ML20045B371

Monthly Operating Rept for May 1993 for Pilgrim Nuclear Power Station.W/930611 Ltr

ML20045B371
Person / Time
Site:	Pilgrim
Issue date:	05/31/1993
From:	Kraft E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-074, 93-74, NUDOCS 9306170250
Download: ML20045B371 (7)

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BOSTON EDISON Pdgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 E. S. Kraft, Jr.

Vice President Nuclear Operations and station Director June 11, 1993 BECo Ltr. #93-074 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293 May 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.

N. lbt& ,

E. S. Kraf Jrg ~

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 Ort White Flint North - Mail Stop 1401 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector 160010 9306170250 930531

-PDR ADOCK 05000293 g R PDR

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OPERATING DATA REPORT J

DOCKET NO. 50-293 -l

. DATE June 11. 1993 j COMPLETED BY: W. Munro .j TELEPHONE (508) 747-8474 OPERATING STATUS '

i NOTES

1. Unit Name Pilgrim I L2. Reporting Period May 1993 .,

.3. Licensed Thermal Power (MWt) 1998  !

4.

-5.

Nameplate Rating (Gross MWe)

Design Electrical Rating (Net MWe) f2j 111

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-6. Maximum Dependable Capacity (Gross MWe) fin

7. Maximum Dependable Capacity (Net MWe) 112 l

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

Reasons:  !

None

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l9. 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 3623.0 179495.0-

12. Number of Hours' Reactor Was Critical 77.3 2220.2 108078.8:

13. Reactor Reserve Shutdown Hours 0.O' O.0 0.0

14. Hours Generator On-Line 23.1 2154.6 104061.0'

15. Unit Reserve Shutdown Hours 0.0 0.0- 0.0

16. Gross Thermal Energy Generated (MWH) 13632.0 4143144.0 182151960 0

17. Gross Electrical Energy Generated (MWH) 2350.0 1430880.0 61564874.0

18. Net Electrical Energy Generated- (}GGI) 2093.0 1376348.0 59269264.0

19. Unit Service Factor 3 . '1 59.5- 58.0'

20. Unit Availablility Factor. 3.1 '59.5 '58.0'

21. Unit Capacity Factor-(Using MDC Net)' -0.4' '56.7 49.2

.23. Unit Capacity Factor (Using DER Net)- 0.4 58.0 50'.3

23. Unit' Forced Outage Rate 16.6 4.0 '12.1

24. Shutdown' 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 June 3, 1993.

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AVERAGE DAILY UNIT POWER LEVEL  !

DOCKET NO. 50-293 UNIT Pilarim I DATE .

June 11,-1993'  ;

COMPLETED BY: W. Munro [

TELEPHONE 50B) 747-8474-  !

MONTH May 1993 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-  !

(MWe Net) (MWo-Net) i 1 0 17 0 'l i

2 0 18 0  !

L 3 0 19 0 I

4 0 20 0-

• 5 0 21 0 l 6 0 22 0 f 7 0 23 0 i

8 0 24 0 9 0 25 O  !

I 10 0 26 0 11 0 27 0 '.

12 0 28 0 .!

13 0 29 0 -

14 0 30 70. i 15 0 31 17  !

16 0  ;

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This format lists the average daily unit power level in MWe-Net for each day in the .l 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 MAY 1993  :

The unit started the reporting period with RFO-9 activities in progress. On May 19,  ;

1993, at 1328 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.05304e-4 months <br />, the Start Up Transformer (EJr) became de-energized during a j planned calibration of turbine / generator relays, lockout test and associated l annunciator verification while shutdown. The Start Up Transformer lockout relay was  ;

actuated instead of the Main Transformer lockout relay. The de-energization of the SUT resulted in designed responses including automatic actuations of the Reactor Protection System, Primary and Secondary Containment Isolation Control Systems and  !

Emergency Diesel Generators. The Start up Transformer was re-energized by 1421 hours0.0164 days <br />0.395 hours <br />0.00235 weeks <br />5.406905e-4 months <br />. RFO-9 activities continued and on 5-28-93 all requirements for placing the j Reactor Mode Switch to "Startup" were satisfied and the reactor was made critical at 1404 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.34222e-4 months <br />. On 5-29-93 with reactor pressure at approximately 140 psig, High Pressure Coolant Injection (HPCI) system and Reactor Core Isolation Cooling (RCIC)  !

system overspeed and flow rate surveillances were successfully performed. Automatic >

Depressurization System (ADS) manual opening of the four safety relief valves (#203- [

3A, 3B, 3C and 3D) was performed on 5-29-93 at 350 psig, At 0209 hours0.00242 days <br />0.0581 hours <br />3.455688e-4 weeks <br />7.95245e-5 months <br /> on 5-30-93 [

the mode switch was placed in RUN and at 0511 hours0.00591 days <br />0.142 hours <br />8.449074e-4 weeks <br />1.944355e-4 months <br /> the unit was synchronized to the i grid. On 5-30-93 the HPCI 1000 psig pump and flow surveillance was successfully )

performed. During the RCIC 1000 PSIG pump and flow surveillance, oscillations were [

noted. The RCIC system was secured and declared inoperable. At 1844 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.01642e-4 months <br /> the NRC was notified per 10CFR50.72 (b) (iii) . At 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> on 5-31-93 the generator was f' j taken off line for planned power ascension testing. Following successful turbine

, generator testing, the generator was synchronized to the grid at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> and l reactor power was being increased to approximately 25 percent. At 1754 hours0.0203 days <br />0.487 hours <br />0.0029 weeks <br />6.67397e-4 months <br /> a f backwash of the main condenser was accomplished. At 1921 hours0.0222 days <br />0.534 hours <br />0.00318 weeks <br />7.309405e-4 months <br /> when transferring l Bus A5, from the Startup Transformer to the Unit Auxiliary Transformer a, Unit j Auxiliary Transformer differential generator lockout occurred (Phase 'c'), causing a turbine trip and a full reactor scram at approximately 25 percent core thermal  :

power. The unit remained in a forced outage condition for the remainder of the  !

reporting period while investigating the cause of the Unit Scram. l SAFETi RELIbF VALVE CHALLENGES MONTH OF HAY 1993 l t

I Requirement: NUREG-0737 T.A.P. II.K.3.3 Date: May 29, 1993 Valve: #203-3A, 3B, 3C and 3D  ;

Reason: Normal Startup Testing (Ref Proc. B.5.6.2)  !

An SRV challenge is defined as anytime an SRV has received a signal to operate via

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reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo 1tr. #81-01 date 01/05/81.  ;

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,REFUELTNG INFORMATION  ;

i The foll,owing refueling information is' included in the Monthly Report as requested f in an NRC letter to BECo, dated January 18, 1978: j 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 1, 1995

3. Scheduled date for restart following next refueling: June 1, 1995

4. Due to their similarity, requests 4, 5, & 6 are responded to collectively +

under #6. l

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.

Ob) There are 1629 fuel assemblies in the spent fuel pool.

B. (a) The station is presently licensed to store 2320 spent fuel assemblies.

I 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 MAY. 1993' PILGRIM NUCLEAR POWER STATION

• MAJOR SAFETY RELATED MAIBrrENANCE , .,.

CORRECTIVE ACTION TO ASSOCIATED ~

. SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER

• Maintenance activities were accomplished in accordance with the RFO-9 outage schedule.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 DOCKET NO: 50-293 NAME: Pilorim I DATE: June 11, 1993

- COMPLETED BY: We Munro TELEPHONE: 508) 747-8474 REPORT MONTH May -1993 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT' ACTION TO PREVENT NO. DATE TYPE 1 (HOURS) REASON DOWN REACTOR REPORT # CODE 4 CODE 5 RECURRENCE 04 5/30/93 S 716.3 C 1 Continuation of.

RFO-9.

05 5/31/93 S 0.0 B 5 Pwr Red-Turb Gen

- off-line for testing 06 5/31/93 F 4.6 A 3 93-014-00 EA XFMR UAT lockout-turb.

trip-scram.

1 2 2 3 4&5 F-FORCED ' A-Equip Failure - F-Admin. 1-Manu?.1 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) .

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