BECO-92-127, Monthly Operating Rept for Oct 1992 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Oct 1992 for Pilgrim Nuclear Power Station

ML20116K496
Person / Time
Site:	Pilgrim
Issue date:	10/31/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-92-127, NUDOCS 9211170227
Download: ML20116K496 (7)

Text

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.  :. y BOSTON EDISON Pilgr# Nuclear Pov.or station Rocky Ril Road Plymouth, Massachusetts 02360

- E. Thomas Boulette, PhD Vee President Nuclear Operanons and Stanon Duecto.

November 12, 1992 BECo Ltr. #92-127 U.S Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 sicense No. DPR-35 D_ocket No. 50-293

Subject:

October 1992 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, hflot tbJ C LY E. Thomas Boulette WJM/bal Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia,.PA 19406 Mr. R. B. Eaton Div. of Reactor Projects I/II Office of NRR - USNRC One White Flint North - Mail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector 170019 9211170227 921o31

/ l PDR ADOCK 05000293 '

R PDR l

OPERATING DATA REPORT DOCKET NO. 50-293 __

DATE. _ November 12. 1992 COMPLETED BY W. Munro TELEPHONE (508) 747-5474 _

OPERATING _ STATUS Notes

1. Unit Name Pilarim 1

2. Reporting Period October 1992

3. .nsed Thermal Power (MWt) 1998

4. nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net MWe) 655

6. Maximum Dependable Capacity (Gross MWe) 6 16 ,

7. Maximum Dependable Capacity (Net MWe) 670 __

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

None

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

10. Reasons for Restrictions, If Any N/A This Month Yr-to-Date f_quiul ative

11. Hours In Reporting Period 745.0 7320.0 174408.0

12. Number Of Hours Reactor Was Critical 562.8 6760.4 105121.0

13. Reactor Reserve Shutdown Hours 0.0 0.0 -0.0

14. Hours Generator On-Line 557.7 6703.2 10120511

15. Unit Reserve Shutdown-Hours 0.0 0.0 Q10

16. Gross Thermal Energy Genereted(MWH) 1096680.0 13115040.0 176819520.0-

-17. Gross Electrical Energy Generated (MWH) 377760.0 4520220.0 .59726634.0

18. Net Electrical Erergy Generated (MWH) 363483 _4351042.0 57401990.0

19. Unit Service Factor 74.9 91.6 58.0-

20. Unit- Availability Factor ..

74.9- 91.6 58.0

21. Unit Capacity Factor. (Using MDC Net) 72.8 88.7 -49.1

22. Unit Capacity Factor.(Using DER Net) 74.5: 90.7 '50.2-

23. Unit Forced Outage Rate 0.0 6.0 12.2

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

Refuelino 0utane #9 startina 4-3-93 for a duration of 58 days

25. If Shut Down At End Of Report Period, Estimated Date of Startup 11-22-92 r

4 e AVERAGE DAILY UNIT POWER LEVEL DOCKET N0, 50-293 UNIT Pilarim i DATE November 12, 1992 COMPLETED BY W. Munro TELEPHONE [5_08) 747!5474 MONTil October 199&

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 569 17 663 2 662 18 663 . _ _ _ _

3 661 19 663 4 661 20 661 5 661 21 662 6 662 22 662 7 663 23 609 8 663 24 60 9 661 25 0 10 662 26 0 11 664 27 0 12 664 28 0 13 661 29 ___

0 14 663 30 0 15 663 31 0 16 662 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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BOSTON EDISON C0iiPANY >

PILGRIM NUCLEAR POWER STATION-4 DOCKET NO. 50-?93 Operational Summary for October 1992 The unit started the reporting period at approximately 64 percent core-thermal power (CTP). Following maintenance on 'C' Reactor Feed Pump, the pump was started and power ascension commenced. At.approximately 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> the unit attained 100 percent CTP._ This power level was essentially maintained until October 23 when at approximately 2036 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.74698e-4 months <br /> a controlled shutdown was initiated to facilitate the planned Midcycle Maintenance and Surveillance Outage. During power reduction, a planned backwash of the m, a condenser was accomplished at approximately 50 percent (CTP). Following backwashing of the Main Condenser, power was increased temporarily to apprcximately 65 percent CTP to perform a thermal backwash. At approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on October 24 power reduction continued, and at 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br /> the turbine generator was tripped off line. All control rods were inserted at 1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br />, and the mode switch was placed in SHUTDOWN position at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />.

The unit ended the reporting period in cold shutdown condition with midcycle maintenance-activities underway. Startup from the midcycle outage is scheduled for November 22, 1992.

Weekly control rod exercises were performed on October a, 10 and 17, 1992. Minor power reductions occurred on October 9 and 10 while performing reactivity manipulations for training purposes.

Safety Relief Valve Challenges Month of October 1992 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during this 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  :

The following refunling 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 Ecorresponds to equivalent notation utilized in the reqqcst.

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

2. Scheduled date for next refueling shutdown: April 3, 1993

3. Scheduled date for restart following next refueling: May 30, 1993

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 1991 refueling outage was of the same design as'-

loaded in the previous outage and consisted of 168 assemblies.

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

(b) There are 1489 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 831 fuel assemblies.

I e -

MONTH ' October, 1992

PILGRIM NUCLEAR POWER STATION  :,

MAJOR SAFETY RELATED MAINTENANCE

. SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIAIED PREVENT RECURRENCE- -LER-Reactor Reactor' Vessel. False high Water level Correct leakage Refer to Associated LER Vessel' water level reactor vessel purturbations at fittings etc. LER. 92-013-00 (RV) control, inst- water level . (spiking) in for Instrument (To be rumentation signal causing- the 'B' refer- Rack C-2206 issued) reference: leg. automatic act- ence leg of'the (Rack B).

'B condensing' uation of the reactor vessel Measure instru-

, chamber.128. Mai Steam - water level in- ment' bypass System / Group 1 strumentation. valve leakage portien of the. on Racks C-2205 Primary Conta- and C-2206.

inment Isola- Confirm accuracy ion ControlL of resistance ,

-System (PCIS). . temperature devices PR92-9203 (RTDs) previously installed per Temp-  ;

orary Modification 91-44.

Sal t - Pump P208E SSW P208E .

.Under invest- Replaced.seven Bid specific- N/A

- Service pump failed igation.. .(7) spider ations sent surveillance . bearings, inst-

Water to'various (SSW) Test Procedure alled rebuilt vendors to 8.5.3.2.(Oper- bowl and two-(2) investigate abili ty ' Test,' intermediate vibration

-due to.. low columns which- problems and

discharge were'out of- limited pump

. fl ow. . ~ tolerance, and a. life.-

PR92-9184 new pump motor.'.

lMidcycle Maintenance outage commenced October 24, 1992:and maintenance:' activity-is being accomplished in ,

.accordance.with' outage. schedule.. >

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' UNIT SHUTDOWNS AND POWER REDUCTIONS -DOCKET NO. 50-293 -

4 RAME PILGRIM 1 . . .

DATE November 12,1 .992' E, COMPLETED.BY W. MUNRO. .

TELEPHONE 508 747-8474..

REPORT MONTH October,1992 - ---

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METHOD OF LICENSE CAUSE.& CORRECTI T DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENTi NO. DATE TYPEl (HOURS) REASON DOWN' REACTOR REPORT # CODE 4 CODE 5 RECURRENCE ~

'06 10/24/92 'S 187'.3 B 1 N/A N/A N/A Shutdown for Mid--

cycle Outage.:.

'i

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1 2 2 3 4&5-F-Forced .A-Equip Failure F-Admin 1-Manual Exhibit F & HL "

, S-Sched B-Main or Test" G-Oper Error 2-Manual Scram Instructions for C-Refueling- ..

_ H-Other 3-Auto Scram Preparations of' D-Regul atory . Restriction. 4-Continued Data Entry Sheet Ee0perator Training- 5-Reduced Load . Licensee Event Report ~

U .&; License Examination- 9-Other -(LER). File (NUREG-1022)'

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