ML20072A710

Monthly Operating Rept for July 1994 for Pilgrim Nuclear Power Station

ML20072A710
Person / Time
Site:	Pilgrim
Issue date:	07/31/1994
From:	Munro W, Olivier W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-084, 94-84, NUDOCS 9408150166
Download: ML20072A710 (7)

Text

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Tech. Spec. 6.9.A.2 k$

Boston Edison Pdgnm Nuclear Power Station Rocky Hdi Road Plymouth, Massachusetts 02360 L. J. Olivier Wcu President Nuclear Operations August 5, 1994 ami station ovector BECo Ltr. #94- 084 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 JULY 1994 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, e a i

. W

.J. Olivier WJM/ lam /9458 l

Attachment I

cc: Mr. Thomas T. Martin l Regional Administrator, Region I l U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector

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9408150166 940731 A)('

f PDR ADOCK 05000293

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. l OPERATING DATA REPORT l

DOCKET NO. 50-293  !

DATE 8/5/94 COMPLETED BY: W. Munro ,

TELEPHONE (508) 830-8474 QPERATING STATUS NOTES

1. Unit Name Pilgrim I

2. Reporting Period July 1994

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) E2a

5. Design Electrical Rating (Net MWe) HEE

6. Maximum Dependable Capacity (Gross MWe) 116

7. Maximum Dependable Capacity (Net MWe) E20

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

NONE

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

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

11. Hours in Reporting Period 744.0 5087.0 189719.0

12. Hours Reactor Critical 744.0 4794.0 117735.5

13. Hours Reactor Reserve Shutdown DmQ qQ Q2

14. Hours Generator On-Line 2.44.0 4674.8 113463.8

15. Hours Unit Reserve Shutdown 0.0 QQ QQ

16. Gross Thermal Energy Generated (MCI) 1479816.0 8933184.0 200077920.0

17. Gross Electrical Energy Generated (MWH)S05280,Q 3061540.0

_ 67707474.Q .

18. Net Electrical Energy Generated (MWH) 486389.0 2946522.0 65080216.0

19. Unit Service Factor 100.0 91.9 59,,8

20. Unit Availability Factor 100.0 2121 59.8

21. Unit Capacity Factor (Using MDC Net) 97,6 HE 1 51.2

22. Unit Capacity Factor (Using DER Net) 99,,8 88.4 52,4

23. Unit Forced Outage Rate QH 1.1 11.5

24. Shutdowns Scheduled Over Next 6 Months IType, Date, and Duration of Each) - MCO-10 October 1994 30 Days

25. If Shutdown at End of Report Period, Estimated Date of Startup - Unit Operating l

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I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 DATE: 8/5/94 COMPLETED BY: W. Munro TELEPHONE: (508) 830-8474 MONTH duly 1994 ,

I DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net) 1 660 17 652 2 660 18 653 3 659 19 648 4 657 20 646 5 658 21 654 6 657 22 656 7 657 23 659 8 655 24 659 9 642 25 657 10 595 26 657 11 658 27 658 12 657 28 658 13 658 29 659 14 654 30 659 15 655 31 658 16 654 This format lie ts 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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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 OPERATIONAL

SUMMARY

FOR JULY 1994

, The unit started the reporting period at 100 percent core thermal power (CTP) where it was essentially maintained until July 9, 1994. On July 9, 1994 at approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> the plant commenced a power reduction to 50 percent CTP to facilitate a backwash of the main condenser. Following completion of the backwash a power increase was commenced, and at 0637 hours0.00737 days <br />0.177 hours <br />0.00105 weeks <br />2.423785e-4 months <br /> on July 10, 1994, the plant attained 100 percent CTP where it was essentially maintained until July 17, 1994. On July 17, 1994, power was

, briefly reduced to approximately 98 percent CTP in response to problems with the " EPIC Computer". On July 19 and 20, 1994, unusually high inlet

, water temperature adversely affected main condenser back pressure, requiring the plant to trim power to maintain adequate vacuum in the main condenser. At 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br /> on July 20, 1994, the plant attained 100 percent CTP where it was essentially maintained throughout the remainder of the reporting period.

SAFETY RELIEF VALVE CHALLENGES MONTH OF JULY 1994 /

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

There were no safety relief valve challenges during the 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).

Reference BECo Ltr. #81-01 dated January 5, 1961.

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l REFUELING INFORMATI.QH

' l l The followin'g refueling inf ormation is included in the Monthly Report as l 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.

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1. The name of this facility is Pilgrim Nuclear Power Station, Docket ]

Number 50-293.  ;

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2. Scheduled date for next refueling shutdown: April 1, 1995.

3. Scheduled date for restart following next refueling: May 26, 1995. j l

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

5. See #6. l l

6. The new fuel loaded during the 1993 refueling outage was of the same design as loaded in the previous refueling outage and consisted of 140 assemblies. l

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

l (b) There are 1629 fuel assemblies in the spent fuel pool.

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8. (a) The station is presently licensed to store 3859 spent fuel )

assemblies. The actual usable spent fuel storage capacity is l 2320 fuel assemblies, f

(b) The planned spent fuel storage capacity is 3859 fuel assemblies.

9. With present spent fuel in storage, the spent fuel pool now has the (

capacity to accommodate an additional 691 fuel assemblies. l

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MONTH JULY 1994 .

PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE -

CORRECTIVE ~

ACTION TO ASSOC SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE PREVENT RECURRENCE LER NO MAJOR SAFETY RELATED MAINTENANCE WAS COMPLETED DURING THE REPORTING PERIOD.

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t UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-293 .

DOCKET NO: 50-293 -

NAME: Pilcirim I .

DATE: 8/5/94 COMPLETED BY: W. Munrd.

TELEPHONE: (508) 830-8474 REPORT MONTH: Julv 1994 METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVEh"r NO. DATE 1 (HOURS) 2 REACTOR REPORT 4 5 RECURRENCE i

THERE WERE NO UNIT SHUTDOWNS OR REPORTABLE POWER REDUCTIONS DURING THE REPORTING PERIOD.

l 1 2 3 4&5 i .

F-Forced A-Equip ?=1ilure 1-Manual Exhibit F & H l S-Sched B-Main or Test 2-Manual Scram Instructions for l C-Refueling 3-Auto Scram Preparations of ,

4 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)

F-Admin '

G-Operator Error H-Other l

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