ML20070A559

Monthly Operating Rept for Dec 1990 for Pilgrim Nuclear Power Station

ML20070A559
Person / Time
Site:	Pilgrim
Issue date:	12/31/1990
From:	Richard Anderson, Munro W BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-003, 91-3, NUDOCS 9101230211
Download: ML20070A559 (7)

Text

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Ptigrim Nuclear Power Station

Rocky Hill Road Plymouth, Man,chusetts 02360 JanJary 14, 1991 BECo Ltr. #91-003-U.S. Nuclear Regulatory Commission Attention:- Document Control Desk Hashington, DC 20555 i License No. DPR-35 Docket No. 50-193 ->

Subject:

December 1990 Honthly Report i

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. -1 dd. dro R.'A.Ander;k,) M M.

son a Station Director and Vice President, Nuclear Operations HJM/bal-Attachment-cc:-Regional Administrator, Region.1 U.S. Nuclear Regulatory Commission-

-475 l All endal e . Rd.

King of Prussia, PA 19406 Senior Resident. Inspector a.

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9101236211 901231 /

_PDR ADOCK 05000293 V R PDR i

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t AVERAGE DAILY UNIT P0HER LEVEL l

'2' ' 50-293 DOCKET NO.

UNIT Pilarim i +

DATE January 14.-1991 COMPLETED BY H. Munro

-TELEPHONE (508) 747-8474 HONTH Qecember 19_90 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-

'(MHt Net) (HHe-Net).

1. 661 17 663 2 662 18 664 3- 662 19 664

'41 662 20 664 5 663 21 664

-6 663 22 661-7: -662 23- 663 8- 295 24 663 9; 377 25 664-10 578 26- ~664

'll- 660 -27 665 ,,

m 12, 664 28 664

'13; 664 29, -663L

,14- 663- 30 644

-15~ 663 31' -489 16' 664 This; format lists the average daily unit power level 11n MHe-Net -for each day in the reporting month,: computed to the nearestLwholef megawatt..

1

OPERAT8NG DATA REPORT DOCKET NO. 50-293 DATE January 14. 1991 COMPLETF.D BY H. Munro TELEPHONE (508) 747-8474 OPERATING STATUS-Notes

1. Unit Name Pilarim 1

2. Reporting Period December 1990

3. Licensed Thermal Power (MHt) 1998

4. Nameplate Rating (Gross HHe) 678

5. Design Electrical Rating-(Net HHe) , 65.5

6. Maximum Dependable Capacity (Gross MWe) 696

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 P. lI5werLevelToWhichRestricted,IfAny(NetMHe) None

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

11. Hours In Reporting Period 744.0 8760.0 152328.0

12. Number Of Hours Reactor Has Critical 744.0 7195.5 92600.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 00

.14. Hours Generator On-Line 744.0 6786.8 -88916.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross-Thermal Energy Generated (MHH) 1421016.0 12856584.0 1.53341496.0

17. Gross Elec'crical Energy Generated (HHH) 489220.0 4410690.0 51647514.0

18. Net Electrical Energy Generated (HHH) 470932.0 _d243224.0 _12526408.0

19. Unit Service Factor 100,0: 77.5 56.2

20. Unit Availability Factor 100.0 77.5 56.2

21. Unit Capacity Factor (Using HDC Net) 94.5 72.3 46.8

22. Unit Capacity Factor (Using. DER Net) 96.6 74.0 47.9

23. Unit Forced Outage Rate 0.0 _

10.8 12 6

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

Refuelina Outaae No. 8. Acril 1991.~anoroximatelv 70 days

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 i: Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

BOSTON ED8 SON COMPANY

-PILGRfH NUCLEAR POWER STATION

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DOCKET NO. 50-293 i

Ooerational Summary for December 1990 The unit started the reporting period at'approximately 100 percent power and -

remained at that level unttl December 8, 1990 when a power reduction to 50 percent was made to conduct a condenser backwash and perform a control rod pattern exchange. While down in power it was observed that core thermal

! limit, MFLPD (Haximum Fraction of Limiting Power Density) was greater than allowed' by Technical Specification. A six (6) hour action statement to correct-the condition or to adjust the APRH scram and rod block setpoint was started. Rod pattern changes to address the MFLPD condition were unsuccessful, and-at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> a Limiting Condition of Operation was entered, to be below 25 percent power within-the next four (4) hours. By 1723 hours0.0199 days <br />0.479 hours <br />0.00285 weeks <br />6.556015e-4 months <br /> on December 8. 1990 reactor power was-less than 25 percent. At 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> on December 9,1990 HFLPD was acceptable and a power increase was started. The unit reached 100 percent power at 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br /> on December 11, 1990 and remained at-that level until December 30, 1990 when a leak was discovered on a one-inch

-line off of the "Cd Reactor Feed Pump (RFP) suction piping. This necessitated a power reduction to 75 percent to remove the "C" RFP from service. The unit-ended the reporting period at 75 percent power.

Power reductions to 90 percent were performed on December 1, 15, 22 and 29 for control rod exercising.

Safety Relief Valve Challenges Month of December 1990

-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. BECo ~

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

._ m.m . _ _ . ._. . _. . ....._.-_ _ _ _ _ _ _ .._.___.. _ ._. _ _ . _ . _ . _ _ _ . . .

. L'.: Rff9ELING INFORMATION 1

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

1. The name of this facility is Pilgrim Nuclear Power Station, Dvhet Number 1 50-293. .l

2. Scheduled date for-next Refueling Shutdown: Second Quarter 1991 i

3. -Scheduled date for restart following refueling: Third 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 i assemblies.- The actual usable spent fuel storage capacity is 2320.

fuel assemblies.

(b) .The planned spent fuel storage capacity is 2320 fu'el assemblies.

l9. 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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-Month L-December 1990 PILGRIM NUCLEAR P0HER' STATION- <

-MAJOR SAFETY RELATED MAINTENANCE-SYSTEM COMPONENT. MALFUNCTION. GA_QSE . MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED .

-PREVENT RECURRENCE- LER-

' Salt .SSH Pump "E" . Low discharge. Degraded pump Rebuilt pump bowl Analysis of wear rings N/A' Service P208E head? wear rings assembly.-' by NED in progress. ,

Hater .

(SSW) ' -Scheduled replace-- Inspection 'of column ~l System ment of pump / column for degredation after ,

assembly.le: Replaced six years of service.

seven (7) spider bearings, one (1) .

line shaft, one (1) l head ~ shaft, pump motor overhauled'by manu-facturer (Hestinghouse).

Implemented. Plant -

Design Change'90-12 Phase 3; Removed tie rods;'. replaced upper &

intermediate column

. sections:with new mat-erial design,'and rep-

, laced lower column-  :

.section with existing -l j naterfal design.

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UNIT SHUTDOHNS AND POWER REDUCTIONS DOCKET NO. 50-293 -

$ NAME Pilarin 1 ,

DATE January 14, 1991 -

COMPLETED BY H. Munro -

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TELEPHONE (508) 747-8474 '

REPORT HONTH December 1990 METHOD OF LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEg ENT ACTION TO PREVENT NO. DATE TYPEI (HOURS) REASON 2 DOWN REACTOR 3 REPORT # CODE COMyE COD RECURRENCE 15 12/08/90 S 0.0 N/A 5 N/A N/A N/A Power reduction for rod pattern exchange, condenser backwash and maintenance in the condenser bay.

16 12/08/90 F 0.0 D 5 N/A N/A N/A Power reduction to clear LOO condition regarding MFLPD.

17 12/31/90 F 0.0 N/A 5 N/A N/A N/A Power reduction to make repairs on "C" Reactor Feed Pump suction line.

1 2 2 3 4&5 F-Forced A-Equip Failure F-Admin 1-Manual. Exhibit F & H S-Sched B-Haint 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

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

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