Text

Monthly Operating Rept for Jul 1990 for Pilgrim Nuclear Generating Station
	ML20059A083
Person / Time
Site:	Pilgrim
Issue date:	07/31/1990
From:	Highfill K, Munro W; BOSTON EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	BECO-90-98, NUDOCS 9008220118
	Download: ML20059A083 (8)
	v • d • e

F ti f

BOSTONEOlSON Pagrim Nuclear Power Station

'tocky Hill Road

. Plymouth. Massachusetts o2360 1

1 i

4 he Pr Nucker operamns August 14, 1990 BECo Ltr. #90- 98 U.S. Nuclear Regulatory Commission Attention: Document Control Desk s

Hashington, DC.20555 License tio. OPR-35 Docket No. 50-293

Subject:

July 1990 Monthly Report

Dear Sir:

)

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, i

.4 K.L. Highfi HJM:bal Attachment cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale'Rd.

King of Prussia, PA 19406 Senior Resident Inspector

/ 94 it w ADOCK2~ n,c0,,

,R, 05000293 1

7-v~,,

PDC

AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO.

50-293 UNIT' Piloria 1 DATE July 1990 COMPLETED'BY W. Munro TELEPHONE-(508) 747-8474 MONTH July 1990 1

DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MHe-Net)

(MHe-Net) 1 658 17 471 2

388 18 598-1 l

3-46 19 644-l 1

4 0

20 563 1

5

-0 21 406 6

0 22 613 7

0 23 647 8

0 24 658 9

0 25 658 i

10 0

26 642 11 179 27 425 12 287 28 243 13 368 29 180-i 14 570 30 357-1 15 600 31 617 l

16 630 i

This format lists the average daily unit power level in MHe-Net for-each day in the reporting month, computed to the nearest'whole megawatt.-

P

OPERATING DATA REPORT DOCKET NO.

50-293 DATE Julv 1990 W. 'unro COMPLETED BY M

TELEPHONE-(508) 747-8474-OPERATING STATUS Notes-1.

Unit Name Pilarim 1 2.

Reporting Period July 1990 j

L 3.

Licensed Thermal Power (MHt) 1998

'J 4.

Nameplate Rating (Gross MHe) 678 E

5. -Design Electrical Rating (Net MHe) 655 6.

Maximum Dependable Capacity (Gross MHe)-

696 7.

Maximum Dependable Capacity (Net MHe) 61Q t

8.

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

i None 9.

Power Level To Hhich Restricted, If Any (Net MPa)

None

10. Reasons For Restrictions, If Any N/A This Month Yr-to-Date Cumulative

11. Hours In Reporting Period

'744.0.

5087.0 154655.0

12. Number Of Hours Reactor Has Critical 560.6_

3820.9-89226.1'

13. Reactor Reserve Shutdown Hours 0

-0.0 0.0

(

14. Hours Generator On-Line 5A0.4 3644.4 85773.7 l

15. Unit Reserve Shutdown Hours 0.0 0.0:

0.0 i'

16. Gross Thermal Energy Generated (MHH) 857568.0 6779880.0 147264792 0

17. Gross Electrical ~ Energy Generated (MHH) 286600.0 2326440.0 49563264.0

18. Net Electrical Energy Generated (MHH) 274751.0 2237289.0 47620473.0

19. Unit Service Factor 72.6

71.6 55.5 1

20. Unit Availability Factor 72.6 71.6

- 5 5. 5' l'

21. Unit Capacity Factor (Using MDC Net) 55.1 65.6 46.0;

22. Unit Capacity Factor (Using DER Net)'

-56.4 67.1 47.0;

23. Unit Forced Outage Rate 27.4.

7.4 12.7 L

24. Shutdowns 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 -

26. Units In Test Status (Prior to Commercial Operation):

N/A i

L Forecast

. Achieved INITIAL CRITICALITY l

INITIAL ELECTRICITY COMMERCIAL OPERATION l

(9/77)

J 4

m

- ~ ~

..a_,-..

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 d

Coerational Summary for July 1990 The unit started the month on line at approximately 100 percent power. At 0511 hours0.00591 days 0.142 hours 8.449074e-4 weeks 1.944355e-4 months on 7/2/90, Reactor Recirculation Pump MG Set "A" tripped, and an active 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO was entered.

Reactor power was stabilized at approximately 66 perct it.

Following troubleshooting, attempts to start the Recirculation l

Pump MG Set "A" were unsuccessful, and at 0414 hours0.00479 days 0.115 hours 6.845238e-4 weeks 1.57527e-4 months on 7/3/90 a shutdown was inititted as required by Technical Specifications.

An Unusual Event was declared at 0419 hours0.00485 days 0.116 hours 6.92791e-4 weeks 1.594295e-4 months on 7/3/90.

Power was lowered to 30 percent and the nactor was manually scrammed at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months by placing the Mode Switch in Shutdown. The Unusual Event was terminated at 0503 hours0.00582 days 0.14 hours 8.316799e-4 weeks 1.913915e-4 months on 7/1/90 with the reactor in Hot Shutdown.

Following troubleshooting and modification to the Recirculation Pump MG Set "A", the reactor was made critical at 2025 hours0.0234 days 0.563 hours 0.00335 weeks 7.705125e-4 months on 7/10/90.

The generator was synchronized to the grid at 0455 hours0.00527 days 0.126 hours 7.523148e-4 weeks 1.731275e-4 months on 7/11/90. With the reactor power at approximately 35 percent, each recirculation pump was tripped individually and re-started under hot conditions as part of the Recirculation Pump MG Set speed control system post work testing.

While at reduced power the main condenser was backwashed on 7/13/90.

Following the backwash, power was increased to approximately 60 percent.

The unit continued to increase power to approxiniately 94 percent when on 7/17/90 the Recirculation Pump MG Set "A" tripped during testing.

The Recirculation Pump MG Set "A" was reatarted later the same day, and power was increased to approximately 98 percent on 7/19/90.

This power level was maintained until 7/21/90 when power was reduced to conduct additional testing on the Recirculatioii MG Sets and to backwash the main condenser.

Power was returned to 99 percent on 7/23/90.

At 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months on 7/26/90 the Number 2 Stop Valve inadvertently went closed, and power was reduced by operator action to 70 per:ent via recirculation pump fic*.:.v%2 tion.

Power was further reduced on 7/27/90 to perform planned maintenance and testing on the Recirculation Pump MG Set ";". At 1604 hours0.0186 days 0.446 hours 0.00265 weeks 6.10322e-4 months on 7/29/90 the main generator was taken off line to mako repairs to the Number 2 Stop Valve latch mechanism.

Following repairs the generator was synchronized to the grid at 0353 hours0.00409 days 0.0981 hours 5.83664e-4 weeks 1.343165e-4 months on 7/30h0.

Power was increased to approximately 97 percent by 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months on 7/31/90 and remained at that level for the remainder of the reporting period.

1 1

Safety Relief Valve Challenges Month of July 1990 Requirement:

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

There were no safety relief valve challenges during thit reporting period.

An SRV challenge,3 defir.ed as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual).

Ref. BECo Ltr. #81-01 dated 01/05/81.

REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo. dated January 18, 1978:

for your convenience, the information supplied has been enumerated so thst, each number corresponds to equivalent notation utilized in the request.

1.

The name of this facility is Pilgrim Nuclear Power Station, Docket Number i

50-293.

2.

Scheduled date for next Refueling Shutdown: Second Quarter 1991 h

3.

Scheduled date for restart fo. lowing refueling:

Third Quarter 1991 4.

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

)

under #6.

i a

5.

See #6, l

6.

The new ft il loaded during the 1986/87 refueling outage was of the same

}

design as loaded in the previous outage, and consisted of 192 assemblies.

7.

(a) There are b30 fuel assemblies in the coret (b) There are 1320 fuel assemt.es in the spent fuel pool.

8.

(a) The station is presently licensed to store 2320 spent fuel assemblies. 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 1000 fuel assemblies, t

t I

r,,.'m.-

y

Month Juiv 1990 PILGRIM NUCLEAR POWER STATION r

MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER R;sidual RHR Pump RHR Pump P203A Minor hydrodyna-Operations personnel Procedure 2.2.19 to be LER 90-011-00 Heat P203A tripped due to mic event (unve-walked line down and revised to vent RHR Removal false shutdown ented air) in successfully put RHR' suction piping between (RHR) cooling high the RHR suction into service.

MD-1001-50 and MD-1001 System pressure iso-line, actuated

-47.

lation signal Pressure Switch-(F&MR 90-205) es PS261-23A and 238.

High Pres-HPCI Steam Drain Body to bonnet Normal Clamp installed None N/A sure Cool--Valve leak.

aging.

to enclose the body cnt Injec-A0-2301-29 to bonnet leak. Leak tion (HPCI) sealing compound System injected into the clamp.

Main Root Valve Packing leak Normal Leak sealing compound None N/A Steam 1-H0-224A aging injected into the (MS) packing chamber.

System Main Main Steam Drain Valve MO-220-1 Faulty Valve New motor installed.

None N/A Staam Isolation Valve failed to open operator motor (MS)

MO-220-1.

during perfor-System mance of PNPS 8.7.4.3 operab-111ty test.

(F8MR 90-176) l r

w___

"*I*

PILGRIM NUCLEAR PONER STATION MAJOR SAFETY RELATED MINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Salt SSN Pump High vibration Under invest-Replaced all columns Inspection of columns N/A Service P208C igation.

with new material for degradation after Mater design. Replaced six (6) years of service.

(SSN) three (3) spider System bearings, one (1) head shaft and two (2) line shafts. Rep-laced pump motor th-rust and guide bear-ings. Rebuilt pug bowl assembly. Removed tie rods per Plant-Design Change 90-12 Phase 3.

L_ _ _ _

1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-293 7

NAME Pilorio 1 DATE Juiv 1990 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 REPORT MONTH July 1990 METHOD OF LICENSE CAUSE & CORRECTIVE ACTION TO PREVENTIVE DURATION SHUTTING EVENT SYSTg g ENT NO.

DATE TYPEI (HOURS)

REASON 2 DOWN REACTOR 3 REPORT #

CODE' RECURRENCE 06 07/3/90 F

191.8 0

2 90-010-00 AD MG-P-RG Shutdown initiated by Tech. Spec. failure to re-start "A" Recirc MG Set within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO.

07 07/17/90 F

0.0 5

N/A N/A N/A Power Reduction.

"A" Recirc MG Set tripped during testing.

08 07/21/90 F

0.0 5

N/A N/A N/A Power reduction.

Thermal backwash Main condenser.

09 07/27/90 F

0.0 5

N/A N/A N/A Power reduction. No.2 Stop Valve and "A" Recirc MG Set.

10 07/29/90 F

11.8 8

5 N/A N/A N/A Turbine Generator manually tripped to repair No. 2 Stop Valve.

~

1 2

2 3

4&5 F-Forced A-Equip Failure F-Admin 1-Manual "thibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram

.nstructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatorv Restriction 4-Continued Data Entry Sheet E-Operator

.ining 5-Reduced Load Licensee Event Report

& License amination 9-Other (LER) File (NUREG-1022)

~

_ _

ML20059A083

Text

Subject:

Dear Sir:

Navigation menu

Search