ML20216J413

Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station

ML20216J413
Person / Time
Site:	Pilgrim
Issue date:	08/31/1997
From:	Cannon R, Desmond N BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-2.97.093, NUDOCS 9709170277
Download: ML20216J413 (7)

Text

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• I l Tech. Spac. 6.9.A.2

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, Pilgrim Nuclear Power Station l Rocky Hill Road Plymouth. Massachusetts 02360 5599 l

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, Nancy L Desmond Regulatory Relations Group i'anager 3,g , g 4 3997 BECo Ltr. 2.97093 i U.S. Nuclear Regulatory Commission

Attention: Document Control Desk

. Washington, DC 20555 Docket No. 50.293 License No. DPR 35

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Aunust 1997 Monthly Report  !

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in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is provided in the attachment for your information and planning. Should you have any questions concerning this report, please contact me i

directly.

kt0d91 N. L. Desmond i

l RLC/dmc/radmisc/897 mrpt

Attachment:

August 1997 Monthly Report cc: Mr. Hubert Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission g ,, (

475 Allendale Road King of Prussia, PA 19406 y j ke g Senior Resident inspector

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9709170277 970831 PDR ADOCK 05000293

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, Attachm:nt OPERATING DATA REPORT 1 ,

i DOCKET NO. 50-293 i NAME: BladH1

! COMPLETED BY: R.L. Cannon i TELEPHONE: (508) 830 8321 j REPORT MONTH: Auaust 1997 OPERATING STATUS NOTES t

j 1. Unit Name Pilgrim i j 2. Reporting Period August 1997

3. Licensed Thermal Power (MWt) 1998 l' 4. Nameplate Rating (Gross MWe) 678

S. Design Electrical Rating (Net MWe) 655

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6. Maximum Dependable Capacity (Gross MWe) 690 l

7. Maximum Dependable Capacity (Net MWe) 670

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

l No Chances

9. Power Level To Which Restricted, if Any (Net MWe): None 1 10. Reasons For Restrictions, if Any: N/A I THIS MONTH YR TO DATE CUMULATIVE

11. Hours in Reporting Period 744,0 5831.0 216767.0 j 12. Hours Reactor Critical 744.0 4419.7 139066.6

13. Hours Reactor Reserve Shutdown 0.0 0.0- 0.0

14. Hours Generator On Line 744,0 4266.2 134436.0 l

15. Hours Unit Reserve Shutdown 0.0 - 0.0 0.0

, 16. Gross Thermal Energy Generated (MWH) 1465398.0 8176354.0 240652284.0 4

17. Gross Electrical Energy Generated (MWH) 499600.0 2777150.0 81584764.0 l . 18. Net Electrical Energy Generated (MWH) 480723.0 2669588.0 78437551.0

19. Unit Service Factor 100.0 73.2 62.0

20. Unit Availability Factor 100.0 73.2 62.0

21. Unit Capacity Factor (Using MDC N: t) 96.4 68.3 54.0 j_ 22. Unit Capacity Factor (Us'ng r;ER Net) 98.6 69.9 55.2

23. Unit Forced Outage Ra'a 0.0 11.4 11,5

24. Shutdowns, Scheduled Over Next 6 Months (Type, Date, and Durat. ion of Each) None l' 25. If Shutdown At End Of Report Period, Estimate Date Of Start Up N/A ,

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1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50 293  ;

NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: (508)830-8321 REPORT MONTH: Auaust 1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL pH (MWe Net) DH (MWe Net) 1 655 16 658

3. 652 17 659 3 653 18 657 4 649 19 655 5 648 20 656 6 651 21 658 7 651 22 658 8 652 23 398 9 651 24 619 10 653 25 662 11 655 26 659 12 654 27 661 13 655 28 662 i

14 657 29 660 15 656 30 658 31 659 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,

r OPERATIONS

SUMMARY

DOCKET NO. 50 293 NAME: Pilarim  ;

COMPLETED BY: R.L. Cannon  !

TELEPHONE: (508) 830 8321 REPORT MONTH: Auaust 1997 l

Th3 plant began the reporting period at 100% Core Thermal Power (CTP) where it was essentially maintained {

until August 23, 1997. On August 23,1997, at 0801 hours0.00927 days <br />0.223 hours <br />0.00132 weeks <br />3.047805e-4 months <br />, the plant commenced reducing power to ')

approximately 43% CTP in response to a seaweed intrusion into the inlet structure. On August 24,1997, at  ;

0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, the plant attained 100% CTP where it was essentially maintained through the end of the  :

rcporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF AUGUST 1992 I Requirement: NUREG 0737 T.A.P.II.K.3.3 j Thtre 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 signal (ADS) or control switch (manual). Reference BECo Ltr. #8101 dated January 5,1981. l 3

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, REFUELING INFORMATION DOCKET NO. 50 293

. NAME: Pilarim COMPLETED BY: R.L. Cannon TELEPHONE: 1508)830-8321 REPORT MONTH: Auaust 1997 Th3 following refueling information is included in the Monthly Report as requested in NRC letter to BECo, d:ted 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: March 20,1999.

3. Scheduled date for restart following next refueling outage: April 24,1999.

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

5. See #6.

6. The new fuel loaded during the 1997 refueling outage (RFO #11) is of the same design loaded in the previous refueling outage and consists of 208 new fuel assemblies.

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

(b) There are 1974 fuel assemblies in the spent fuel pool.

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.

O. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 894 fuel assemblies.

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UNIT SHUTDOWNS AND POWER REDUCTIONS

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DOCKET NO. 50-293 NAME- Pilorim .

COMPLETED BY: R.L Cannon TELEPHONE- (508) 83CN3321 REPORT MONTH: Avaust 1997 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 6 970823 F 0 H N/A N/A N/A N/A Power Reduction from 100% CTP to approxanately 43% CTP due to seaweed intmson into the sea waterintake structure.

t There were no unit shutdowns during this reporting period. There was one power reducbon for Maintenance (thermal backwash)

[ 1 D 2 3 [ 4&S )

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

( ) C - Refueling D - Regulatory Re.striction 3- Auto Scram Data Entry Sheet Ocensee Event Report (LER) 4 - Continued File (NUREG-1022)

E- Operator Training & 5- Reduced Load Lict. nse Examination 9 - Other j F- Admin /

G -Operation Error H - Other

. . . _ -. . . = _ . - -. . ... -. -_ -_ . . . . . . - - - . - . . . - - . _ .

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' PILGRIM NUCLEAR POWER STATION SK3NIFICANT SAFETY-RELATED CORRECTWE MAINTENANCE -

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DOCKET NO. 50-293 NAME- Pilanm -

COMPLETED BY: R.L Cannon TELEPHONE- (508)830-8321

• REPORT MONTH: Auoust 1997 i

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

Low Relay 10A- Two pairs of Root Failed relay was Pending completion of the root cause LER 97 ~ '-00 l Pressure' K278 failed contacts Cause replaced and analysis  !

Coolant evaluation satisfactorily injection not yet tested i completed I i i

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