ML20071A455

Monthly Operating Rept for Mar 1991 for Pilgrim Nuclear Power Station

ML20071A455
Person / Time
Site:	Pilgrim
Issue date:	03/31/1991
From:	Richard Anderson, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-053, 91-53, NUDOCS 9104160219
Download: ML20071A455 (8)

Text

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. BOSTON EDISON Pilgom Nuclear Nw Etation Rock,y Hill Road Plymouth, Manathusetts 02300 ePr??nt?

$$$ cip*0.Y .n. April 12, 1991 BECo Ltr. #91-033 U.S. Nuclear Regulatory Commission i Attention: Document Control Desk i Hashington, DC 20555 i License No. OPR-35 pocket No. 5.Qd,.21_ l

Subject:

March 1991 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.

,) o th j'j f5th - \N R/A. Anderson

/

HJH/bal Attachment cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector 9104160219 910331

{DR ADOCK0500 gig'3 {g]p lll .

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AVERAGE DAILY UNIT P0HER LEVEL I

DOCKET NO. 5Q.-29 3 UNIT Pilarim 1 DATE Ati r i l 12, 1991 COMPLETED BY _H. Munro TELEPHONE (508) 747-8474_

HONTH Harch 1991 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POHER LEVEL (MWe-Net) (MWe-Net) 1 665 17 630 2 664 18 665 _

3 663 19 665 .

4 5 11 20 665 5 201 21 665 6 . . . , _18 6 22 665 7 . . _ _ .

183 23 663 8 346 24 664 9 _

635 25 318 10 664 26 463 11 637 27 625 12 605 28 482 13 665 __ 29 654 14 665 30 660____

15 635 31 662 16 479 This format lists the average daily unit power level in MWe-Net for each day in t',e reporting month, computed to the nearest whole megawatt,

l OPERATING DATA REPORT l

,' DOCKET NO. 50-293 l DATE Ap r rt 12, 1991

)

COMPLETED BY _H. Munro TELEPHONE 198) 747-8474 OPERATING STATUS Notes

1. Unit Name Pilarim 1

2. Reporting Period _ Earth 1991

3. Licensed Thermal Power (MHt) 19H

4. Nameplate Rating (Gross HHe) 678

5. Design Electrical Rating (Net MHe) 6.M

6. Maximum Dependable Capacity (Gross MHe) 696

7. Maximum Dependable Capacity (Net MHe) 670 _ _ _ _ _

8. If Changes Occur in Capacity Ratings (1tems Number 3 Through 7) Since Last Report, Give Reasons:

,_ . None _

9. Power Level To Hhich Restricted, If Any (Net MHe) _..None

10. Reasons for Restrictions, If Any N/A Ih11_Equih Yr-to-Date Comulative

11. Hours In Reporting Period _- 744.0 2160.J 160488.0

12. Number Of Hours Reactor Has Critical ,_ 744J 2160.0 94760.7

13. Reactor Reserve Shutdown Hours AS 0.0 0.0

14. Hours Generator On-line 744.0 2160.0 91076.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Grot,s Thermal Energy Generated (MHH) 1282152.0 ._3925920.0 157267416.0

17. Gross Electrical Energy Generated (HHH) 438860.0 ._1348090.0 52995604.0

18. Net Electrical Energy Generated (MHH) _42170LQ 1297285.0 50923693.0

19. Unit Service factor 100.0 100.0 56.7

20. Unit Availability factor 100.0 100.0 56.7

21. Unit Capacity factor (Using HDC Net) 84di 89.6 47.4

22. Unit Capacity factor (Using DER Net) Bidi 91.7 48.4

23. Unit Forced Outage Rate 0.0 0.0 12.5

24. Shutdowns Scheduled over Next 6 Honths (Type Date, and Duration of Each):

Refuelino Outaae No. 8. Hav 1991. aporoximatelv 70 days

25. If Shut Down At End Of Report Period Estimated Date of Startup N/A 1

j BOSTON EDISON COMPANY i'

PILGRIM NUCLEAR POWER STATION f ,

DOCKET NO.50-29J _

Ooerational Summarv for March 1991 The unit started the reporting period at 100 percent power. On March 4, 1991 operation at reduced power levels was necessitated for replacement of the "A"

. recirculation pump motor generator (MG) set brushes, followed by a condenser cloride intrusion the same day which required operation at 50 percent power to isolate the 1-3 condensar water box. The unit remained at reduced power until March 5, 1991 when at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br /> the unit entered an LCO for Maximum Fraction of Limiting Power Density (MFLPD) greater than fraction of Rated Power (FRP),

requiring a power reduction to below 25 percent. On March 6, 1991 with MFLPD acceptable.-a power increase to 35 percent was performed. While at reduced power the "A" recirculation MG set was again removed-from service to implement a temporary modification to add a second set of brushes on the generator end.

Power remained at 35 percent until March 8,1991 when the source of the cloride intrution (tube leakage) was discovered and repaired. Power ascension progressed and the unit attained 100 percent power on March 9, 1991. The unit remained at approximately 100 percent power through March 24, 1991 with the exception of two occasions March 11 and 15, when power was reduced to approximately 45 percent to perform condenser backwashing. On March _24. 1991 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> a lockout of the_ shutdown transformer occurred, resulting from a negative sequence trip. On March 25, 1991 while testing the "B" emergency

. diesel generator (EDG), required surveillance for shutdown _ transformer out of service, a lockout of the the 4160 volt bus'A-6 occurred and the "B" EDG tripped, deenergizing-the entire "B" safety related power train. Power was reduced to 35 percent. Plant conditions were stabilized, and on March 25, 1991 bus A-6 was returned to service. Following repait and testing,-the "B" EDG was declared opdable on March 28, 1991. An operability evaluation was performed on the shutdown tre.nsformer to permit operation with the negative

- sequence trip disabled. -Reactor power was increased to 98 percent on Harch 29, 1991 and ended'the. reporting period at 100 percent. Control rod exercises were performed on March 2, 9, 16, 23 and 31, 1991 Safety. Relief Valve Challenges Month of March-1991 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief velve challenges during this reporting period.

- An SRV cha11cnge is defined as anytime an SRV has received a signal to-operate l -- via reactor pressure, auto signal (ADS) or control switch (manual). Ref. BECo Itr.'#81-01 dated 01/05/81..

l i-

[ _,.~s. _U ~.,f., .,~.~L.. _,e_..m..., -. ,....-____<

BEFUELING INf0RMATIQM The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 18, 1978:

for your cor,enience, the information supplied has been enumerated so that, each number corresponds to equivalent not6 tion utilized in the request.

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

2. Scheduled date for next Refueling shutdown: Second Quarter 1991

3. Scheduled date for restart following refueling: Third Quarter 1991

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

5. See #6.

6. The new fuel 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 580 fuel assemblies in the cor'e.

(b) There are 1487* 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 capreity 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.

• Includes 167 new fuel assemblies to support current refuel outage.

Month March 1991 ~

PILGRfM NUCLEAR P0HER STATION MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMM)NENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER Recirc- "A" Recirculation Generator end_ Root cause Replaced all fcur Collector rings MsA ulation Motor Generator brushes arcing under investi- brushes. Later in scheduled for replace-  !

System Set

• due to worn gation.- the reporting period ment dering RF" 8.

and pitted Temporary Modifica-collector ring. tion TM91-12 Rev.1 was implemented to

, add a second set of l

' brushes to the gen-erator end outboard collector ring.

Reactor Terminal strip for During Surveil- Repeated Broken terminal Refer to associated LER 91-004-00 i Core Temperature Switch lance Test torquing of the swapped with spare LER.

Isola- TS 1350 (Heidmuller 8.M.2-2.6.3 screws. terminal on same ,

tion SA K6N). Temperature block. MR written  ;

Cooling Switch to replace broken i System TS1360-14C terminal. '

could not be relanded. ,

Terminal strip-ped. (F&MR91-90) i Diesel "B" Diesel Gener- Failure of Root cause Replaced automatic Failed voltage iegulator LER 91-005-00 '

Genera- Generator automatic under voltage regulator. to be sent to manufact- (to be issued) tors ("B-EDG") voltage reg- investigation urer (Basler Electric) and ulator for analysis.

Auxil- (Basler Elect- t iaries ric).

(FEMR 91-99) +

) k

Month March 1991

~

~

PILGRIM GlCLEAR P0HER STATf0N ,

MAJOR SAFETY RELATED MAINTENANCE .

SYSTEM COMPONENT MALFUNCTION [AUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED  ;

PREVENT RECURRENCE LER __ i t

i High Pressure Trans- Degraded per- Loss of fill- -Pressure transmitter Refer to associated LER LER 91-003-00 f I'ves- mitter PT263-508 fomance. oil in pressure replaced with rebuilt sure (Rosemount Inc). transmitter's Rosemount Inc. Unit.

Coolant sensing module. i Injection [

System.

i  ;

Condenser Condenser Chloride Tube leakage Plugged leaking N/A N/A l and 1-3 water intrusion tubes l

~

Condenser box

• Auxiliary l System l

• NOTE Items are not safety related, however caused major reduction in power.

3 t'

t i

_ ___ _ . _ _ _ _ __.___ . _ _ _ -__t_ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ . _ .- _ . _ _ . . _ _ . _ _ . -_ _ _ _ . _ _ .

__e _ _ . _ _ _ _ _

m UNIT SHUTDOHNS'AND P0HER~REDUCTIG~S'

' ~

DOCKET NO.L50-293'  :.-

2

. NAME_ Pilorin 1 '

DATE aprit 12..1991 ,

COMPLETED BY'N. Munro .-

i.

, TELEPHONE- (508) 747-8474'

. REPORT: MONTH March'1991 METF2 0F -

LICENSE- CAUSE & CORRECTIVE:

DURATION SHUTTING EVENT- ENT ACTION.TO PREVENT ~

SYSTEg NO. DATE' ' TYPEI ' ~(HOURS) ' REASON 2 DOHN REACTOR 3 REPORT # CODE COMyE-COD RECURRENCE' 4 03/04/91 F 0.0 N/A 5 'N/A N/A -N/A Power reduced to-replace Retirc.' MG Set-

"A" brushes;' Adjust MFLPD; implement Temp..

, Mod. to add additional brush on MG Set "A";

troubleshoot condenser.

.cloride intrusinn.

5 '03/16/91 F 0.0 N/A' 5 N/A N /.'. N/A Power reduced to per-

~

form main condenser-backwash.

6 03/25/91 F -0.0 N/A '5 91-005-00 EK/EB -DG,90 Power reduced due to.

loss of O' Bus.

7 03/28/91 F 0.0 N/A 5- 91-005-00 EK/EB DG,90 Power reduced to'per-form "B" Diesel testing.

l 1 2 2 3 4&5 l

l F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H l S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for

l. C-Refueling .

H-Other 3-Auto Scrain Preparation of

D-Regulatory Restriction 4-Continued Data Entry Sheet l E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER). File-(NUREG-1022) l l

l

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