ML20064B385

Monthly Operating Rept for Sept 1990 for Pilgrim Nuclear Power Station

ML20064B385
Person / Time
Site:	Pilgrim
Issue date:	09/30/1990
From:	Richard Anderson, Basilesco G BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-90-120, NUDOCS 9010160291
Download: ML20064B385 (8)

Text

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Pilgnm Nuclear Power Station Rocky Hdi Road -

I Plymouth, Massachusetts 02360 '

October to ,1990-BECo Ltr._ 1 90- 120 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555

{

License No. DPR-35.

Docket No. 50-293

Subject:

September 1990 Monthly Report l 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. .

Station Director-and Vice President, Nuclear Operations GJB/bal

-Attachment cc: Regional Administrator, Region 1 '

U.S. Nuclear Regulatory Commission <

475 Allendale Rd. >

King of Prussia, PA 19406 i

Senior Resident Inspector O

dfW 9010160291 900930 PDR ADOCK 05000293 9 '\

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AVERAGE DAILY UNIT P0llER LEVEL DOCKET NO. 50-293 +

UNIT Pilarim 1-DATE- n-emum, in ioon

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COMPLETED BY G. Bai11esco ~~ R TELEPHONE (508) 747-8S34- I MONTH Sentember 1990 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MHe-Net) (MHe-Net) 1 654 -17 0 2 617 18 0 3 0 19 0 1

4 0 20 0 5 0 21 0 6 0 22 0-7 0 23- 0 8 0 24 0 j 9 0 25 136 10 0 26 502 11 0 27 633  ;

12 0 28 '661 l 13 0 29 504 i

14 0 30 639 i 15 0 31 N/A 1 16 0  !

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. i

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OPERATING DATA REPORT-DOCKET NO.- 50-293' DATE -October 10. 1990 COMPLETED BY G. Basilesco-TELEPHONE (508) 747-8534 R OPERATING STATUS Notes

1. Unit Name Pilarim 1 '

2. Reporting Period .Sentember 1990 l

3. Licensed Thermal Power (MHt) 1998

4. Nameplate Rating (Gross MHe) 678 i

5. Design Electrical Rating (Net MHe) 655 <

6. Maximum Dependable Capacity (Gross MHe) 696

7. Maximum Dependable Capacity (Net MHe) 670

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

1 None

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9. Power Level To Hhich Restricted, If Any (Net MHe) __. None

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

11. Hours In Reporting Period 720.0 6551.0 156119.0  !

12. Number Of Hours Reactor Has Critical 421.6 4986.5 90391.7 i

13. Reactor Reserve Shutdown Hours 0.0 0.0 0. 0 .  !

14. Hours Generator On-Line 189.4 4577.8 86707.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy: Generated (MHH)

17. Gross Electrical Energy Generated (MHH)

.J20904.0 108630.0.

8540448.0 149025360.0 2924890.0 50161714.0 l;

18. Net Electrical Energy Generated (MHH) 104302.0- 2812807.0 48195991.0  !

19. Unit Service Factor 26.3 69.9 '55 5 'i

20. Unit Availability Factor 26.3 69.9 55.5 i

21. Unit Capacity Factor (Using MDC Net) 21.6 64.1 46.1 l

22. Unit Capacity Factor (Using DER Net) - 2 2.1.. 65.6 47.1,

23. Unit Forced Outage Rate 73.7 15.2 13.0

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

None '

a

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) l

> BOSTON EDISON COMPANY .

l PILGRIM NUCLEAR POWER STATION-DOCKET NO. 50-293 0 e Operational Summary for Seotember 1990 l

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The unit-started the month at approximately 100 percent power. At 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br />  !

on 9/2/90, Control room operators observed a slow unexplained increase in i Reactor Vessel water-level. Operators took manual control of the feedwater-Control System attempting to restore water level to normal, When it was  !

determined that feedwater Control could not be reestablished, power was 'l reduced to 60 percent and the reactor was manually scrammed at 2233 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.496565e-4 months <br /> by i placing the Mode Switch in Shutdown. After the shutdown, other equipment problems were experienced-with RCIC, HPCI and RHRS. After maintenance activities were performed, including a modification to the feedwater control system, the reactor was made critical on September 18, 1990 at 0342 hours0.00396 days <br />0.095 hours <br />5.654762e-4 weeks <br />1.30131e-4 months <br />.

Additional maintenance was then performed on the RCIC turbine and RHR HO-1001-50 valve, and on September 25, 1990 the generator was synchronized to the grid at 0106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br />. Power was increased to approximately 100 percent by 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on September 27, 1990. On September 29, 1990 power.was reduced to approximately 50 percent to perform a control rod pattern change. Power was then increased to approximately 100 percent by 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on September 30, 1990 and remained at that-level for the remainder of the reporting = period.

Safety Relief Valve Challenges Month of Seotemhgr 1990 -

Requirement: NUREG-0737 T.A.P. II.K.3.3 '

Date: September 3, 1990 Valve # 203-3B and 3C Reason: Reactor pressure control.

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.

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. 1 REFUELING INFORMATION The following refueling information is included in the Monthly. Report as  !

requested-in an NRC letter to BECo, dated January 18, 1978:

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

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

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

3. Scheduled date for restart following refueling: . Third Quarter 19911 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 refue' ling outage was of the same-l 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 i; 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 in storag'e, the spent fuel pool now has the

capacity to accommodate an additional 1000 fuel r

u mblies.

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Month September 1990 PILGRTM G CLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE ,

SYSTEM COMPONENT MALFUNCTION CAUSE . MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED l PREVENT RECURRENCE LER Feedwater Train "B" Packing Degradation of Repacked valves Refer to associated LFR 90-013-00 (FH) Feedwater leak stem and packing (FV-642 A&B) with LER System Regulating box. improved design.

Valve FV-642 B.

(F&MR 90-276)

Feedwater Startup Feedwater Air leak. Degradation of Repacked valve with Refer to associated LER 90-013 (FH) Regulating Valve internal diaph- live load packing; LER.

System FV-643. rage of the replaced booster (F&MR 90-284) booster relay. relay.

Feedwater Feedwater Reg- - Blown fuse Moisture accum- Replaced fuse and Refer to associated LER 90-013-00 i (FH) ulating Valve ulated in-press- pressure switch: LER.

System Power Supply ute switch from implemented design

. (640-42)- junction box, modification per.

as a result of PDC 90-56. Repaired FV-642 B packing-leak._ ,

packing leak. ,

Reactor RCIC Turbine Turbine-trips Looseness in Overspeed trip mech- Refer to associated LER 90-013-00L '

Core (F&MR 90-285,286) mechanica1' aver- anism disassembled LER.

' speed trip link- and cleaned; linkage Isolation Cooling age. adjusted.

(RCIC)

System Reactor RCIC Injection ' Valve failed . Valve disc . Valve modified to Refer to associated LER 90-013-00 Core Check valve to close. binding due_to reduce binding. LER Isolation 1301-50 loose shaft key. (FRN 90-03-84)

Cooling .

(RCIC)

System

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Month ' September 1990 .' ?

PILGRIM NUCLEAR POMER STATION -

MAJOR SAFETY RELATED MAINTENANCE ~1 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENAfE;E CORRECTIVE ACTION TO ASSOCIATED

_2R_DIENT RECURRENCE LER High HPCI turbine Flow oscill- EG-R hydraulic Needle valve adjust- Refer to associated - LER 90-013-00 Pressure (F&MR 90-291) ations; over- actuator needle ed; diagnostic test- LER.

Coolant speed trip. valve improperly ing on-going.

Injection adjusted; cause (Temporary Modifica-(HPCI) of overspeed- tion 90-31).

System trip under inve- .

stigation.

Residual Shutdown Cooling Valve did not failure of Relay replaced Refer to associated LER 90-013-00

' Heat Suction Isolation respond (open) seal-in relay LER Removal Valve MD-1001-50 to control 16A-K29 (RHR) (F&MR 90-292) switch. (CR-120A)

' System Residual Shutdown Cooling Body to Under Leak sealant compound None . N/A Heat Suction Isolation bonnet leak. investigation (Furmanite)' injected Removal . Valve MO-1001-50 into valve body.

(RHR) (F&MR 90-296)

System '

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-F ~~ " ' " " ' ' * **""~"'~~~~'~"# ~ L- - - - - - ~ ~ - - - ' - ~ - - -

UNIT SHUTDONNS AND PONER REDUCTIONS DOCKET NO. 50-293. ..~

NAME Pilarir] - --

DATE october 10. 1990- ~ ' -! ;

COMPLETED BY G. Bas 11esco'- ' '- .._

TELEPHONE (508) 747-8534' REPORT MONTH September 1990 METHOD OF LICENSE CAUSE & CORRECTIVE. ,

NO. DATE TYPE I DURATION (HOURS) REASON 2

-SHUTTING DONN REACTOR 3 EVENT.

-REPORT #

SYSTEM C00E4 g ENT ACTION TO PREVENT' RECURRENCE 12 09/02/90 F 530.6 A 2 90-013-00 SJ FU Failure to maintain reactor water level.-  !

PDC 90-56. implemented.-

13 09/29/90 S 0.0 -

5 N/A Power. reduction to' perform control rod-pattern change.

1 2 2 3 4&S -

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

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

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