BECO-LTR-92-117, Monthly Operating Rept for Sept 1992 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Sept 1992 for Pilgrim Nuclear Power Station

ML20115A939
Person / Time
Site:	Pilgrim
Issue date:	09/30/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-92-117, NUDOCS 9210150184
Download: ML20115A939 (7)

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,, L BOSTON EDISON Pil yim Nuclear Power Station Rocky Hail Roed Pyruouth, Massachusetts 02360 E. Thomas Boulette, PhD vice Presde r,t Nuclear Operatons one stainn omer October 14, 1992 BEco Ltr. #92 117 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

. September 1992 Monthly Report in accordance with PNPS Technical Specification 6.9. A.2, a copy of the Operational Statu. 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.

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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 19400 Mr. R. B. Enton Div. of Reactor Projects 1/11 Office of NRR - USNRC One White Flint North - Mail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 Senior Resident inspector 9210150184 920930 l PDR ADOCK 03000293 \

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. i AERA.Jil. DAILY UtilT POWIR LEVEL DOCKET T10. 50-293 Villi _Eilarim 1 _

DATE oct.cbe r__14._1992 LOMPLETED BY._W, Munrg _...

TELEPil0flE L5_qel.747-8474 M0f1Til Jeptemtier 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 66.2 17 663 2 660 18 662 .

3 _ . _ _ 662 19 _.

Q62 4 662 20 661 5 661 21 663 6 661 _ _ 22 _

663 7 660 23 665 8 661 24 662 9 661 25 66]

10 663 26 662 11 663 27 661 12 _

660 28 550 13 402 29 489 14 458 30 478 15 . . _ 661 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.

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OPERATING DATA REPORT DOCKET NO. 50-293 DATE october 14. 1992 COMPLETED BY TELEPHONE W . Jign_r.p__._54 74 (5081-747- _

l OPERATING STATUS l Notes

1. Unit Name Pilarim 1

2. Reporting Period Seotember 1992

3. - Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

5. Design Electricai Rating (Net MWe) r 451

6. Maximum Dependable Capacity (Gross MWe) 696

7. Maximum Dependable Capacity (Net MWe) 670

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

None

-9. Power Level-To Which Restricted, If Any (Net MWe) None

16. ~ Reasons for Restrictions, If Any N/A P

__. r This Month Yr-to-Date Cumulative

11. Hours-In Reporting Period 720.0 6575.0 173663.0

12. Number Of Hours Reactor Was Critical 720.0 6197 6 104558.2 .

13- . Reactor Reserve Shutdown Hours- 0.0 u0.t0._ 0.0

14. Hours Generator On-line 720.0- 6145.5 -100648.4

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 .

16. Gross Thermal Energy Generated (MWH) 1374792.0 -11018360,0 175722840.0

17. Gross Electrical Energy Generated (MWH) 472000.0 4142460.0 59348871tQ

18. Net Electrical Energy Generated (MWH) 454146.0 3907559.0 57038507.0

19. _ Unit Service Factor 100.0 93.5 58.0

20. Unit Availability _ Factor-. _ 100.0 93.5- 58.0

21. Unit Capacity Factor (Using MDC Net)- 94.1 90.5 49.0 *

'22L Unit Capacity Factor (Using DER-Net) 96.3 92.6 50 1

-23. Unit' Forced Outage Rate . . _ _

0.0 6.5 12.3-124. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):- ,

Midcycle outaae - Start October 24, 1992. Duration 30 days

25. If Shut Down At End of Report Period, Estimated Date of Startup N/A-t- T* i e- t4+mgtrge et er 1= -v t--my 9- w -ee a-ar ee--1-,r,---=-e w ww-+ ,e --r----

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BOS10!1 EDISoft COMPANY PILGRlM fiUCLEAR POWER STATION

_ DOC QT fio. 50-293 OPfrat ignalltmmiiry f or SpjL emher t 1992 The unit started the reporting period at approximately 100 percent core thermal power (ClP) and maintained this power level until September 13 when reactor power was reduced to approximately 43 percent C1P to backwash the main condenser. Following the backwash reactor power was increased to approximately 65 percent CTP to facilitate a rod pattern exchange and perform selective maintenance. On September 15 the unit attained 100 percent CTP where it was maintained until Septemoer 28 when power was reduced to approximately 75 percent C1P to facilitate maintenance ' the "A" Condensate Fump. On September 30 at approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> reactor power was further reduced to approximate 64 percent CTP to investigate a problem with the "C" Reactor feedwater Pump. The unit ended the reporting period at approx.mataly 64 percent CTP and increasing power.

Weekly control rod exercises were performed on September 5,12,18 and 26.

Safety Relief Valve Challenges *

[ionth of Septemtler 1992 Requirement: fiUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during this reporting period.

An SRV challenge is defined 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

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EEEt!f11FG lhEORMAT10h

' Ning ref ueling information is included in the Monthly Report as requested in an r to EECo dated January 18, 1978:

v h, v onvenience, the information supplied has been enumerated so that each number N')' ct _

_f,Js to ?quivalent notation utilized in the request.

. N name of this facility is Pilgrim Nuclear Power Station, Docket Nurnber 50-293.

'. 'hedaled date for riext afueling shutdown: April 3, 1993 i 3. Scheduled date for restart following next refueling: June 8, 1993  ;

4. Duc to their similarity, requests 4, 5, & 6 are responded to collectivel t. 1er #6, ; '

5. See #6. b o'

6. The new fuel loaded during the 1991 refw iino oci/e was of the same design as lo,ded in the previous outage and consisted et 3r ossemblies.

7. 'a) in te :>80 fuel asremblies in the core. .

(b) There ure 1489 fuel assemblies in the spent fuel pool.

8. (a) The station i.; presently licensed to store 2320 spent fuel assemblies. The actual usaole spent fuel storage capacity is 2320 fuel asse-Slies.

(b) The planned spent fuel storage capacity is 2320 fuel asremb'ies.

9. With present spent fuel in storage, the spent fuel pool now has the capacity tc accommodate an additional 831 fuel assemblies.

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MONTH _Septe:nbe r, 1932_ ,

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELAlED MAINTENANCE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED COMPONENT MALFUNCTION CAUSE SYSTEM LER PREVENT RECURRENCE Under Valve gagged closed Under N/A Salt Motor MO-38'1 shows Operated dual indication Investigation (Temp. Mod 92-20). Investigation Service Valve operator Water '/alve (open/ closed)

MO-7813 when closed. inspected and (SSW) overhauled.

System (PR92-9144)

Area Temper- Stripped terminal Repeated Stripped Terminal Refer to Associated LER Reactor 92-010-00 Core ature Switci. block torquing of for TS-1360-176 LER.

Isolation TS-1360-17C. termination the terminal was replaced.

Cooling point. screw during Associated circuitry (RCIC) (PR92-9145) quarterly was functionally System calibration tested with satis-process. factory result:,.

Stem found Lubricated stem. MOV PM and Votes test N/T Reactar Motor Failed to meet dry. Performed scheduled.

Core Operated Valve stroke timing Spray M0-1400-25B criteria while surveillance performing satisfacterily.

Surveillance 8.5.1.3 (PR92-9179) l -_

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DOCKET NO. 50-293  :

UNIT SHUTDOWNS'AND POWER REDUCTIONS NAME PILGRIM 1 '.

DATE October 14, 1992 COMPLETED BY W. MUNR0 TELEPHONE 508 747-8474 REPORT MONTH August, 1992 METHOD OF LICENSE CAUSE & CORRECTIVE SHUTTING EVFNT SYSTEM COMPONENT ACTION TO PREVENT DURATION I REPORT # CODE 4 CODE 5 RECURRENCE NO. DATE TYPEl (HOURS) REASON DOWN REACTOR l N/A N/A N/A Power reduction 05 9/I3/92 1 0.0 H 4 for main condenser backwash, rcd pattern exchange, and to perforr selective maintenance.

l 3 4&S 2 2 1

F-Admin 1-Manual Exhibit F & H F-Forced A-Equip' Failure Ir.structi^ns for 8-Main or Test G-Oper Error 2-Manual Scram S-Sched 3-Auto Scram Preparat uns of C-Refueling H-Other 4-Continued Data Entry Sheet D-Regulatory Restriction I.icensee Event Report E-Operator Training 5-Reduced Load

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

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