ML20245J340

Monthly Operating Rept for Jul 1989 for Pilgrim Nuclear Power Station

ML20245J340
Person / Time
Site:	Pilgrim
Issue date:	07/31/1989
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-122, NUDOCS 8908180004
Download: ML20245J340 (7)

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Pilgrim Nuclear Power station .-

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Plymouth, Massachusetts 02360 K. L. HighflH L

' station Director .

August II, -1989 BECo Ltr.. 489 122 U.S.-Nuclear. Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293 Subject': ' July 1989 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.

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

King ~of Prussia, PA 19406 Senior Resident Inspector L

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-l- l: [ AVERAGE DAILY UNIT POWER LEVEL-

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DOCKET NO. 50-293-m J. *-

UNIT Pilarim 1 DATE Aum2st 11.1989 -] '

COMPLETED BY- H. Munro TELEPHONE (508) 747-8474 MONTH' Jul'y 1981 I

. DAY: AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL l' , (MHe-Net) (MHe-Net) 1 117 17 240

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2 193 18 132

.. 3 198 19 0 .

1 -

1 4 213 20 0 5 274 21 0 6 299- 22 0 7 304 23 0 8 _

301 24 0-9 294 25 0 10 304 26 69 11- '305 27 178 12 294 28 187 13 291 29 252-l-

14 278 30 304 15: 301 31 304 16 304 This format lists- the average daily unit power level in MHe-Net for each day in the reporting month, computed to the nearest whole megawatt.

~0PERATING DATA REPORT DOCKET NO. 50-293 DATE a,,,,,+~

,, , ano COMPLETED BY ~ W: Munrof ~' '

TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. Unit.Name Pilorim 1

2. Reporting Period July 1989

3. Licensed Thermal Power (MWt) 1998

4. Nameplate Rating (Gross MWe) 678

5. . Design Electrical Rating (Net MWe) 655-

6. Maximum Dependable Capacity (Gross MWe) 690

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) 50% Core Thermal Power

10. Reasons For Restrictions, If Any Regulatory Restriction. Confirmatory Action Letter 86-10. Power Ascension Phase.

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 5087.0 145895.0

12. Number Of Hours Reactor Was Critical 561.8 2790.0 82581.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 547.0 2156.9 79403.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal' Energy Generated (MWH) 482760.0 1295448.0 136295328.0

17. Gross Electrical Energy Generated (MWH) 150540.0 374010.0 45818614.0 18.' Net Electrical Energy Generated (MWH) 142467.0 347998.0 44023427.0

19. Unit Service Factor 73.5 42.4 54.4

20. Unit Availability Factor 73.5 42.4 54.4

21. Unit Capacity Factor (Using MDC Net) 28.6 10.2 45.0 22.' Unit Capacity Factor (Using DER Net) 29.2 10.4 46.1

23. Unit Forced Outage Rate 25.9 37.0 13.0

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

Maintenance outaae. October 1.1989 for a duration of 30 - 42 davs (scooe under review).

25. If Shut Down At End Of Report Period, Estimated Date of Startup -

N/A .

!-> 26. Units In Test Status (Prior to Commercial Operation): N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

4- . BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 4 -Operational Summarv for July 19'89 The reactor remained critical, in the Startup mode, until 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> on.

. July l',1989 when the Mode Switch was placed in' the Run position. At 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> the turbine generator was synchronized to the grid. The unit remained on line until July 18,=1989 when the unit was manually scrammed at 1036 hour0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.94198e-4 months <br />s-

,. -due to loss of main condenser vacuum which occurred while changing the steam jet air. ejector line up. The unit remained'in cold shutdown, to remove mussels from the main condenser water boxes and both:the RBCCH and TBCCH.

system piping, until 0047 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> on July 26, 1989 when the reactor was made critical. The turbine generator-was synchronized to the grid on July 26, 1989 at 0936 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.56148e-4 months <br />, and remained on line operating at approximately 50. percent rated thermal power for the remainder of the reporting period.

Safety Relief Valve Challenges Month of July 1989 Requirement: NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during the month.

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

1tr. #81-01 dated 01/05/81.

, 1; g J; D REFUELING INFORMATION

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' The following refueling _information is included in the Monthly 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. i L 1. The' name of this facility is Pilgrim Nuclear Power Station, Docket Number L 50-293.

2. Scheduled date for next Refueling Shutdown: 'First Quarter 1991

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

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

5. See #6.

l 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 core.

(b) There are 1320 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 assemd :es.

9. With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies.

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