BECO-92-076, Monthly Operating Rept for June 1992 for Pilgrim 1

Monthly Operating Rept for June 1992 for Pilgrim 1

ML20101Q865
Person / Time
Site:	Pilgrim
Issue date:	06/30/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-92-076, BECO-92-76, NUDOCS 9207150139
Download: ML20101Q865 (8)

Text

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BOSTON EDISON Paigem Nuclear Poet 5tabon Rocky Hill Anad Plymouth, Mas 5xhun tn 02300 E. Thomas Boulette. PhD Vice Presdent Nuclear Opmatons and Staton Deectet July 14, 1992 BEco Ltr. #92-076 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555 License No. DPR-35 Eqclet No. 50-293_.

Subject:

June 1992 Monthly Report 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.

b / [ occ(f//-(

E. Thomas Boulette WJM/bal Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King.of Prussia, PA 19406 Mr. R. B. Eaton Div. of Reactor Projects 1/11 Office of NRR - USNRC One White Fiint North - Mail Stop 1401 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector

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9207130139 920630 j

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4 ayfBAGE CAlLY UNIT POWER LEVEL, DOCKET NO.

50-293 UNIT Pilarim 1 DATE

.. Ju.Ts _14. 1992

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COMPLETED BY

_ W. Munro TELEPHONE (500) 747-8474 MONTil,,.slyne __1992 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 1 577 17 663 2.

661.

18 664 3

664 19 665 4

662 20 664 5

661 21 664 6_

656 22 663 7

660 23 665 i

8 662 24 664 9

660 25 663 10 660 26 664 11 660 27 663 12 3 61 28 664 13

~622 2'9 664 14 564-30 663 15 666

.31 N/A 16 -'

663 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.

_ = _ _

9D-*P-p-1=.M vagpt sr

• Wa*-eh e BWd 9 Ye-W-4

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f W M"4"t*Ff"'M"fN

OPERATING DATA REPORT DOCKET NG.

50-293 7

n DATE J.uiv it,. 19o9 j%,.

COMPLETED BY W,' Monro TE! ' HONE

_Qq8) 7/,7-8474 _

_?ERATING..;tIMUji 4

Note, b

y

. Unit. Naraa Pily;im 1 L

2.

Reporting Period,,,_ June 1992 3.

Licensed Thermal Power (MWt) 1998

[

4.

Nameplate Rating (Gross MWo) 678 5.

Design Electrical Rating (Net MWe)._

655 6.

Maximum Dependat,le Capacity (Gross MWe) 695 7.

Maximum Dependable Capacity (Net MWe) 67Q 8.-

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

X None 5

Power Level To Which Restricted, If Any (Net MWe)

Wone y

10.ResrirlrRestrictions,i'Any 9/A k

y Titis Month Lr tqdal_e fd4EU)1t1YM

11. Hours In Reporting Period 720&

4367.0 _ 171455.0

12. Number Of Hours Reactor Was Critical 720.0 3.J89. 6 102350.R

n. Reactor Reserve Shutdown Hours 0.0 0.0

.q. D 14._ Hours Generator On line

' 7 20_&

_ 3937.5 18440d

15. UnitLReserve Shutdown Hours Q.4 0.0

_.2d 16.- Cross Thercial Energy Generated (MWP.)

J420824 2

_7]_07288.0 f/liU].fg.a

17. Gross Ei.:ctrical Er.ergy Generated (MWR) 461930 Q

?fbj530.0 _57867944J

18. Net Electrical-Energy Generated (MWH) 471QLO

_M5.2428,0 SE613376.0 19.' Unit Service Factor 100.0 90 1 57.4

20. Unit' Availability Factor 100.0:

90.2 5]_d

21. Unit Capacity Factor (Using MDC Net)

_ 100.0 8.14 40.5 97.8 87.6 4_8 d 2?. Unit Capacity Factor (Using DER Net)

-23. Unit Forced Outage Rate 0.0-98 12J 24'. Shutdowns Scheduled.0ver Next 6 Months (Type, Date, and Duration of Each):

F,ldevcle 'outaae - October 1992 Aporoxima_t.ely 3.5 days

25. If Shut Down At_End Of R., cort Period, Estimated Date of Startup N/A l

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4 BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET

• 50-293 OperatJonal Summary for June 1992 The unit started the reporting period at approximately 100 percent core thermal power (CTP). On June 1 at 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> while attempting to change out the "B" Recirculation Motor Generator Set outer exciter brushes while on-line, a generator lockout occurred causing the "B" Recirculation Punp to trip.

Reactor power dropped to 46 percent OTP.

Following change out of the brushes the "B" Recirculation Pump was restarted on June 1 at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br />.

Reactor power was returned to 100 percent Cr, at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> on June 2 and maintained until June 13 when at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> power wa; reduced to approximately 50 percent to perform a main condenser backwash.

Fellowing a successful backwash reactor power was increased to 100 percent at 1412 hoars on June 14, where it was essentially maintaincd for the remai,1 der of the reporting period.

Weekly control rod exercises were performed on June 6,13, 20 and 27.

Safety Relief Valve Challenges MonLD of_ June 1992 Requirement:

NUREG 0737 1.A.P. l!.K.3.3 There were no safety relief valve challenges during this reporting period.

n An SRV challenge is defined as anytime an SRV has received a sigral to operate via reactor pressure, auto signal (ADS) or control switch (manual).

nef. BECo ltr. #81-01 dated 01/05/81.

i

F REFUELING INFORMATION l

1 The following refueling information is included in the Monthly Repert as requested in an.NRC letter'to BECo, dated January 18, 1978:

For your convenience, the inforniation supplied ' - been enumerated so that each number corresponds to equivalent notation utilie in the request.

1.

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

2.

Scheduled date fcr next refueling shutdown: April 1, 1993 3.

Scheduled date for restart following next refueling: June 8, 1993 4.

Due to their similarity, requests 4, 5, & 6 are responded to collectively under 96.

5.

See #6.

6.

ibe new fuel loaded during the 1991 refueling outage was or the same design as loas'ed in the previous outage and consisted of 168 assemblies.

/.

(a)

There'are 580 fuel assemblies in the ce-e.

(b) There are 1489 fuel assemblies 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 831 fuel assemblies.

2

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o MONTHf June. 1992' PILGRIM NUCLEAR POWER STATION

'MA-10R SAFETY RELATED MAINTENANCE SYSTEM COMPONENT.

MALFUNCTION

-CAUSE MAINTENANCE-CORRECTIVE ACTION TO ASSOCIATED PREVENT RECUF.RENCE LER Primary Post Accident failed to Limit Switch Performed timit None N/A

.Contain-Purge and Vent indicate out of ad-

' Switch adjust-

. ment.

Valve SV-50828

" Full epen" justment ment to obtain

'Atmo-position proper " Full open' spheric during stroke position indica-Control timing test.

tion. Performed (PCIS)

(PR92.9067) post work test satisfactorily.

System Reactor Recirculation.

Generator

. Accidental

' Changed out MG To be determined N/A Recircu--

Pump M5 tor Gen-lockout shorting of set outer exciter lation erator (MG) causing "B" opposite brushes, and re-System Set X-234B*

Recirculation polarity started the "B" Pump to trip.

brush pig-Recirculation Pump.

(PR92.9075) tails on ex-citer collect-or rings while l

changing out t

MG Set outer exciter brushes on line.

Reactor RBCCW Pump Pump seal Faulty Implemented Replacement of N/A Building P-2010 leaking mechanical FRN 92-03-18 to each RBCCW Closed mechanical seal.

replace original pump nechanical mechanical seal seal on an as Cooling seal.

(single) with needed basis.

Water split seal.

(RBCCW)

(Chesterton System type 221) o Not a Safety System,. however, the malfunction caused 'a power reduction.

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. MONTH JUNE 1992' PILGF.lM NUCLEAR POWER STATION-MAJOR SAFETY RELATED MAINTENANCE G

~

SYSTEM.

COMPONENT MALFUNCTION CAUSE:

MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED

~

PREVENT RECURRENCE LER

. Reactor Terminal ' block

Weakened ter-Repeated

' Replaced Refer to associated LER 92-Core

. in Junction mination point loosening ~

terminal-LER.

007-00.

Isolation.

Box J599.

.on terminal:

and torquing with installed (To be Cooling

. block for

' of: terminal spare.

issued)

(RCIC)

Temperature.

block screws System-

~ Switch Juring quar-TS-1360-16C.

terly cali-brations.

Salt

- Sample tap on Sheared off Unknown.

Removed woeden Train personnel to N/A

Service abandoned. hypo-pipe ^ nipple.-

plug and re-make aware of code

-Water chlorinatfor.

(PR 92-0203.01)-

maining broken repcir,and Temp.

(SSW) sample-system nipple; repl-Mod. requirements.

System off the-SSW aced with new discharge line.

nipple and capped using-approved code repair.

(FRN 92-03-25)

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A DOCKET No.-50-293 UNIT SHUTDOWNS AND POWER REDUCTIOFS NAME PILGRIM 1 DATE Niv 14, 1992 COMPE EED BY W. MUNR0 TELEPHONE SOB 747-8473 REFORT-MONlti JUNE 1992 METHOD OF LICENSE CAUSE & CORRECTIVE

. DURATION

SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO.

DATE TYPEI (HOURS)

REASON

_DOWN REACT 0k REPORT # CODE 4 CODES RECURRENCE There were no unit shutdowns or significant power reductions during the reporting period required to be reported.

i d

2 3

4&5 1

2 i

F-Forced A-Equip Failure E-Admin 1-Manual Exhibit F & H S-Sched E-Main or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparations of 4-Continued Data Entry Sheet D-Regulatory Restriction 5-Reduced Load Licensee Event Report E-Operator Training 9-Other (LER) File (NUREG-1022)

& Ltcense Examination 1

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