BECO-LTR-92-098, Monthly Operating Rept for Jul 1992 for Pilgrim Nuclear Power

Monthly Operating Rept for Jul 1992 for Pilgrim Nuclear Power

ML20099H477
Person / Time
Site:	Pilgrim
Issue date:	07/31/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-92-098, BECO-LTR-92-98, NUDOCS 9208190053
Download: ML20099H477 (7)

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BOSTON EDISON Pilgrvn Nuclear Power Statrin Rouy Hill Road Plymouth, Massachusetts o2300 E. Thomas Doulette, PhD Vke Presdent Nuclear Operanons and Staten Duettor August 12, 1992 BEco Ltr. #92-098 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555 License No. DPR 35 Docket No. 50-29J_

Subject:

July 1992 Monthly Report in accordance with PNPS Technichi 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 ouest:nns concerning this report please contact me directly.

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E. Thomas Boulette WJM/bal Attachment cc:

Mr. Thomas-T. Martin Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Mr. R. B. Eaton Div of RLactor Projects I/II Office of NRR - USNRC One White flint North - Mail Stop 1401 11555 Rockville Pike Rockville, MD 20852 Senior Resident inspector 920e290053 920731

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4 AVERAGE DAILY UtilT POWER __LLyll DOCKET l10,50-29L Uf41T Pilarim 1 DATE August 12, ii[9'2

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COMPLETED BY W. Munro TELEPH0f1E (5081 747;li474 M0fl1H July 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-liet)

(MWe-flet) 1 60) 17 659 2

663 18 641 3

662 19 520 4

663 20 662 5

QE3 21 662 6

365 22 660 7

664 23 660 g

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1. _63 24 669 9

663 25 660 10 664 26 623 11-662 27 581

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12 661 _

28 652 13 661 29 660 14 662 30 660 15 661 31 660 16 658 This f ormat lists the average daily unit power level in MWe-liet for each day in the reporting month, computed to the nearest whole megawatt.

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OPERATil4G DATA REPORT DOCKET 110.

50-293 DATE August 12, 1992 COMPLETED BY W. Munro TELEPHONE (508) 747-5474 _

OPERATING _SIAlMS Notes 1.

Unit Name Pilarip_J 2.

Reporting Period July 1992 3.

Licensed Thermal Power (MWt) 1998 4.

Nameplate Rating (Gross MWe) 61B 5.

Design Electrical Rating (Net MWe) 655 6.

Maximum Dependable Capacity (Gross MWe).

6_2s 7.

Maximum Dependable Capacity (Net MWe) 670 8.

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

None

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9.

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

None 10.

Reasons For Restrictions, if Any N/A This Month Yr-to-Date [umulative

11. Hours in Reporting Period 744.0 5111.0 172199.0

12. Number Of Hours Reactor Was Critical 744.0 4733.6 103094 2

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-line 744,0 4681.5 99184 1 2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 14666FJ Q 9173952.0 112878432.0

17. Gross Electrical Energy Generated (MWH) 504600.0 3166L1Q1Q _ 58372544,0

18. Not Electrical Energy Generated (MWH) 485551 Q 3047979.0 56098927.Q

19. Unit Service factor 100.0 91 6 57.6 1

20. Unit Availability Factor 100.0

91. 6. __

57.5

21. Unit Capacity Factor (Using MDC Net) 97 a 89.0 48.6 s

22. Unit Capacity Factor (Using DER Net) 99.6 91.0 49.7

23. Unit Forced Outage Rate 00 8.4 12.4 2

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

Midcycle outaae - Octobpr 1992 Acoroximately 35 days 25.

If Shut Down At End Of Report Period, Estimated Date of Startup N/A

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i BLfELit!UMORIMllDI!

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 3.

Scheduled date for restart following next refueling:

June 8, 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 assemb' lies.

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.

4 (b)

The planned spent fuel storage capacity is 2320 fuel asser.;blies.

9.

With present spent fuel :n storage, the spent fuel pool now has the capacity to accommodate an additional 831 fuel assemblies.

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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-L9's Operational Summary for July 1992 The unit started the reporting period at approximately 100 percent core thermal power (CTP). On July 18, at approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, reactor power was reduced to facilitate a thermal backwash of the main condenser, and pe' form selective maintenance.

Following the backwash, reactor power was raised to 100 percent CTP where it was maintained until July 26 when at 2123 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.078015e-4 months <br /> power was reduced to 40 percent CTP when the "A" Recirculation Pump Motor Generator Set drive motor breaker tripped causing a trip of the "A" Recirculation Pump.

On July 27 at approximately 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> reactor power was returned to 100 percent C1P where it was essentially maintained for the remainder of the reporting period. Weekly control rod exercises were performed on July 4, 11, 19, and 25.

Safety Relief Valve Challenges Month of July 1992 Requirement:

NUREG-0737 1.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 (manuai).

Ref. BLCo lir. #81-01 dated 01/05/81.

MONTH July, 1992 PILSRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED iMINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE COP.

V 10 4 TO AS IATED Salt Motor Operated During perform-

. Lack of lub-Lubricated spline inspect valves N/A Service Valve ance of Surv-rication on and spline adapt-(MO-3806. M0-3805 MO-38G6, M0-3808) and Water M0-3813 eillance Proce-the spline or.

(.SSW) dure 8.5.3.1 and spline lubricate as required.

System "SSW MOV Oper-adaptor.

ability" M0-3813 failed to indicate full closure.

(PR 92.9118)

Salt "D"

SSW High less than Added weights NED preparing new N/A Service Pump P-208D vibration; optimum on the motor improved design for nater pump in design.

coupling to SSW pumps. CJSA 32-013 (SSW)

" Required compensate for in review process.

System Action Range" motor imbalance.

(PR92.9118)

Diesel A" Emergency Check valve Corrosior.

Disassembled Established PM program N/A Generators Diesel Gener-failed in open buildup in Check Valve, for all Emergency Diesel and ator starting position.

check valve.

cleaned internals Generator air system check Auxilia-air Check replaced valve valves.

PDC 91-08 seat. Reassembled Diesel Generator Air ries Valve 47-CK-101C.

valve and re-Start Piping to be installed. Per-implemented during MCO-92.

formed Post Work Test 8.9.1.2 successfully.

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UNIT SHUTDOWNS AND POWER REDUCTIONS TCKET NO._

50-293 NAME PILGRIM 1 DATE August u, ej:t2 COMPLETED BY W. MUNRO TELEPHONE S_05~747-8474 REPORT MONTH JULY 1992 METHOD OF LICENSE CAUSE & CORRtCTIVE DURATION SHUTTING EVENT SiSTEM COMPONENT ACTION TO PREVENT NO.

DATE TYPE 1 (HOURS)

REASON DOWN REACTOR REPORT #

CODE 4 CODES RECURRENCE There were no unit shutdowns or significant power reductions

. during the reporting period required to be reported.

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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 4-Continued Data Entry Sheet D-Regulatory Restriction 5-Reduced Load Licensee Event Report E-Operator Training 9-Other (LER) File (NUREG-1022)

& t_icense Examination G

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