ML19332C635

Monthly Operating Rept for Oct 1989 for Pilgrim Nuclear Power Station

ML19332C635
Person / Time
Site:	Pilgrim
Issue date:	10/31/1989
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-167, NUDOCS 8911280369
Download: ML19332C635 (7)

Text

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sammmum Pilgnm Nuclear Pwr station Rocky Hill Road Plymouth, Massachusetts 02360 I

K. L Highfill station Director November 14, 1989 BECo Ltr. #89-167 U.S. Nuclear Regulatory _ Commission 1

Attention:

Document Control Desk D

Hashington, DC 20555 License No. DPR-35

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Docket No. 50-293_

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Subject:

October 1989 Honthly 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, t

K.L. High HJH:bal Attachment cc: Regional Administrator, Region 1 U.S. Nucicar Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector 3>1 1

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OPERATING DATA REPORT DOCKET NO.

50-293 DATE November 14. 1989 1

COMPLETED 8Y H. Munro TELEPHONE

_GQB) 747-8474 OPERATING STATUS Notes 1.

Unit Name Pilorim 1 2.

Reporting Period October 1989 3.

Licensed Thermal Power (MHt) 1998 4.

Nameplate Rating (Gross MHe) 678 5._

Design Electrical Rating (Net MHe) 655 6.

Maximum Dependable Capacity (Gross MHe) 690 7.

Maximum Dependable Capacity (Net MWe) 670 l

8.

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

None 9.

Power Level To Hhich Restricted, If Any (Net MWe) 75% Core Thermal Power 10/1/89 thru 10/6/89

10. Reasons for Restrictions, If Any Regulatory Restriction. Confirmatory Action Letter 86-10.

Power Ascension Phase.

-Ihis Month Yr-to-Date Cumulative

11. Hours In Reporting Period 745,0 7296.0 148104.0

12. Number Of Hours Reactor Has Critical 297.1 4380.1 84171.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 291.9 3729.8 80959.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 461904.0 3361584.0 138361464.0

17. Gross Electrical Energy Generated (MHH) 156770.0 1060960.0 46505564.0

18. Net Electrical Energy Generated (MHH) 150471.0 1005248.0 44680677.0

19. Unit Service Factor 39.2 51.1 54.7

20. Unit Availability Factor 39.2 51.1 54.7

21. Unit Capacity Factor (Using HDC Net) 30.1 20.6 45.0

22. Unit Capacity Factor (Using DER Net) 30.8 21.0 46.1

23. Unit Forced Outage Rate 0.0 28.0 13.0

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

Maintenance Outage March 18. 1990 for a duration of 39 days.

25. If Shut Down At End Of Report Period, Estimated Date of Startup - 11/6/89

26. Units In Test Status (Frior to Commercial Operation):

N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

I" AVERAGE DAILY UNIT POWER LEVEL j.

DOCKET NO.

50-293 UNIT Pilarim 1 DATE November 14, 1989 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 MONTH October 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY. POWER LEVEL (HWe-Net)

(MHe-Net) 1 486 17 0

2 484 18 0

3 484 19 0

4-487 20 0

5 486 21 0

6 461 22 0'

7 529 23 0

8 467 24 0~

9 559 25 0

10 619 26 0

11 658 27 0

12 522 28 0

13 29 29 0

14 0

30 0

15 0

31 0

16 0

This format lists the average daily unit power level in MHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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BOSTON EDISON COMPANY PILGRIM NUCLEAR P0HER STATION DOCKET NO. 50-293 Ooorational Summarv for Ocipber 1931 l

The unit remained on line at approximately 75 percent rated thermal power in accordance with the approved Power Ascension Plan until October 11, 1989 when the power was gradually increased to 100 percent in accordance with NRC authorization previously received on October 6,1989.

The unit remained online until 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> on October 13, 1989 when a controlled shutdown was initiated and the turbine generator was manually tripped off line at 0351 i

hours, to enable performance of Temporary Procedure TP 89-71 Shutdown Cooling l

r llowing the successful performance From Outside Control Room Demonstration.

o of TP 89-71 the unit remained in the cold shutdown condition to facilitate scheduled maintenance / testing outage activities, for the remainder of the reporting period.

Safety Relief Valve Challenges Month of Getober 1989 Requirement:

NUREG-0737 T.A.P. II.K.3.3 Date:

October 13, 1989 Valve #203-3B and 30.

Reason:

SRVs opened and closed from Alternate Shutdown Panel during performance of Temporary Procedure TP 89-71 Shutdown Cooling from Outside Control Room.

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 i

l 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, each number corresponds to equivalent notation utilized in the request.

1.

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

2.

Scheduled date for next Refueling Shutdown:

Second Quarter 1991 i

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.

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 1

assemblies.

The actual usable spent fuel storage capacity is 2320 i

fuel assemblier.

(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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PILGRIM iiUCLEAR POWER STATION' MAJOR SAFETY RELATED MAINTENANCE

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SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Control CRHEAF "B" CRHEAF "B" Failure of val-Procedural error Refer to as>ociated LER 89-030-00 Room High train.

failed flowrate idation/ review corrected. CHREAF LER.

Efficiency requirements-process to det-

"A" and "B" train Air Filtra-of Proc.8.7.2.7 ect procedural dampers re-adjusted.

tion System (F&MR 89-357) error involving Surveillance Procedure (CRHEAF) incorrect flow 8.7.2.7 performed area (TP88-07) successfully.-

Residual RHR Shutdown Valve found

. Body to bonnet Furmanite injected Valve NO 1001-50 N/A Heat Cooling Suction leaking.

leak.

_into valve MO 1001-50, will be refurbished Removal Isolation Valve (F&MR 89-389) to seal leak per during RFO-8.

System M01001-50 Procedure 3.M.4-42.

(RHR)

Reactor RBCCN Heat During Insp-Metal fatigue.

Removal of existing Under investigation.

N/A Building Exchanger ection lower damaged divider plate Closed E2098.

pass divider and installation of Cooling plate found of new divider plate.

Mater cracked en both System ends.

(RBCCH)

(F&MR 89-393)

2.

- UNIT SHUTDOHNS AND POWER REDUCTIONS' DOCKET.k0.-50-293

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DATE November 14, 1989

~~ (j, Il NAME Pilarin l'-

2' COMPLETED BY N. Munro 7

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TELEPHONE (508) 747-8474^

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' REPORT M'WTH-October 1989

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"Y METHOD OF LICENSE CAUSE & CORRECTIVE

' DURATION-

-SHUTTING -

EVENT-SYSTEM ENT

ACTION TO PREVENTIVE ~

- NO.

.DATE TYPEI (HOURS) '

REASON 2'

~ :DOHN REACTOR 3

. REPORT #'

C00E4 E

PECURRENCE-14 10/13/89 S-

-453.1 B

1 N/A N/A N/A

' Controlled shutdown to-

. perform TP 89-71.

Shutdown Cooling from.

Outside Control Room-Demonstration.

Scheduled 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) 1 g

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