ML20065S202

Monthly Operating Rept for Apr 1994 for Pilgrim Nuclear Station

ML20065S202
Person / Time
Site:	Pilgrim
Issue date:	04/30/1994
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-056, 94-56, NUDOCS 9405170192
Download: ML20065S202 (8)

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U Tech. Spec. 6.9.A.2 BOSTON EDISON P,lgum Nudear Power Station Rocky Hi;l Road Plymoum, Massachusetts 02360 E. T. Boulette, PhD Senior Vee Pres &nt - Nuclear May 13 , 1994 BEco Ltr. #94- 056 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 APRIL 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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E. T. Boulette, Ph WJM/ lam /9458 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

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, l OPERATING DATA REPORT I

• DOCKET NO. 50-293 DATE May 13, 1994 COMPLETED BY: W. Munro TELEPHONE (508) 830-8474

' OPEPATING STATUS NOTES ,

.1. Unit Name Pilgrim I

- 2. Reporting Period April 1994

3. Licensed Thennal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

' 5. . Design Electrical Rating (Net MWe) Sjil

6. Maximum Dependable Capacity (Gross MWe) ERE

7. Maximum Dependable Capacity (Net MWe) 5.7_Q

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

Jane

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

10. Reasons For Restrictions, If Any: N/A P

This Month Yr-to-Data Qtmulative

11. Hours in Reporting Period 719.0 2879.0 187511.0

12. Hours Reactor Critical 579.8 2586.0 115527.5

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 560.3 2477.2' 111266.2

15. Hour., Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated MWH) 936528.0 4605288.0 195750024.0 ,

17. Gross Electrical Energy Generated (MWH) 317640.0 1579810.0 66225744.0

18. Net Electrical Energy Generated (MWH) 305081.0 1520182.0 63653876.0

19. Unit Service Factor 77 d 86 0 59.3

20. Unit Availability Factor 77.9 86.0 59.3

21. Unit Capacity Factor (Using MDC Net) 63.3 78.8 50.7

- 22. Unit Capacity Factor (Using DER Net) 64.8 80.6 51.8 23 Unit Forced Outage Rate 22.1 6.8 11.7 -i i 24. Shutdowns scheduled over next 6 months (type, date, and duration of each) - MCO l October - 30 Days ,

25. If shutdown at end of report period, estimated date of startup - 5/1/94

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Y l AVER 1fLE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 DATE: May 13, 1994 COMPLETED BY: W. Mungo TELEPHONE: (508) 830-8474 MONTil April 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 664 17 375 2 664 18 353 3 637 19 354 4 663 20 341 5 663 21 272 6 664 22 261 ,

7 664 23 0 8 662 24 0 9 663 25 0 10 664 26 0 11 663 27 0 12 662 28 0 13 663 29 49 ,

14 662 30 126 15 661 16 662 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 SU_MMARY FOR APRIL 1994 The unit started the reporting period at 100 percent core thermal power (CTP) where it was essentially maintained until April 17, 1994 On April 17, 1994, reactor power was reduced to approximately 50 percent CTP to facilitate a thermal backwash of the main condenser, and perform control rod scram time testing. During the testing, at approximately 56 percent CTP, a number of the control rods exhibited an increased 10 percent scram insertion time. Also one control rod (10-31) failed to fully insert within 7 seconds in accordance with the acceptance criteria. This control rod was declared inoperable, fully inserted, and electrically disabled. Disassembly of the control rod's scram solenoid pilot valve, revealed one completely failed exhaust diaphragm and an embrittled and cracked pressure diaphragm. Other control rods which had exhibited slow or degraded scrar insertion times were disassembled and upon inspection revealed diaphragms in various degrees of degradation. On April 20, 1994, while the rod scram time testing continued, reactor power was reduced to approximately 43 percent CTP to facilitate troubleshooting of the Augmented Offgas (AOG) System. On April 22, 1994, following the discovery of additional diaphragms with significant degradation, the decision was made to shut the plant down so that the scram solenoid pilot diaphragms on all 145 hydraulic control units (HCU) could be replaced. At 2321 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.831405e-4 months <br /> on April 22, 1994, the main turbine was manually tripped off-line, and at 0331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br /> on April 23, 1994, a controlled shutdown of the reactor was completed. Following HCU maintenance, the reactor was made critical at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> on April 28, 1994, and the main generator was synchronized to the grid at 1046 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br /> on April 29, 1994. Power was increased to approximately 25 percent CTP where it was essentially maintained to perform post work testing of the control rods. On April 30, ,

1994, at 2051 hours0.0237 days <br />0.57 hours <br />0.00339 weeks <br />7.804055e-4 months <br /> the main generator was manually tripped offline to facilitate a weld repair on the extraction steam line entering the train "B" second point feedwater heater.

The unit remained offline for the remainder of the reporting period.

SAFETY RELIEF VALVE CHALLENGES MOiUH OF APRIL 1994 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 anytime 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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REFUEkING INFORMATJ2N 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 f acility is Pilgrim Nuclear Power Statior . 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

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 1993 refueling outage was of the same design as loaded in the previous refueling outage and consisted of 140 assemblies.

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

(b) There are 1629 fuel ansemblies 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 691 fuel assemblies.

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MONTH APRIL 1994 .

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PILGRIM NUCLEAR POWER STATION PA70R SAFETY RELATED MAINTENANCE 5

i CORRECTIVE ACTION TO ASSOCIATED SYSTEM COMPCNENT MALFUNCTION CAUSE MAINTENANCE PREVENT FICURRENCE LER Centrol Rod CRD Hydraulic Scram Solenoid Root cause Replacement of To be determined N/A

- Drive (CRD) Control Units Pilot Valve under Scram Solenoid System Malfunctions. investigation Pilot Valve Failed Diaphragms on all -

Surveillance 145 CRD Hydraulic Procedure 9.9 Control Units.

Acceptance Post Maintenance Criteria during Test satisfactory, CRD scram time CRD System placed testing. in service.

Main Steam Main Steam Incorrect Gear Root cause Replaced Motor To be determined N/A (MS) System Outboard Ratio Verified under Pinion Gear and Drain Line Per Engineering investigation Worm Shaft Valve Motor Evaluation. Clutch Gear.

Operator Performed t

MO-220-2. diagnostic Votes  !

, test. Post work l testing completed  !

satisfactorily, and valve declared operable.

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s 4 4 MONTH APRIL 1994 .;

PILGRIM NUCLEAR POWER STATION ESTOR SAFETY RELATED MAINTENANCE ,

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CORRECTIVE ACTION TO ASSOCIATED SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER 4

Reactor RBCCW Valve Valve stem Normal aging Disassembled To be determined N/A Building 30-HO-252 separated valve.

Closed from disc. Inspection

' Cooling indicated stem Water was broken in (RBCCW) half.

System Replaced stem in kind.

Replaced packing.

, Post work testing satisfactory.

Feedwater Second Steam Original Weld overlay None N/A (FW) System

• Point FW ' leak construction repair Heater "B" weld defect Train i

• Not Safety Related But Required Turbine Shutdown i

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UNIT SFUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 .'

DOCKET NO: 50-293 NAME: Pilorim I '

, DATE: May 13, 1994 COMPLETED BY: W. Munro TELEPHONE : (508 ) 830-8474 REPORT MONTH APRIL 1994 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHTIITING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO. DATE TYPE (HOURS) P'ASON DOWN REACTOR REPORT # CODE CODE RECURRENCE 1 2 3 4 5 4 4-17-94 S 0.0 B -

N/A N/A N/A Power Reduction -

Thermal Backwash Main Condenser 5 4-22-94 F 144.7 B 1 N/A N/A N/A Reactor Shutdown to Perform Maintenance on CRD Hydraulic Control Units Solenoid valves 6 4-30-94 F 14.0 B -

N/A N/A N/A Main Generator Manually Tripped Offline to Perform a Weld Repair on the Extraction Steam Line Entering the Train 'B'-

Second Point Feedwater Heater 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) h k

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