ML20136G779

Monthly Operating Rept for Feb 1997 for Pilgrim Nuclear Power Station

ML20136G779
Person / Time
Site:	Pilgrim
Issue date:	02/28/1997
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703180196
Download: ML20136G779 (7)

Text

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Tech. Spic. 6.9.A.2 G

Boston Edison l

Pilgrim Nuclear Power staten Rocky Hill Road i

Plymouth, Massachusetts 02360 L J. Olivier Vice President Nuclear Operations March 14, 1997 and station oirector BECo Ltr. 2.97.031 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 l

Docket No. 50.293 License No. DPR-35 i

February 1997 Monthly Report in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the l

Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. Should you have any questions conceming this report, please contact me directly.

L.J. Olivier RLC/avf/297-mrpt Attachment cc: Mr. Hubert Miller

/

Regional Administrator, Region I

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U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 L-'

Senior Resident inspector 9703180196 970228 PDR ADOCK 05000293 R

PDR 180046 BIppsppmupp

OPERATING DATA REPORT DOCKET NO.

50-293 NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH:

February 1997 OPERATING STATUS NOTES

1. Unit Name Pilgrim 1

2. Reporting Period February 1997

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

5. Design Electrical Rating (Net MWe) 655

~

6. Maximum Dependable Capacity (Gross MWe) 696

7. Maximum Dependable Capacity (Net MWe) 670

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

No Chances

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 672.0 1416.0 212352.0

12. Hours Reactor Critical 336.6 1080.6 135727.5

13. Hours Reactor Reserve Shutdown 0.0 0.0 0.0

14. Hours Generator On-Line 336.6 1080.6 131250.4

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Hours Thermal Energy Generated MWH) 599784.0 2033452.0 234509382.0

17. Gross Electrical Energy Generated (MWH) 198230.0 678770.0 79486384.0

18. Net Electrical Energy Generated (MWH) 189574.0 650589.0 76418552.0

19. Unit Service Factor 50.1 76.3 61.8

20. Unit Availability Factor 50.1 76.3 61.8

21. Unit Capacity Factor (Using MDC Net) 42.1 68.6 53.7

22. Unit Capacity Factor (Using DER Net) 43.1 70.1 54.9 l

23. Unit Forced Outage Rate 0.0 0.0 11.4

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

Currently In RFO #11 That Commenced On 2/15/97

25. If Shutdown At End Of Report Period, Estimate Date Of Start-Up 3/26/97

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-293 NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH:

February 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 584 16 0

2 582 17 0

3 580 18 0

4 576 19 0

5 575 20 0

6 574 21 0

7 570 22 0

l 8

564 23 0

9 563 24 0

10 562 25 0

11 558 26 0

12 556 27 0

l 13 553 28 0

14 500

)

15 3

1 This format lists the average daily unit power level in MWe-Net for each day in the reporting mor,5. computed to the nearest whole megawatt.

OPERATION

SUMMARY

DOCKET NO.

50-293 NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH:

February 1997 The plant entered this reporting period at approximately 93 percent core thermal power (CTP) with the reactor in and of core life coast-down.

On February 1,1997, at 0155-hours, reactor power was reduced approximately 10 percent CTP to perform control rod exercising. At 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />, control rod exercising was complete and reactor power was returned to approximately 93 percent CTP. On February 8,1997, reactor power was reduced to approximately 81 percent CTP for control rod exercising. Following completion of the control rod exercising, at 2331 hours0.027 days <br />0.648 hours <br />0.00385 weeks <br />8.869455e-4 months <br />, reactor power was retumed to the pre-exercise power of approximately

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~ 90 percent CTP. The plant continued in coast-down until February 14,1997, at 2001 hours0.0232 days <br />0.556 hours <br />0.00331 weeks <br />7.613805e-4 months <br />, when a controlled shut-down commenced in preparation for entering RFO #11. During the shut-down sequence, raactor water level control problems were encountered, and at 0038 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> on February 15,1997, the reactor

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was manually scrammed. The reactor remained shut down for the remainder of the reporting period for refueling.

SAFETY RELIEF VALVE CHALLENGES f

MONTH OF FEBRUARY 1997 Requirement:'

NUREG-0737 T.A.P. II.K.3.3 P

Data:

2/15/97 Valve:

RV-203-3B Reason:

Reactor vessel pressure control following manual scram Dato:

2/15/97 Valve:

RV-203-3C Reason:

Reactor vessel pressure control following manual scram An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo Ltr. #81-01, dated January 5,1981.

1 Y

m

REFUELING INFORMATION i

DOCKET NO.

50-293 NAME:

Pilorim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH:

February 1997 e

Tha followin0 refueling information is included in the Monthly Report as requested in NRC letter to BECo, i

dit:d January 18,1978:

i 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 refueling shutdown: Currently in RFO #11 that commenced on February 15,1997.

3. Scheduled date for restart: March 26,1997.

4. Due to similarity, requests 4,5, and 6 are respondad to collectively under #6.

1

5. See #6.

6. The new fuel loaded during the 1995 refueling outage (RFO #10) is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.

7.

(a)

There are no fuel assemblies in the core (Full core off-load for in-vessel work).

j (b)

There are 2553 fuel assemblies in the spent fuel pool. This includes 208 new fuel assemblies awaiting fuelloading for cycle 12.

1 8.

(a)

The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.

(b)

The planned spent fuel pool storage capacity is 3859 fuel assemblies.

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 895 fuel assemblies.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-293 NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH:

February 1997 i

METHOD OF LICENSE SYSTEM COMPONENT CAUSE &

TYPE DURATION REASON SHUTTING EVENT CODE CODE CORRECTIVE ACTION NO.

DATE (HOURS)

DOWN REACTOR REPORT TO PREVENT 1

2 3

4 5

RECURRENCE l

1 2/15/97 5

311.4 C

2 97-003-00 N/A N/A Refueling Outage #11 I

{

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1 D

2

[3

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]

4&5 F - Forced A - Equip Failure 1 - Manual Exhibit F & H S - Scheduled B - Main or Test 2 - Manual Scram Instructions for Preparations of

(

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C - Refueling 3 - Auto Scram Data Entry Sheet Licensee Event Report (LER)

D - Regulatory Restriction 4 - Continued (File (NUREG-1022)

E - Operator Training &

5 - Reduced Load License Examination 9 - Other j

F - Admin

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G - Operation Error Other i

u

FEBRUARY 1997 f

DOCKET NO.

50-293 NAME:

Filarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH: February 1997 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY-RELATED MAINTENANCE i

ITEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED LER TO PREVENT RECURRENCE y

i Performed Maintenance Activities in Accordance with RFO #11 Outage Schedule i

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