ML20064G755

Monthly Operating Rept for Feb 1994 for Pilgrim Nuclear Power Station

ML20064G755
Person / Time
Site:	Pilgrim
Issue date:	02/28/1994
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-029, 94-29, NUDOCS 9403160341
Download: ML20064G755 (8)

Text

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H i BOSTON EDISON Pagrim Nuclear Power Staton l Rocky Hill Road i Plymouth, Massachusetts o2360 l l

1 E. S. Kraft, Jr.

. Wce President Nuclear Operanons and Staton Dwector March 15, 1994 BECo Ltr. #94- 029 ,

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 FEBRUARY 1994 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.

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b WJM/dmc/9417 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 l

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AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO. 50-293-DATE March 15, 1994 COMPLETED BY: W. Munrg_,

TELEPHONE (508) 830-8474 MONTH February 1994 r

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe- Ne t) r 1 666 17 565.

2 665 18 479 3 666 19 485 4 665 20 485 5 666 21 485 J

6 665 22 482 7 665 23 54 i 8 665 24 0 9 666 25 0 10 665 26 0 11 585 27 .0 ,

12 665 28 0 13 665 :l 14 664 15 664 ,

I 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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,. BOSTON EDISON COMPANY PILGRIM NUCLEAR. POWER STATION DOCKET NO. 50-293 '

DIEFArlD1!M_EUNRiRY FOR F.EB_PEARY 19.94 The unit started the reporting period at 100 percent core thermal power (CTP). On February 11, 1994, 'a brief power reduction to approximately 47 percent C"TP was made . to.

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facilitate a backwash of the main condenser to de-ice the intake bay. -Following the ,

backwash reactor power was increased to 100 percent CTP where it was maintained until .

February 17, 1994, On February 17,- 1994, at approximately 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />, while performing the Main Steam Isolation Valve (MSIV) Quarterly Test, the AO-203-1D inboard isolation valve failed the closure time requirement, rendering the valve inoperable and requiring '

the valve to be closed. The outboard MSIV AO-203 2D was also closed. Reactor power was reduced to approximately 75 percent CTP at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> and was maintained at that level until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on February 22, 1994, when a controlled manual shutdown of the unit was commenced for a planned maintenance outage. On February 23, 1994, at 0553 hours0.0064 days <br />0.154 hours <br />9.143518e-4 weeks <br />2.104165e-4 months <br /> the main turbine generator was manually tripped off line. At 1254 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.77147e-4 months <br /> the Reactor Mode Switch was placed in the SIRTrDOWN position, and by 2003 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.621415e-4 months <br /> the unit was in cold shutdown  ;

condition. The unit remained in cold shutdarwn for the remainder of the reporting period  :!

to facilitate the MSIV outage maintenance activities. 1 4

-n SAFETY RELIEF VALVE C11ALLENGES HQE11LQF FEBRUARY 1994 e

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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 anytima an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo ltr. #81-01 date 01/05/81.  !

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i REFUEk!,Hg_JRQEMATJO_N T1e foll,owing' refueling information is included in the Monthly Report as requested in an

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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: April 1, 1995

3. Scheduled date for restart following next refueling: May 26, 1995 s

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

5. See #G.

6. The new fuel loaded during the 1993 refueling outage was of the same design as  ;

loaded in the previoun refueling 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 assemblies. The actual usable spent fuel storage capacity is 2320 fuel assemblies.

(b) The planned spent fuel storage capacity in 2320 fuel assemblies. j

. 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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OPERATING DATA REPORT

-. i DOCKET NO. 50-293 -i DATE rch 15 - IM7 ' 4 COMPLETED BY: W. Munro TELEPHONE (508) 830-8474 I QP.3BliTllLQ S.TA111S NOTES

.1 . Unit Name Pilgrim I

2. Reporting Period February 1994

'3 Licensed Thermal Power (MWt) 1998 *

4. Nameplate Rating (Gross MWe) 571

5. . Design Electrical Rating (Net MWe) fji5.

'6. Maximum Dependable Capacity (Gross MWe) fjiui

7. Maximum Dependable Capacity (Net MWe) 670 ,

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If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report,'Give Reacons: ,

None ,

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9. Power Level To Which Restricted, If Any (Net MWe) . Noua

10. Reasons For Restrictions, If Any: N/A 73Lis Month Yr-to-Date Cumulative-

11. Hours In Reporting Period 672.0 . _ 1416.0 186048.0 >

12. Number of Hours Reactor Was Critical 590.4 1334.4 114275.9 ,

=13. Reactor Reserve Shutdown Hours Od 0.0 0.0

, 14. Hours Generator On-Line 533.9 _ 1277.9' 110066.9- '

. 15. Unit Reserve Shutdown Hours 0.0 0.0- 0 . 0 .-

16. Gross Thennal Energy Generated (MWH) 986064.0 '2464560.0 193609296.0

17. Grons Electrical Energy Generated (MWH) 339050.0 850530.0 ,_f.54 9 64 64 . 0

18. Net Electrical Energy Generated (MWH) 326292.0 818973.0 62952667.0

19. Unit Service Factor 79.4 90.2- 59.2-20 Unit Availability Factor 79.4 90-R

. 59.2'

21. Unit Capacity Factor (Using MDC Not) 72.5 86.3 50.5'

- 22. Unit Capacity Factor (Using DER Net) 74.1 88.3~ 51.7 'J

23. Unit Forced Outage Rate 0.0 0.0 11'7.

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

25. If shutdown at end of report period, estimated date of startup - Ma*ch 4, 1994 i

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+ 4 UNIT SHUTDOWNS.AND PCWER REDUCTIONS DOCKET ~NO: 50-293 ,

DOCKET NO: 50-293 NAME: Pilorim I $

DATE: March 15, 1994 '

COMPLETED BY:- W. Munro TELEPHONE: (509) 830-8474 .

REPORT MONTH FEBRUARY.- 1994

ETHOD OF LICENSE CAUSE & CORRECTIVE-DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO. DATE TYPE (HOURS) REASON DOWN REACTOR REPORT # CODE CODE RECURRENCE 1 2 3 4 5

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1 2-23-94 S 138.1 B 1 N/A N/A N/A Main Steam Isolacion Valve

' Maintenance Outage, 4

4 1 2 2 3 4&5

.F-FORCED -A-Equip' Failure. F-Admin 1-Manual Exhibit F&H '

=. S-SCHED B-Main or Test G-Oper Error 2-Manual Scram. Instructions for:

C-Refueling H-Other 3-Auto Scram Preparations 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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