DOCKET NO. _, 50-293 DATE __Anril 13. 1990 COMPLETED BY .N. Munro TELEPHONE . L508) 747-8474 OPERATING STATUS Notes

l. Unit Name Pilarim 1 z

2. Reporting Period March 1990

3. Licensed Thermal Power (MHt) 1998  :

4. Nameplate Rating (Gross MHe) 678

5. Design Electrical Rating (Net HHe) 655

6. Maximum Dependable Capacity (Gross MWe)___121

7. Maximum Dependable Capacity (Net MHe) 670

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

None

9. Power Level To Which Restricted, If Any (Net HHe) None

10. Reasons'ForRestrictions,IfAny N/A This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 2160.0 151728.0

12. Number Of Hours Reactor Has Critical 250 3 1666.3 87071.5

13. Reactor Reserve Shutdown Hours 0.9 0.0 0.0

14. Hours Generator On-Line 244.9 1660.9 83790.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (1:WH) 452808.0 3258864.0 14?743776.0

17. Gross Electrical Energy Generated (MWH) 155530.0 1125800 0 _11162624.0

18. Net Electrical Energy Generated (MHH) 149662.0 108375.2 46466936.0

19. Unit Service Factor 32.9 76.9 55.2 s

20. Unit Availability Factor 32.9 762 2 55.2

21. Unit Capacity Factor (Using HDC Net) _30.0 7419 45.7

22. Unit Capacity Factor (Using DER Net) 30.7 76.6 46.8

23. Unit Forced Outage Rate 0.0 0.Q 12,7

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

Maintenance Outaae March 9. 1990 for a duration of 39 days.

25. If Shut Down At End Of Repcrt Period Estimated Date of Startup - ADril 17.191Q

26. Units In Test Status (Prior to Commercial Operation): N/A Forecast Achieved INITIAL CRITICALITY __

INITIAL ELECTRICITY COMMERCIAL OPERATION .  ;

(9/77) L:

BOSTON EDISON COMPANY

, PILGRIM NUCLEAi! POWER STATION

DOCKET NO. 50-293 Operational Summarv for March 1990 The unit remained on line at approximately 100 percent thermal power until 3-9-90 when a controlled shutdown was initiated to facilitate the mid cycle maintenance outage. The reduction in power continued until 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> on 3-11-90 when the turbine generator was removed from service. All control rods were fully inserted at 1017 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.869685e-4 months <br /> on 3-11-90.

Safety Relif f Valve Challenges Month of March 1990 Requirement: NUREG-0737 T.A.P. II.K.3.3  ;

There were no safety relief valve challenges during the reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo ,

Ltr. #81-01 dated 01/05/81.

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l l

, . . REFUELING INF.ORMATION j l

The following refueling information is included in the Monthly Report as i requested in an NRC letter to BECo, dated January 18, 1978: j For your convenience, the information supplied has been enumerated so that. 4 each number corresponds to equivalent notation utilized in the request.

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

2. Scheduled date for next Refueling Shutdown: Acond Quarter 1991

3. Scheduled date for restart following refueling: l Second Quarter 1991

4. Due to their similarity, requests 4, 5, & 6 are responded to collectively )

under #6.

5. See #6. l

6. The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.

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

(b) There are 1320 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies. 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 1000 fuel assemblies.

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Month' March 1990 PILGRIM NUCLEAR POWER STATION ] ,

MAJOR SAFETY RELATED MAINTENANCE '.

SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER High M0 2301-9 Valve failed to Failure of The nisa11gned contact Torque switch sched- N/A~

Pressure HPCI Pump go fully closed switch clos- support was tightened uled for replacement Coolant Discharge Valve via Control Room ing contacts to preclude recurrence. during the mid-cycle Injection Panel C903 control to makeup due outage.

System switch while perf- to misalign-(HPCI) orming HPCI Simul- ment in the ated Automatic contact supp-Actuation Test. ort and snap (F&MR 90-16) action of the torque switch.

Feedwater Outboard Feed- Check valve failed Under Valve soft seat Refs.- to associated LER 90-004-00 System water Check scheduled Local investigation material, bushings LER.

(FH) Valve Leak Rate testing. and hinge pins have CV-261-62A (F&MR 90-62) been replaced.

Recirculation Recirc MG Set Instability in Aging of the Recirc. Speed Con',rol N/A N/A.

System "B" the speed cont- electronic modification PDC 90-14 (Recirc) rol function components of has been incorporated Motor Gen- loop. the MG set. Into 'B" Recirc.

erator Set (F&MR 90-49) MG Set. MG Set "A" (MG) is scheduled to be modified during the mid

, cycle outage.

Containment Excess Flow Operability of Personnel Check valves CK-125 A&B Refer to associated LER 90-001-00 and Reactor Check Valves check valves was error. were replaced per LER.

Systems. CK-125A and inappropriately PDC 90-32.

CK-125B. verified during performance of Surveillance Proc- '

edure 8.M.3-2 functional test.

(F&MR 90-32)

CIT SHUTDOHNS AND POWER REDUCTIONS DOCKET NO. 50-293 "

NAME P11eria 1 DATE' April 13. 1990. 1*

COMPLETED BY N Munro ,  ;

TELEPHONE (508) 747-8474 REPORT MONTH March IJJQ

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METHOD OF LICENSE CAUS'E / CORRECTIVE NO. DATE TYPEI DURATION (HOURS) REASON 2 SHUTTING DONN REACTOR 3 EVENT REPORT #

SYSTEg CODE g ENT ACTIS TO PREVENTIVE RECURRENCE 02 03/11/90 S 499.1 B 1 N/A N/A N/A Shutdown for midcycle maintenance outage.

1 2 2 3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of.

D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report-

& License Examination 9-Other: -(LER) File (NUREG-1022)

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