ML20044C029

Monthly Operating Rept for Feb 1993 for Pilgrim Nuclear Power Station.W/930312 Ltr

ML20044C029
Person / Time
Site:	Pilgrim
Issue date:	02/28/1993
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-93-033, BECO-LTR-93-33, NUDOCS 9303160327
Download: ML20044C029 (8)

Text

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BOSTON EDISON Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 E. S. Kraf t, Jr.

Vice President Nuclear Operations and Statson Director March 12, 1993 BECo Ltr. #93- 033 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293 February 1993 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.

d[ Noo E. S. Krit .

WJM/bal Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road 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 1401 11555 Rockville Pike-Rockville, MD 20852 Senior Resident Inspector 9303160327 930228 .

PDR- ADOCK 05000293

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• ' OPERATING DATA REPORT

' DOCKET NO. 50-'293 .

DATE March.12, 1993 - =!

COMPLETED BY: W. Munro i TELEPHONE (508) 747-8474' 'j-

- OPERATING STATUS l

-NOTES  :-

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l'. Unit-Name Pilgrim I .;

2. . Reporting Period February 1993 I

. 3 ~. Licensed Thermal Power (MWt) 1998 -[

4. Nameplate Rating (Gross MWe) f,23. {

5. Design Electrical. Rating (Net MWe) 15ji l l6. Maximum Dependable Capacity (Gross MWe) 121 l

7. _ Maximum Dependable Capacity (Net MWe) 570 ,

- 8. If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last' Report, Give.. .l

-Reasons: f None .j

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

10. Reasons For Restrictions, If Any: N/A I This Month Yr-to-Date QgnQative ,

11. . Hours In Reporting Period 672.0 1416.0 177280.0: 3

12. Number of Hours Reactor Was Critical 672.0 3416.0 107274.6) .;

13. Reactor Reserve Shutdown Hours 0.0 0.0 -0.0'

- 14. Hours Generator On-Line 672.0 1416.0 103322.4-

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 '

16. Gross Thermal Energy Generated (MWH) 1308648.0 2788056.0.'180796872.0  !

' 17. Gross Electrical Energy Generated (MWH) 452670.0 965210.0 61099204.0 [

18. Net' Electrical Energy Generated (MWH) 435555.0 928942".0 58721858.0 j

19. Unit Service Factor 100.0 100.0 '58.3

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20. Unit Availablility Factor 100.0 100.0 58.3

-'21.

22.

Unit Capacity Factor (Using MDC Net)

Unit Capacity Factor (Using DER Net) 96.7 99-0 97.9

'100.2 49.4:

50.6

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23. Unit Forced Outage Rate  !

0.0 0.0 12.2

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

Refueling Outage #9 starting 4-3-93 for a duration of 58 days. .!

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25. If Shut Down At End of Report Period,. Estimated Dete of Startup Unit Operatina.

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-i AVERAGE DAILY UNIT POWER LEVEL '

. F DOCKET NO. 50-292  ;

UNIT Pilctrim I '  ;;

DATE March.12, 1993 i COMPLETED BY: W. Munro '

TELEPHONE 508) '747-8474 l i

MONTH February 1993 '

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER. LEVEL t (MWe Net) (MWe-Net) 3 1 665 14 667 f

2 459 15 640- f l

3 614 16 666 ]

i 4 664 17 666  !

5 666 18 667 6 666 19 665 e

7 665 20 634 i 8 665 21 498 9 666 22 665 10 667 23 667 ,

11 668 24 667 '

12 665 25 667 E 13 667 26 667 ,

27- 667 28 649 I 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 OPERATIONAL

SUMMARY

FOR FEBRUARY 1993 The unit' started the reporting period at approximately.100 percent core thermal power (CTP). On .2-2-93 reactor power was reduced to approximately 50 percent- CTP to

- perform a main condenser backwash in response to increased macrofouling caused by an ocean storm. Following the successful backwash, power was increased and at apprcximately 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on 2-3-93 the unit attained.100 percent CTP. On 2-15-93 power was reduced briefly to perform selective maintenance. Following maintenance, power was increased ard at approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> the unit ' attained 100 percent CTP where it was maintained until 2-20-93 when' power was reduced to perform a main condenser backwash. Following the backwash, power was increased.to 100 percent CTP and was essentially maintained for the remainder of the reporting period. Minor power reductions were made on 2-22-93 and 2-28-93 to perform control rod pattern adjustments.

SAFETY RELIEF VALVE CIULLLENCES Month of February 1993 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenget-during the reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operator via reactor pressure, auto signal (ADS) or control switch (manual). F.ef. BECo ltr. #81--

01 date 01/05/81, i

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F REFUELING INFORMATIOR .

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 l number corresponds to equivalent notation utilized in the request, j

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

293.

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

3. Scheduled date for restart following next refueling: May 31, 1993 {

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

5. See #6. .

6. The new fuel loaded during the 1991 refueling outage was of the same design as f loaded in the previous outage and consisted of.168 assemblies. l

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

(b) There are 1489 fuel assemblies in the spent fuel pool. i

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. l

9. With present spent fuel in storage, the spent fuel pool now has the capacity  !

to accommodate an additional 831 fuel assemblies.

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MJdTH - February. 1993 PILGRIM NUCLEAR POWER STATION '

MAJOR SAFETY RELATED MAINTENANCE-CORRECTIVE ACTION TO- ASSOCIATED

. SYSTEM -.. COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER' .

~ Salt:' Discharge Check valve Corroded seat Disassembled. Upgraded-valve using , N/A-i Service' check valve - leaking by its- . ring _and disc. and inspected Monel internals.

. Water 29-CK-3880B. seat. . valve. -Replaced -p 1

.(SSW) disc, seat ring, System hinge pins bolting, grease fittings and gaskets.

Reassembled and successfully-tested.

i Salt Pump P-208B Failed to pass ' Excess clear- Pump overhauled: Investigating new N/A-

. Service' surveillance - ance'in disassembled and- pump design (Spec Water: ' Procedure column flange. inspected. M.8-B) LTP #617

.(SSW) 8.5.3.2 due to Line shafts Installed SSW pump upgrade System- high vibration pitted and- rebuilt saction program.

and low dis- worn from bowl; seven new charge head packing and spider-bearings; bearing con- 'two line shafts; tact. one head shaft; one column; pack-E 'ing and new gas-kets. Tested successfully.

Motor: overhauled:

disassembled and cleaned, replaced upper and lower bearingsJ .Re-assembled, meg .

gered and re-

~ 1nst alled.

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MONTH February; 1993' -

-PILGRIM NUCLEAR POWER STATION ~

MAJOR SAFETY RELATED MAINTENANCE -

CORRECTIVE ACTION TO ASSOCIATED ~

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' SYSTEM. COMPONENT MALFUNCTION ~ CAUSE MAINTENANCE PREVENT RECURRENCE LER Reactor RCIC turbine Valve failed Galled stem Machined stem New designed stem 93-002'-00:

Core Steam Inlet to stroke full due to mini- and bonnet to and backseat to (to be issued)

- -Isola- Valve open during mal stem and increase be installed.

tion" MO-1301-61 performance of backseat clearances;

' Cooling ~ surveillance clearance. overhauled and (RCIC) Procedure -inspected the

System 8.5.5.1 and motor operator tripped. and replaced the motor.

Following repairs the valve was stroked success-fully.

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

NAME: -Pilorim I DATE: March 12,-1993 COMPLETED BY: W. Munro TELEPHONE: 508) 747-8474 REPORT MOICH February 1993.

METHOD OF LICENSE CAUSE & CORRECTIVE DUPATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVEITF WO. DATE TYPE 1 (HOURS) REASON DOWN REACTOR REPORT # CODE 4 CODE 5 RECURRENCE 01 2/2/93 F 0.0 H 5 N/A Power reduction to perform main conden-ser backwash.

02 2/21/93 F 0.0 H 5 N/A ~ Power reduction to perform main conden-ser backwashi 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 Reduced Load Licensee-Event Report

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