ML20198L770

Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station

ML20198L770
Person / Time
Site:	Pilgrim
Issue date:	12/31/1997
From:	Cannon R, Desmond N BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-2.98.003, NUDOCS 9801160114
Download: ML20198L770 (3)

Text

- _ _ - _ _ _ _ _ _ _ -_- --__- - - _ _

Tech. Spec. 6.9.A.2 l *-

4 Boetors Edieors Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachuset's 02360-5599 Nancy L Desmond Regidatory Relations G.sup Manager January 14,1998 BECo Ltr. 2.98.003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50.293 License No. DPR-35 Decemt,er 1997 Monthly Report in accordance with Pilgrim Nuclear Power St& tion Technical Specification 6.9.A.2, a copy of the operational status summary for Pilgrim Nuclear Pnwer Station is provided in the attachment for your infurmation and plannilig. Shoutr'")u have ar, ciestions conceming this report, please contact me directly.

fy U N. L. Desmond M h RLC/dcgidecmonth

Attachment:

December 1997 Monthly Report cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission  ;

475 Allendale Road King of Prussia. PA 19406 h"M.J ' )

Senior Resident inspector

~

9.'01160114 971231 gDR ADOCK0500g23 J g ,pi s

]I ji q ,

i

,y Att^ chm:nt GPERATING DATA REPORT 50-293 DOCKET NO.

NAME: Pilorim COMPLETEtt BY: R.L. Cannon TELEPHONE- f508) 830-8321 REPORT MCNTH: December 1997 OPERATING STAMS BOTES

1. Unit Name Pil;f.m i

2. Reporting Period December 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 Chanoes _..

9. Power Level To Which Restricted, If Aor .At MWe): None

10. Reasons For Restrictions, if Any: N!A THIS MONTH YR-TO-DATE CUMULATIVE

11. Hours in Reporting Period 744.0 8760.0 219696.0

12. Hours Reactor Critical 637.1 7068.0 141714.9

13. Hours Reactor Reserve Shutcown 0.0 0.0 0.0

14. Hours Generator On-Line 572.1 6841.7 137011.5

15. Hours Unit Reserve Shutdown 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1030708.0 13135510.0 245611440.0

17. Gross Electrical Energy Generated (MWH) 356590.0 4481870.0 83289484.0

18. Net Elec+-ical Energy Generated (MWH) 342749.0 4310431.0 80078394.0

19. Unit Sorvice Factor 76.9 78.1 62.4

20. Unit Availability Factor 76.9 78.1 62.4

21. Unit Capacity Factor (Using MDO Net) 68.8 73.4 54.4

22. Unit Capacity Factor (Usir.g DER Net) 70.3 75.1 55.6

23. Unit Forced Outage Rate 23.1 11./ 11.5

24. Shutdowns, Scheduled Over Next 6 Months (Type, Date, and Duration of Each) None li Shutdown At End Of Report Period, Estimate Date Of Start-Up Unit Operating

_ r. m. e. _ ,, _.. _ . _ , . - _. - .- -- - _ _

DOCKET NO. .50-293? . *1 ~ >

L. NAME: Pilanm i

~: - COMPLETED BY; t R. L Cannon n;

'~(TELEPHONE- (508) 830-8321? .e

REPORT MONTH: December 1997 ' g ~

- OHRATION

SUMMARY

cThe plant entered December in a shutdown condition performing maintenance on main steam isolabon valves (MSIVs) AO-203-.1C anNAO-203- *

" 28.1 On 12/3, at 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br />, the generator was synchronized to the grid. On 12/5, at 01_44 hours, the plant commenced reducing power from : ._

~ approximately 35% core thermal power (CTP) in response to a nitrogen leak detected in the drywell. On 12/5, at 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />, the plant was taken L ,

! off line to facilitate isolation of a nitrogen leak in the drywell. On 12/5, at 2252 hours0.0261 days <br />0.626 hours <br />0.00372 weeks <br />8.56886e-4 months <br />, the generator was syrdrienized to the grid. -.On 122, at ; 3 0908 hours0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.45494e-4 months <br />; the plant expenenced a reactor scram in response to a react 0r high water level signal resultog from problems with one of the two

!' i feedwater regulatmg valves. On 12/10, at 0103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br />, the genamior was synchronized to the grid. On 12/11, at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, the plant attamed

. 1100% CTP where it was maintained until 12/12. On 12/12, at approximately 1056 hours0.0122 days <br />0.293 hours <br />0.00175 weeks <br />4.01808e-4 months <br />, the plant reduced power in response to a recuculatog .

J pump trip. LOn 12/13. at 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br /> < the plant attained .100% CTP where it was essentially maintained through the end of the reportog penod i One safety relief valve'was lifted during this period for post work testing. Other maintenance activrbes were performed in av.vida cs with the ? j forced outagt work schedule.

UNIT SHUTIX)WNS I' I METHOD OF CAUSE/ CORRECTIVE ACTION / COMMENTS 3

TYPE DURATION REASON SHUTTING DOWN

[ NO. DATE! (HOURS) .

REACTOR -

1' '2 3 1- 971201- F 84.0 A 1 Reactor was manually shutdown when main steam isolation valves AO-203-con't 1C and AO-203-28 did not indicate fully closed during surveellence testlng. [

The details regarding this shutdown are documented in License Event -

Report 97-025-00.  ;

2 971206 F 87.9 A 3 Automatic scram due to high reactor water level dunng power ascertsion from the forced shutdown of November 23,1997.' The high waterlevel .  :

resulted from failure of the.*A* feedwater regulating valve. The details ' .

• regarding this shutdown are documented in License Event Report 97-026-f A

, 00.

, 1 2 3 i F - Forced A - Equip Failure 1 - Manual

- S - Scheduled B - Main or Test 2 - Manual Scram c'

C - Refueling .

3 - Auto Scram '

^

D - Regu story Restriction. 4 - Continuation E - Operator Training & 5 - Other License Examination

,. F - Admin ~

G - Operation Error H - Other l

, ,, _ , - , - _m _ . . _ , ..