ML20138K581

Monthly Operating Rept for Jan 1997 for Pilgrim Nuclear Power Station

ML20138K581
Person / Time
Site:	Pilgrim
Issue date:	01/31/1997
From:	Cannon R, Olivier L BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-017, 97-17, NUDOCS 9702190048
Download: ML20138K581 (7)

Text

--

.... =

6 Tech. Sp c. 6.9.A.2 i

e Boston Ediswr Pilgrim Nuclear Power Staten Rocky Hill Road Plymouth, Massachusetts 02360 i

L J. Olivier Vice President Nuclear Operatens February 13, 1997 and staten oirector BECo Ltr. #97-017 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 j

License No. DPR-35 JANUARY 1997 MONTHLY REPORT in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the f

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/dmc/9458 Attachment I

cc: Mr. Hubert Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector 1

I 9702190048 970131

?

PDR ADOCK 05000293 R

pg m

i 7-I OPERATING DATA REPORT DOCKET NO.

50-293 e

NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 REPORT MONTH ' - January 1997

{

OPERATING STATUS.

NOTES 1.

~ Urit Name '

Pilgrim 1 2.

Reporting Period January 1997 3.

' Licensed Thermal Power (MWt) 1998 4.

' Nameplate Rating (Gross MWe)

DZR 5.

- Design Electrical Rating (Net MWe).

655 6.

Maximum Dependable Canacity (Gross MWe) 696 7.

Maximum Dependable Capacity (Net MWe)-

929 8.

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

1 No Chances 9.-

Power Level To Which Restricted, if Any (Net MWe): None 10.-

Reasons For Restrictions, if Any: N/A 1

This Month Yr-to-Date Cumulative 11.

. Hours in Reporting Period 744.0 744.0 211680.0 12.

Hours Reactor Critical 744.0 744.0 135390.9.

13.

Hours Reac.or Reserve Shutdown 0.0

. 0.0 0.0 -

14.

Hours Generator On-Line 744.0 744.0 130913.8 15.

Hours Unit Reserve Shutdown.

Q&

. 0.0 0.0 16.

Gross Thermal Energy Generated (MWH) 1433668.0 433668.0 233909598.0

- 17.

Gross Electrical Energy Generated (MWH) 480540.0 480540.0 79288154.0 18.

Net Electrical Energy Generated (MWH) 461015.0 461015.0 76228978.0 19.

Unit Scrvica Factor 100.0 100.0 61.8

{

20.. - Unit Availability Factor 100.0 100.0 61.8 21.

Unit Capacity Factor (Using MDC Net) 92.5 92.5 53.7 22.

Unit Capacity Factor (Using DER Net) 94.6 94.6 55.0 23.

Unit Forced Outage Rate 0.0 0.0 11.4 24.

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

RFO-11, February 15,1997,42 cays 25.

If Shutdown at End of Report Period, i

Estimated Date of Startup-UNIT OPERATING i

1 i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

54293 NAME:

Pilanm COMPLETED BY:

R.L. Cannon TELEPHONE:

(508) 830-8321 1

REPORT MONTH January 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 652 17 631 2

651 18 627 3

647 19 626 4'

640 20 623

{

5 642 21 619 l

6 638 22 615 7

637 23 612

)

8 636 24 608 9

632 25 603 10 629 26 603 11 517 27 599 12 611 28 598 13 635 29 595 14 635 30 591 15 634 31 588 16 634 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.

OPERATIONAL

SUMMARY

DOCKET NO.

50-293 NAME:

Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE:

(508)830-8321 REPORT MONTH January 1997 Tha plant entered the period at 98.9 percent core thermal power (CTP). At 0230 on January 4,1997, reactor power was reduced to approximately 88 percent CTP for control rod exercising. At approximately 0317 hours0.00367 days <br />0.0881 hours <br />5.241402e-4 weeks <br />1.206185e-4 months <br /> i

on January 4,1997, reactor power was raised to approximately 90 percent CTP. At approximately 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> on January 11,1997, commenced control rod exercising for rods not requiring a power reduction. At gpproximately 0333 hours0.00385 days <br />0.0925 hours <br />5.505952e-4 weeks <br />1.267065e-4 months <br /> on January 11,1997, control rod exercising was completed. At approximately 0705 hours0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br />, on January 11,1997, commenced a power reduction to 85 percent CTP to complete exercising control rods that could not be performed at 90 percent power and to further reduce power to approximately 6t. jercent to bypass the hi h pressure feedwater heaters in accordance with Procedure 2.2.152, "Feedwater 0

H ster, Extraction Steam and Heater Drains." At approximately 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> on January 11,1997, power cscension to approximately 100 percent CTP was commenced. At approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on January 12, 1997,100 percent CTP was achieved. On January 18,1997, reactor power was reduced for control rod ex:rcising. At approximately 0256 hours0.00296 days <br />0.0711 hours <br />4.232804e-4 weeks <br />9.7408e-5 months <br />, reactor power was restored to approximately 100 percent CTP wh:re it remained until 2353 hours0.0272 days <br />0.654 hours <br />0.00389 weeks <br />8.953165e-4 months <br /> on January 24,1997, when reactor power was reduced approxirnately 10 p:rcent CTP for control rod exercising. At 0042 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> on January 25,1997, control rod exercising was completed and reactor power was raised approximately 10 percent CTP. The period ended with the reactor et epproximately 92 percent CTP with plant in coast down.

SAFETY RELIEF VALVE CHALLENGES MONTH OF JANUARY 1997 Requirement:

NUREG-0737 T.A.P. II.K.3.3 Th re were no safety relief valve challenges during the reporting period.

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

[.

REFUELING INFORMATION 1

DOCKET NO.-

50-293 NAME:

Pilorim COMPLETED BY:

R. L Cannon TELEPHONE:

(508) 830-8321-REPORT MONTH January 1997 l

Th3 following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, d;ted January 18,1978:

For your convenience, the information supplied has been enumerated so that each number corresponds to '

squivalent notation utilized in the request.

l

' 1.

The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.

2,.

Scheduled date for next refueling shutdown: February 15,1997.

3.

Scheduled date for restart following next refueling: March 29,1997.

'r 4.

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

5.

See #6.

l 8.

The new fuel loaded during the 1995 refueling outage (RFO-10) is of a different design than that i

loaded in the previous refueling outage and consists of 136 new fuel assemblies, j

7.

(a)

There are 580 fuel assemblies in the core.

.c

.(b)

There are 1973 fuel assemblies in the spent fuel pool. This includes 208 new fuel assemblies awaiting fuelloading for cycle 12.

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.

l

-(b)

. The planned spent fuel storage capacity is 3859 fuel assemb!ies.

)

1 9.

With present spent fuel in storagc, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.

l 1

Pil GRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE DOCKET NO.

50-293 NAME:

Pilarim

- i COMPLETED BY:

R.L. Cannon TELEPHONE-(508) 830-8321 REPORT MONTH January 1997_-

SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO.

LER PREVENT RECURRENCE i

No significant or major safety-related corrective maintenance was performed during the period.

t mm

. m...- -

-=

--e-

LA4iT SHUTDOWiss AND POWER REQUCTIONS DOCKET NO.

50-293 1

NAME-Pilarim COMPLETED BY:

R.L. Cannon TELEPHONE-(508) 830-8321 REPORT MONTH January 1997 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO.

DATE 1

(HOURS) 2 REACTOR REPORT 4

5 RECURRENCE There were no unit shutdowns or significant power reductions (> 20%) during this reporting period.

1 1

2 3

4&5 F-Forced A-Equip Failure 1-Manual Exhibit F & H S-Sched B-Main or Test 2-Manual Scram Instructions for C-Refueling 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)

F-Admin G-Operator Error H-Other k

m...

.m

., -