ML20005G802

Monthly Operating Rept for Dec 1989 for Pilgrim Nuclear Power Station

ML20005G802
Person / Time
Site:	Pilgrim
Issue date:	12/31/1989
From:	Highfill K, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-09, 90-9, NUDOCS 9001230108
Download: ML20005G802 (7)

Text

P o

o 90

~

SOSRWEM5(W Pilgrim Nuclear Power station i

Rocky Hill Road Plymouth, Massachusetts 02360 j

p K.L.HighflN station o rector g

January-12, 1990 L

BECo Ltr. #90- 09

[

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293-

Subject:

December 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.

'. L. 'H HJM:bal Attachment cc: Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 i

Senior Resident Inspector i

i b" g D.

gynm ung fopKW19 p4

AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. _

50-293 UNIT Pilcria 1 DATE u m,, e.1, io icon l

00MPLETED BY W. NUnro ' ~ ~ ' '

l TELEPHONE (508) 747-8474-MONTH December 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 625 17 630 2

624 18 633 3

623 19 634 4

626 20 636 5

626 21 637 6

576 22 634 7

397 23 634 8

83 24 636 9

0 25 637 10 0

26 623 4

11-0 27 519 12 60 28 608 13 451 29 3 53 14 626 30

_ gi.6 l

15 633 31 657 16 628 l

This format lists the average daily unit power level in MHe-Net for each day j

in the reporting month, computed to the nearest whole megawatt.

l l

l l

L j

OPERATING DATA REPORT DOCKET NO.

50-293 DATE January 12. 1990 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 j

OPERATING STATUS Notes 1.

Unit Name Pilarim 1 2.

Reporting Period December 1989 3.

Licensed Thermal Power (MHt) 1998 4.

Nameplate Rating (Gross MWe) 678 5.

Design Electrical Rating (Net MHe) 655 6.

Maximum Dependable Capacity (Gross MHe) 690 l

7.

Maximum Dependable Capacity (Net MHe) 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 MHe)

None i

10. Reasons For Restrictions, If Any N/A i

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 8760.0 149568.0

12. Number Of Hourt Reactor Has Critical 645.8 5613.8 85405.2

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 i

14. Hours Generator On-Line 635.9 4900.0 82129.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MHH) 1159920.0 5485032.0 140484912.0

17. Gross Electrical Energy Generated (MHH) 399720.0 1792220.0 47236824.0 l

18. Net Electrical Energy Generated (MHH) 384101.0 1707755.0 45383184.0

19. Unit Service Factor 85.5 55.9 54.9

20. Unit Availability Factor 85.5 55.9 54.9

21. Unit Capacity Factor (Using MDC Net) 77.1 29.1 45.3 l

22. Unit Capacity Factor (Using DER Net) 78.8 29.8 46.3 i

23. Unit Forced Outage Rate 14.5 24.1 12.9 l

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

Maintenance Outaae March 9.1990 for a duration of 39 days.

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

26. Units In Test Status (Prior to Cc wrcial Operation):

N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) l 1

I

BOSTON EDISON COMPANY i

PILGRIM NUCLEAR POWER STATION

=,

DOCKET NO. 50-293 l

Ooerational Summary for December 1989 The unit remained on line at approximately 94 percent thermal power until December 6, 1989 when at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, while increasing power, the "A" i

recirculation pump tripped reducing power to approximately 38 percent.

Following maintenance to the "A" recirculation pump MG set the power was increased to approximately 94 percent. At 0308 hours0.00356 days <br />0.0856 hours <br />5.092593e-4 weeks <br />1.17194e-4 months <br /> on December 8, 1989 a l

full reactor scram occurred due to a pressure pertubation to the reactor protection system (RPS) low water level instruments.

This occurred as technicians were restoring the local level transmitter to service following calibration.

The unit was brought to cold shutdown condition after an unsuccessful attempt to repair a faulty ball valve in the traversing incore probe (TIP) system. At 0526 on December 12, 1989, following successful testing of the "A" recirculation pump MG set and replacement of the TIP ball valve, the reactor was made critical, and at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> the turbine generator was synchronized to the grid.

The unit remained on line maintaining approximately 96 percent thermal power when,following a power reduction on December 26, 1990 to enable a rod pattern change, power was again increased i

and the unit remained on line at approximately 99 percent thermal power for

~

the remainder of the reporting period, i

i Safety Relief Valve Challenges Month of December 1989 1

Requirement:

NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve challenges during the reporting period.

An SRy challenge is defined as anytime an SRV has received a signal to operate i

via reactor pressure, auto signal (ADS) or control switch (manual).

Ref. BECo l

Ltr. #81-01 dated 01/05/81.

L i

l l

1

---c.----

w--

,www

---,e

REFUELING INFORMATION j

The following refueling information is included in the Monthly Report as 3

requested in an NRC letter to BECo dated January 18. 1978 4

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 Pilgrim Nuclear Power Station, Docket Number i

50-293.

2.

Scheduled date for next Refueling Shutdown: Second 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.

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 assemblies.

f 9.

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

1 l

a

._. ;gn PILGRIM NUCLEAR PONER STATION 4

MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO' ASSOCIATED PREVENT RECURRENCE LER Traversing TIP ball Ball valve was Damaged Ball valve and solenoid Refer to associated LER 89-037-00 In-core valve.

partially open valve stem.

actuator were replaced. 'LER.

Probe (TIP)

(No. 45-300A) when it was Valve was leak rate System thought to be tested.in accordance in the closed.

with Procedure 8.7.1.5 position.

(F&MR 89-443 i

(F&MR 89-463)

Re:ctor Floor exhaust Damper (AON-90) Rubbing of the Damper operation Refer to associated LER 89-038-00 Building /

ventilation did not comple-damper blades corrected by pressing LER.

Secondary damper tly close on and stationary the damper edge seals-Containment (A0N-90).

isolation edge seals.

outward, per vendor System signal instructions.

l (F&MR 89-472) e d

s-n s.e

,m,-

,y.,-

e,. - -.,,

i.4

.ww.

.,w.

..-,.4 m

,,-e-

-.c.

.1

___y_-..

ueww. -. =

..m_-

UNIT SHUTDONNS AND PONER REDUCTIONS-DOCKET NO. 50-293 NAME P11 erie 1 DATE Jcnuary 12. 1990 -

COMPLETED BY M. Munro TELEPHONE (508) 747-8474 REPORT MONTH December 1989 i

METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT

.SYSTEY g ENT ACTION TO PREVENTIVE NO.

DATE TYPEI (HOURS)

REASON 2 DONN REACTOR 3 REPORT #

CODE' RECURRENCE-15 12/7/89 0.0 N/A Power reduction due to "A" Recirculation pump trip. Troubleshoo-ting "A" Recirculation Pump MG Set.

16 12/8/89 F

108.1 H

3 89-038-00 JC LI Minor Hydraulic Trans-1ent caused false Rx vessel water level

-signal. Local level indicator calibrated..

89-037-00 IG ISV TIP machine No. 1 Ball valve inop. Ball valve replaced 1

2 2

3 45 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 E-Operator Training 5-Reduced Load Licensee Event Report j

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

I l

t l

t i

t o

e

-. - -. ~. - -

e--

.--s,

. w.

,-w

+. -. ---....,,

.a+-

.,r.--,e-%-.

w~.,,w--

,,____.__u-a,a,m_.-_._m__.m_m... _ _ -. _ _ -. _ _. - -

-