ML20006E676

Monthly Operating Rept for Jan 1990 for Pilgrim Nuclear Power Station.W/900214 Ltr

ML20006E676
Person / Time
Site:	Pilgrim
Issue date:	01/31/1990
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-023, 90-23, NUDOCS 9002260205
Download: ML20006E676 (7)

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[. , Pilgrim Nuclear Power Station

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Ralph G. Bird i Senior Vice President - Nuclear --

S!' February 14 , 1990  !

BECo Ltr. #90- 023

• r U.S. Nuclear Regulatory Commission Attention: ' Document. Control Desk

Hashington, DC 20555 License No. DPR-35 ,

, Docket No. 50-293_

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Subject:

January 1990 Monthly Report

DearLSir:

h LIn: accordance with PNPS Technical Specification 6.9.A.2, a copy of the Operational Status Summary.for-Pilgrim Nuclear Power-Station is attached for o' -your information and planning. Should you have any questions concerning this report:please.' contact me directly. .i

$h K.U..Highfill

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l cc: Regional Administrator, Region 1

' U.S. Nuclear Regulatory Comission

, ~475 Allendale Rd.

King of Prussia, PA 19406

" lSeniorResidentInspector .

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, TAVERAGE DAILY UNIT POWER LEVEL.

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. c DOCKET NO. 5.0-293

-. -* UNIT Pilarim 1 DATE: February 14,-1990, COMPLETED BY H. Munro TELEPHONE- (508) 747-8474 1 -MONTH January 1990-: ,

DAY AVERAGE DAILY POWER LEVEL' DAY- AVERAGE DAILY POWER LEVEL

,s. '(MHe-Net)~ (MHe-Net) 1 660 17 666 2 666- 18 666 I 3' 663 19 ~668~  ;

4 668 20 668

'5 663 21 666 6 669 22 667

7. 667 23 667 8 666- 24 666 9 668-- 25 665

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. 668 26 666-11- 668 27 666 12 666 28 665 13 666 29 664 14 666- 30 665 15 663 31 665

-16 665 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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OPERATING DATA REPORT DOCKET NO. 50-293 DATE February 14, 1990 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 LOPERATING STATUS Notes

1. Unit Name- Pilarim 1

2. Reporting Period January 1990

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3. . Licensed Thermal Power (MHt) 1998

4. Nameplate-Rating (Gross MWe) 678

5. Design Electrical-Rating (Net MWe) 655 ,

- 6. Maximum Dependable Capacity (Gross MHe) 690 .

7. Maximum Dependable Capacity (Net MWe) 670

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

1 None

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

10. Reasons For Restrictions, If Any N/A 1

This Month Yr-to-Date Cumulative

71. Hours In. Reporting Period 744.0 744.0 150312 0 l '12. Number Of Hours Reactor Has Critical 744.0 744.0 86149.2 l 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 744.0 82873.3

15. Unit Reserve-Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 1484664.0 1484664.0 141969576.0

17. Gross Electrical Energy Generated (MHH) -514600.0 514600.0 47751424.0

18. Net Electrical Energy Generated (MHH) 495449.0 495449.0 45878633.0.

19. Unit Service Factor 100.0 100.0 55.1

20. Unit Availability Factor 100.0 100.0 55.1

21. Unit Capacity Factor (Using MDC Net) 99.4 99.4 45.6

22. Unit Capacity Factor (Using DER Net) -101.7 101.7 46.6 l 23. Unit Forced Outage Rate 0.0 0.0 12.8 *

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 Report Period, Estimated Date of Startup - N/A .

26. Units In Test Status (Prior to Commercial Operation): N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

, " BOSTON EDISON 1 COMPANY-

. . . . PILGRIM NUCLEAR P0HER STATION' 1 ; ' "* DOCKET NO. 50-293 vil:.;

Ooerational' Summary for January 1990- e 1 The unit remained on line at.approximately 100 percent thermal power  :

_throughout the reporting period.

-The "A":Feedwater regulator valve and the "A" Recirculation Motor Generator.

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Set remained in manual control throughout the reporting period.

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Safety Relief Valve Challenges' Month of January 1990 i

L -i J- Requirement: NUREG-0737 T.A.P. II.K.3.3 f 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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REFUELING INFORMATION 1

The following refueling information is included in the Monthly Report as requested:in an NRC letter to.BECo, dated January 18, 1978:

For your convenience, the information supplied has been. enumerated so that, 4

each number corresponds.to equivalent notation utilized lin the ' request.

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

2. Schedu1Ed date for next Refueling Shutdown: Second Quarter 1991

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

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

5. See #6.

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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. 1(a) The station'is presently licensed to store 2320 spent fuel assemblies. The actual usable spent fuel-storage capacity is 2320 fuel assemblies.

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

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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- .M nth January 1990 Y --

-PILGPIM' NUCLEAR PONER STATION-- -

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' MAJOR: SAFETYRELATEbMAINTENANCEl

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.q SYSTEM LCOMPONENT~ MALFUNCTION , ' CAUSE MAINTENANCE- CORRECTIVE ACTION ~T01 -ASSOCIATEDi i PREVENT RECURRENCE LER ~- -

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Salt Service SSH Pump During transportL 0riginal. ~

' Disassembled column, Replace existing pump' Voluntary LER Hater (SSH) P-208A pump 208A was' - casting prob . performed extensive columns-(Pumps-A,B,C D: (To be issued)J <

System dropped, result- lems,"and de-;non-destructive .. and E).with new columns ~

ing'in a'360 . . aluminization examinations ~ of each of improved design..

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' degree circumfer- - of the alumi . column ~ section.. >(Refer to BECo Ltr.90-017 ential fracture- ' num bronz . Replaced top, bottom,' dtd'1/19/90).

of the pumpfshaft alloy..'Also' and two' intermediate-casing. a through- sections. . Performed l (F&MR 90-08) wall crack - hydro." Re-assembled existed from pump column in vertical-a: prior weld position. Implementing repair. PDC 90-12, Tie rod -

modification,'to improve stress margins.

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~ y J UNIT.SHUTDONNS!AND POWER REDUCTIONS

i DOCKET NO.'50-293:' '

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NAME ' - P11 erie 1  :

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DATE Fabruery 14, 1990" -2J

- COMPLETED BY N. Munro .

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TELEPHONE- ~(508) 747-8474 2 REPORT MONTH- January 1990-

.. METHOD OF LICENSE CAUSE'& CORRECTIVE NO. DATE TYPEI ' '(HOURS)

DURATION REASON'

, SHUTTING

- DONN REACTOR .3

. EVENT REPORT #-

SYSTEg'.

. CODE g ENT- ACTION TO PREVENTIVE-RECURRENCE ~-  ;-

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There were no unit shutdowns or sianificant onwer reductions durino the reportino Deriod.

w 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 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 1(LER) F11e-(NUREG-1022)-

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