ML20043H062

Monthly Operating Rept for May 1990 for Pilgrim Nuclear Power Station.W/900614 Ltr

ML20043H062
Person / Time
Site:	Pilgrim
Issue date:	05/31/1990
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-90-075, BECO-90-75, NUDOCS 9006210517
Download: ML20043H062 (7)

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, Pdgrim Nuclear Power Staton Rocky Hill Road Plymouth. Massachusetts o2360 t

i o 5i hnEar a Vce President. Nuclear operstons s June 14, 1990 BECo Ltr. #90- 075 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293.

Subject:

May 1990 Monthly Report

Dear Sir:

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.

• p K.L. Highfil HJH:bal Attachment cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector

) 9Y 9006210517 900531 h

PDR ADOCK 05000293 il R PDC I

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AVERAGE DAILY UNIT POWER LEVEL 50-293 DOCKET NO.

'. UNIT Pilarim 1 DATE June 14. 1990 COMPLETED BY W. Munro TELEPHONE (508) 747-8474 MONTH May 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-. Net) (MHe-Net) 1 649 17 481 2 565 18 482 3 547 19 486 4 652 20 81 5 663 21 0 6 663 22 306 7 . 663 23 630 8 664 24 570 9 664 25 546 10 . 665 26 642 11 664 27 654 12 662 28 664 13 443 29 663 14- 0 30 662 15 110 31 567 16 470

'This format lists the average daily unit power level in HHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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OPERATING DATA REPORT 1 l

50-293 DOCKET NO.

DATE mmn it icon i COMPLETED BY H. Munro l TELEPHONE (508) 747-8474 OPERATING STATUS I

Notes  :

1. Unit Name Pilarim 1 l

2. Reporting Period May 1990 1

3. Licensed Thermal Power (MHt) 1998 j

4. Nameplate Rating (Gross MHe) '

678

5. Design Electrical Rating (Net MHe) 655 l

6. Maximum Dependable Capacity (Gross MHe) 696  ;

7. Maximum Dependable Capacity (Net MWe) 670 l

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

None 1

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

10. Reasons for Restrictions If Any N/A

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This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 3623.0 153191.0

12. Number Of Hours Reactor Has Critical 709.2 2540.3 87945.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 657.6 2384.0 84513.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 1178256.0 __4519512.0 145004424.0 ,

17. Gross Electrical Energy Generated (MHH) 404040.0 1556970.0 48793794.0

18. Net Electrical Energy Generated (MHH) 18111 1 Q 1497884.Q 46881068.0

19. Unit Service Factor 88.4 65.8 55.2

20. Unit Availability Factor 88.4 65.8 55.2

21. Unit Capacity factor (Using MDC Net) 77.9 61.7 45.7

22. Unit Capacity Factor (Using DER Net) 79.7 63.d 46.7

23. Unit Forced Outage Rate 11.6 3.5 12.7

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

None

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

26. Units In Test Status (Prior to Commercial Operation): N/A Forecast Achieved INITIAL CRITICALITY '

INITIAL ELECTRICITY COMMERCIAL OPERATION L

(9/77) l i

1

r BOSTON EDISON COMPANY PILERIM NUCLEAR POWER STATION

__ DOCKET NO. 50-293 Qg.trational Summary fot May 1990 The unit started the month on line at approximately 99 percent core thermal power. Following a power redJction to 78 percent on 5/2/90 to perform a rod pattern chang and a condenser backwash, power was increased to approximately 100 1ercent and was maintaineo until 5/13/90 when at 1602 hours0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br /> a disturbance en tie grid initiated a generator load reject which resulted in a full reactor scram. During the transient, increased reactor pressure caused three (3) of the safety relief valves to open momentarily and then reset. The load reject trip resulted from a faulty time delay coil in the KLF-1 loss of field relay (15 cycle delay). On 5/15/90 at 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> the reactor was made critical and at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> the generator was synchronized to the grid. Power was increased to 75 percent and was held at that level due to a turbine control system problem. On 5/20/90 a power reduction to " hot standby" was initiated to enable troubleshooting the turbine control system; and at 0808 hours0.00935 days <br />0.224 hours <br />0.00134 weeks <br />3.07444e-4 months <br /> on 5/20/90 the main generator was tripped off line to perform maintenance on the intercept valve transmitter portion of the turbine control system. On 5/22/90 the Mode Switch was placed in "Run" and the generator was synchronized to the grid at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />. Following a power increase to 96 percent, a power reduction to 50 percent was made to enable a rod pattern change and to per/orm a condenser backwash. Power was increased to 100 percent on 5/27/90.

Following a power reduction to 50 percent on 5/31/90 to perform a condenser backwash, power was then increased to 85 percent and remained there for the remainder of the reporting period, i

Safety Relief Valve Challenges Month of May 1990 . ...

Requirement: NUREG-0737 T.A.P. II.K.3.3 Date: May 13, 1990 Valve # 203-3A, 3B, and 3C Reason: Generator load reject - Reactor Scram 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 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: Second Quarter 1991

3. Scheduled date for restart following refueling: Second Quarter 1991

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 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies. ,

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

(b) There are 1320 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. Hith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.

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Month May 1990 PILGRIM NUCLEAR POWER STATION

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MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRQ!CE_ LER Electric Loss Of Field Faulty "x" coil Normal aging Loss Of Field Relay Procedure 3.M.3-39 to LER 90-006-00 Power Relay KLF-1 in KLF-1 relay. KLF-1 removed and be revised to include System (Nestinghouse) Cause of unit replaced with anoth- calibration of the trip and scran er KLF-1 relay, cont- time delay for the "x" on 5/13/90. aining an adjustable coil of the KLF-1 relay.

(F&MR 90-161) delay 'x' coll. Refer to Associated LER.

Salt Serv- SSH Pump High vibration Analysis Replaced seven (7) Inspection of columns N/A ico Hater P208B and low disch- in progress. spider bearings, and for degradation aftar (SSN) arge head. one (1) line shaft. six (6) years of service.

System (F&MR 90-21) Replaced pump motor bearings. Rebuilt pump bowl assembly.

Implemented Plant Design Change 90-12 Phase 3; Removed tie rods, replaced upper and intermediate column sections with new mater-ial design, and replaced lower column section with existing material design.

Control Rod CRD 42-07 CRD 42-07 Partially Replaced collett N/A N/A Drive (CRD) failed to blocked collette finger filters. Re-System withdraw from finger filters, placed all four (4) 00 position. and faulty Directional Flow Con-directional trol Valves FCV-120, flow control 121, 122 and 123.

valves in the Performed Procedure hydraulic 3.M.1-30 (Postwork control unit. Testing) successfully.

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UNIT-SHUTDONNS AND.PONER REDUCTIONS- DOCKET NO, 50-293 -

_ NAME' Pileria 1 ,

DATE June 14. 1990.. ,- .

COMPLET[D BY M. Munro ',"

TELEPHONE (506) 747-8474: -

REPORT MONTH May 1990 ~-

METHOD OF LICENSE CAUSE & CORRECTIVE NO. DATE TYPEI DURATION (HOURS) REASON 2 SHUTTING DONN REACTOR 3 EVENT REPORT #

SYSTEY CODE' g ENT ACTION TO PREVENTIVE RECURRENCE 03 05/13/90 F 42.5 A 3 90-008-00 EL' 92 Generator load reject ,

resulting in automatic '

reactor scram.

04 05/20/90 F 43.9 B N/A N/A N/A N/A Turbine offline for control system repairs.

l 1 2 2 3 4&S F-Forced A-Equip Failure F-Admin 1-Manual- Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Ex&mination 9-Other (LER) File (NUREG-1022) aw-- -&-wc-e_

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