BECO-92-062, Monthly Operating Rept for May 1992 for Pilgrim Nuclear Power Station

Monthly Operating Rept for May 1992 for Pilgrim Nuclear Power Station

ML20210D852
Person / Time
Site:	Pilgrim
Issue date:	05/31/1992
From:	Boulette E, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-92-062, BECO-92-62, NUDOCS 9206180128
Download: ML20210D852 (7)

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. !S ROSTON EDISON

. rogeim Nude row bution Hocky Hill kosd rlymOuth, Massachuntts 02300 E. Thomas Boulette, PhD Vete hesident Nudp operstons and Station Dwoctor June 11 , It

• BECo Ltr. #92 , t U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. OPR-35 Docket No. 50-293-

Subject:

Hay 1992 Honthly 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.

h, tthMu] O LA. (i L E. Thomas Boulette HJH/bal-Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Hr. R. B. Eaton Div. of Reactor Projectr I/II

• Office of NRR.- USNRC One Hhlte Flint North - Hail Stop 1401 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector

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4 6YIMGLDA11LUNIT P0HER LEVEL DOLKET NO. SQ-2SQL_

UNIT Pil2 Tim 1 DATE ___ June 11. 1992 COMPLETED BY _&.Hunro TELEPHONE (508) 74L-B.42L 4

HON 1H .May 1992 DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HHe-Net) (HHe-Net) 1 ,, 666 17 665 2 665 18 665 3 .. 6 6 5_ __ 19 664 4 664 20 665 -

5 664 21 666 6 6E5 22 665 7 665 23 61.4 8 663 24 663 9 662 25 660 .

101 520 26 660 11 664 27 661 12 663- 28 659 13 664 29 659 14 665 30 608 15 665 31 605 16 665 This format lists the average daily unit power level in HHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

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'. OPERATING DATA REPORT

. DOCKET NO. 50-193__

DATE June 11. 1992 COMPLETED BY H. Hunro TELEPHONE _(508) 747-8474__

OPERATING STAT 01 Notes

1. Unit Name . Pilarlp 1

2. Reporting Period Hav 1992

3. Licensed Thermal Power (HHt) . 1901

4. Nameplate Rating (Gross HHe) _. 678

5. Design Electrical Rating (Net HHe) 655

6. Maximum Dependable Capacity (Gross HHe)___h94

7. Maximum Dependable Capacity (Net HHe) 670

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

None

9. Power Level To Hhich Restricted, If Any (Net H.le) None

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

11. Hours In Reporting Period 744.0 _ 3647.0 1707351 0

12. Number Of Hours Reactor Has Critical 744.0 32692 1 10163Q22

13. Reactor Reserve Shutdown Hours 0.0 __ _j) JD Q10

14. Hours Generator On-Line 744.0 32122) , 97720 4

15. Unit Reserve Shutdown Hours 0.0 _.__Q10 Q10

16. Gross Thermal Energy Generated (HHH) 1468728.0 6286464.0j69990944.0

17. Gross Electrical Energy Generated (HHH) 506450.0 2171600.0 $7378014.0

18. Het Electrical Energy Generated (HHH) _4A1115.0 2090793.0 55141741.0

19. Unit Service factor 100.D 88.2 57 2

20. Unit Availability Factor _ 102.0 88.2 57.2

21. Unit Capacity factor (Using HDC Net) 97.8 85.6 48 2

22. Unit Capacity factor (Using DER Het) __

100.0 87.5 49 3

23. Unit Forced Outage Rate 0.0 11.8 12.6

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

Midcycle outaae - October 1992 Aontg1]mately 35 days

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

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. BOST0h ED! SON COMPANY PILGRIH NUCLEAR POWER STATION DOCKEi NO. SQ-EJ_

Ooerational Summary for Hav 1992 The unit started the reporting period at approximately 100 percent core I thermal power (CTP) where it was maintained until May 10 when power was ,

reduced to approximately S2 percent CTP to perform a thermal backwash of the '

main condenser. The weekly control rod exercise was performed while power was  !

reduced. Power was restored to 100 percent CTP by 2152 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.18836e-4 months <br /> on May 10, and was maintained until May 74 when power production decreased slightly resulting from macro fouling of the main condenser. On May 30 power was reduced to approximately 47 percent CTP to perform a backwash of the main condenser. The weekly control rod exercise was performed while power was reduced. On Hay 31 at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> the unit attained 100 percent CTP where it was maintained for the remainder of the reporting period. Hinor power reductions were initiated on May 2, 16 and 23 to perform the weekly control rod exercises.

Safety Relief Valve Challenges Month of May 1992 Requirement: NUREG-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. 8ECo ltr. #81-01 dated 01/05/81.

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!!EFUELING INFORMATION The following refueling information is included in the Holthly Report as requested in an NRC letter to BECo, dated January 18, 1978:

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

1. The name of this facility is ?11 grim Nuclear Power Station, Docket Number 50-293.

2. Scheduled date for next refueling shutdown: April 3, 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 #6.

5. See #6.

6. The new fuel loaded during the 1991 refueling outage was of the same design as loaded in the previous outage and consisted of 168 assemblies. *

7. (a) There are 580 fuel assemblies in the core.

(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. Hith present spent fuel i n storage, the spent fuel pool now has the capacity to accommodate an additional 831 fuel assemblies.

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u_____________ _ _ _ _ _ _ _ _ . _ _ _ _ . _

Month May 1992 -

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE .

SYSTEM COMPONENT MALFUNCTION' CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED PREVENT RECURRENCE LER 4

Diesel "B" Emergency Check valves stuck Corrosion Chr.k valves disas- PDC 91-08 Diesel Gen- None Generat- Diesel Gener- in closed position. buildup in sembled, cleaned, erator Air Start Piping ors and ator Check (PR 92-9046). check valves. reassembled and to be implemented during Auxili- Valves 47CK-3018 . reinstalled. MOD-9 .

aries and 47CK-301C System on Turbo Assist

' Receiver inlets (T-1508 and T-1518).-

Diesel "B" Emergency Safety relief Incorrect Starting air comp- Implementation of None Generat- Diesel Generator valve lifted and . application of ressor pressure PDC 91-08 will replace ors and Safety Relief discharged at Crosby type switch-(PS-45668) all the air system Auxilia- Valve. 250 PSIG when JMBU relief was recalibrated at relief valves with a ries (PSV4581B) rated at 275 psis valve in air the lower range of type more applicable System (PR 92-9047) system (Refer- its setpoint toler- to the system Ence Information ence to prevent requirements.

Notice. inadvertent lifting (IN 90-18) of the relief valve.

Salt "A" SSH pump Position Corrosion and Operator removed N/A N/A Service discharge indicator wear. and replaced in kind.

Water valve operator. loose.

(SSH) (29-H0-3815).

System Salt Vent valve. Leaking by seat Normal wear. Vent valve removed N/A N/A Service (29-H0-3847) following and replaced in Hater venting kind.

CSSH) operation.

System

UNIT SHUTD0HNS AND POWER REDUCTIONS DOCKET NO. 50-293 Pilcrim 1 NAME '

DATE June 't. 199?

• OOMPLETED SY H. Munro TELEPHONE (508) 747-8474 REPORT HONTH May 1992 .

METHOD OF LICENSE CAUSE & CORRECTIVE SLTTING EVENT COMPONENT ACTION TO PREVENT DURATION SYSTEg NO. DATE TYPEI (HOURS) REASON 2 DOWN REACTOR 3 REPORT-# CODE CODE 3 RECURRENCE i

5 N/A N/A N/A Power reduction due to i 04 5/10/92 5 0.0 N/A thermal backwash ot' Main Condenser.

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2 3 4&5 1 2 F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet 5-Reduced Load Licensee Event Report E-Operator Training

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