BECO-LTR-93-015, Monthly Operating Rept for Jan 1993 for Pilgrim Nuclear Power Station Unit 1

Monthly Operating Rept for Jan 1993 for Pilgrim Nuclear Power Station Unit 1

ML20128K758
Person / Time
Site:	Pilgrim
Issue date:	01/31/1993
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-93-015, BECO-LTR-93-15, NUDOCS 9302180297
Download: ML20128K758 (8)

Text

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- BOSTON EDISON Pugnm Nuclear Power Station Hot hy Hdi Acad Plymouth, Menachusetts 02360 E. C. Kraf t. Jr.

Vice Presdent Nuclea+ Operatons and station omtor february 11 1993 BEco Ltr. #93- 015 U.S. Nuclear Regulatory Commission Attention- Docum nt Control Desk Washington, OC ?%55 License No. DPR-35 Docket No. 50-293 January 1993 Morathly 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.

S Nu',).

E. S. Kraf' r.

WJM/bal l

Attachment 1

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- 1/I!

Office of NRR - USNRC One White Flint North - Mail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 l Senior Resident Inspector 1

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! l l 9302100297 930131 1 PDR ADDCK 05000293 l R PDR J

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. OPERATING DATA REPORT DOCKET NO. 50-293 DATE rebruary 11, 1993 COMPLETED BY: )L Munro TELEPHONE (508) 747 8474 OPERATING STATUS NOTES

1. Unit Name ))ilgrim 1

2. Reporting Period January 1993-

3. l.icensed Thermal Power (MWt) 1918

4. Nameplate Rating (Gross MWe) SlB

5. Design Electrical Rating (Net MWe) 5.15

6. Maximum Dependable Capacity (Gross MWe) 525

7. Maximum Dependable Capacity (Net MWe) 519

8. if Changes Occur in Capacity Ratings (Item 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 Cumulative

11. Hours in Reporting Period 744.0 744.0 176616.0

12. Number of Hours Reactor Was Critical 744.0 744.0 106602.6

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 744.0 744.0 102650.4

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1479408.0 1479408.0 179488224.0

17. Gross Electrical Energy Generated (MWH) 512540.0 512540.0 60646534.0

18. Net Electrical Energy Generated (MWH) 493387.0 493387.0 58286303.0

19. Unit Service factor 100.0 100.0 58.1

20. Unit Availablility Factor 100.0 100.0 58.1

21. Unit Capacity Factor (Using MDC Net) 99.0 99.0 49.3

22. Unit Capacity Factor (Using DER Net) 101.2 101.2 50.4

23. Unit Forced Outage Rate 0.0 0.0 12.2 l 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, If Shut Down At End of Report Period, Estimated Date of Startup Unit Operatina,

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4 MfBAGE DAILY uni] POWER LEVEL DOCKET NO. SM91 UNIT Pilarim I DATE rebruary 11, 1993 COMPLETED BY: F. Hunto TELEPHONE M3) 747 8411 MONTH January 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

, (MWe Net) (MWe Net) 1 667 16 638 2 668 17 669 3 666 18 669 4 665 19 669 5 665 20 669 6 663 21 668-7 664 22 668 8 662 23 666 9 664 24 667 10 665 25 667 11 665 26 666 12 664 27 666 13 665 28 667 14 664 29 666 15 606 30 666 31 665 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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l . BOSTON EDISON COMPANY l

PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 )

OPERATIONAL

SUMMARY

FOR JANUARY 1991 ,

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The unit started the reporting period at approximately 100 percent core thermal

power (CTP), and was essentially maintained at that level until 1-15-93 when power

was reduced to approximately 67 percent CTP to perform a main condenser backwash, i On 1-16 93 the unit attained 100 percent CTP where it was maintained for the ,

, remainder of the reporting period. Minor power reductiens were made on 1-2, 1-7, 1-l 14, 1-16 and 1-23-93 to perform control rod exercises, i

k SAFETY RELIEF VALVE CHALLENGES Month of January 1991.

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{ Requirement: NUREG 0737 T.A.P. II.K,3.3 l

i There were no safety relief valve challenges during the reporting period.

4 An SRV challenge is defined as anytime an SRV has received a signal to operator via 3 reactor pressure, auto signal (ADS) or control switch (manual). Ref. BEco ltr. #81-q 01 d:te 01/05/81, a

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I LEfuELING_INL0fLMAll0N 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: April 3, 1993 1

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

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.

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.I PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MRINTENRNCE CORRECTIVE ACTION TO ASSOCIATED ' '

MAINTENANCE PREVENT RECURRENCE LER SYSTEM- COMPONENT MALFUNCTION CAUSE Cell #4 found Crack in Replaced Continue to perform N/A Diesel Emergency Diesel monthly surveillance Generators Generator 'A' with low outer batt- battery ery casing on battery. <

and Air Compressor level.

due to aging.

Auxil- Battery (PR 93.9002) iaries Root cause Replaced blown Refer to associated LER 93-001-00 High HPCI Flow No indication (to be issued)

Indicating of flow while under invest- fuse and perf- LER.

Pressure ormed surveil-Coolant Controller performing igation.

Injection FIC 2340-1 HPCI oper- lance satis-ability sur- factorily (HPCI)

System veillance due to blown power supply fuse in-side FIC 2340-1 (PR 93.9021) l High vibra- Pump Balanced pump Investigating new N/A Salt SSW Pump degradation motor coupling pump design (Spec.

Service P-208G tion observed while perfor-- MS-B). LTP #617 SSW Water Water Pump Upgrade ming SSW Pump (SSW) Frogram.

System and Valve Surveillance Procedure 8.5.3.2.

Overhauled To be determined N/A Motor Operator Failed to ep- Root Cause Salt under invest- motor operator Service M0-3801, TBCCW erate via the and HBC gear Heat Exchanger control igation Water. unit. Replaced "A" Service switch on (SSW)

Panel Cl in spring pack and System Water Outlet motor pinion.

Valve. the Control Room.

Replaced both bearings in the HBC worm gear.

Installed new SMS and HBC gasket kits.

pg8111 January. 1993 h s -'

PILGRIM fiUCLEAR POWER STATI0li MAJOR SAFETY RELATED MAltiTEtt931CE ,

t CORRECTIVE ACTIO!i TO ASSOCIATED !

SYSTEM- COMP 0tiEtiT MALFUt1CTI0ti CAUSE MAltiTEtiANCE LER, PREVENT RECURREtiCE i Reactor RBCCW Loop "B" Failed to op- Rcot Cause Adjustment of To be t

Building Inlet Valve 'erate from thA under spring tension on determined i Closed ,

Motor Operator the control investigation limit switches 4 & 8.

i' Cooling M0-40108. switch, and Following adjustment i Water position ind- the valve was operated (RBCCW) ication was satisfactorily. L System erratic.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCCtET NO: 50-293 , ,

DOCKET NO: 50-293 .

NAME: Pilgrim I* 1 DATE: February 11. 1993

COMPLETED BY: W. Munro .

TELEPHONE: 508) 747-8474 REF'iT MONTH January 1993 I METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENT

NO. DATE TYPE 1 (HOURS) REASON DOWN REACTOR REPORT # CODE 4 CODES RECURRENCE I

There were no unit shutdowns or reportable power reductions during the reporting period.

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P 1- 2 2 3 4&S 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)