BECO-LTR-91-132, Monthly Operating Rept for Sept 1991 for Pilgrim Nuclear Power Station

Monthly Operating Rept for Sept 1991 for Pilgrim Nuclear Power Station

ML20085E995
Person / Time
Site:	Pilgrim
Issue date:	09/30/1991
From:	Richard Anderson, Munro W BOSTON EDISON CO., PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR-91-132, NUDOCS 9110210321
Download: ML20085E995 (7)

Text

- _ _ _ - _ _ _ _ _

f e

BOSTON EDISON Pilgrim Nuclear Pcwer Station Rocky Hi'l Road Plymouth, Massachusetts o2360 be^dEIe*n't$"

October 11, 1991

['u'[5L d'p'l,'Ln, BECo Ltr. #91-132 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20'iS5 License No. DPR-35 Docket NL 50-29L

Subject:

September 1991 Monthly Report

Dear Sir:

In accordance with PNPS Tc:hr cal Specification 6.9.A.2, a copy of the Operational Status Summary for h igrim Nuclear Power Station is attached for your information and planning. Should you have any questions concerning this report please contact me directly.

L jf N

R'.A. Anderson

\\/

HJH/bal Attachment cc: Mr. Thomas T. Martin Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale RJ, King of Prussia, PA 19406 Mr. R. B. Eaton a

Div. of Reactor P'ojects I/II Office of HRR - UtNRC One White Flint North - Mail Stop 14D1 11555 Rockville Pile Rockville, MD 20852 Senior Resident Inspctor t

910930 F

gnonom

/)/ (I gen nuocxosoog.jj3

~. _..u

8VUBGLD&lLLUHli P0HER LEVEL DOCKET NO.

50-293 UNIT PilgrJm 1 DATE COMPLETED BY _1L_)Junro TELEPHONE

_150311.4Z-33]1, HONTH Seticabar_1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net)

(RHe-Net) 1 645 17 E62 2

658 18 661 3

657 19 663 4

65B 20 661 5

656 21 66L 647 22 663 6

7 434 23 662 8

590 24 6ft0 9

64B 25

_t02 10 659 26 662 11 659 27 IE4 12 650 28 664 13 658 29 663 14 549 30 69 15 650 31 N!A 16 661 This format il$ts the average daily unit power level in HHe-Net for each day in the repo-ting month, computed G., the nearest whole megawatt.

l

OPERATING DATA REPORT DOCKET NO.

50-293 1

DATE COMPLETED BY,L _Bynto TELEPHONE

_(SDQL141-BAL4_

OK! BURG _SIAIUS Notes 1.

Unit Name Pilgrim 1 2.

Reporting Period _Siple.tnbat_1931 3.

Licensed Thermal Power (MWt) 1990 4.

Nameplate Rating (Gross HWe) 018 5.

Design Electrical Rating (Net HWe) _.

655 6.

Maximum Dependable Capacity (Gross MWe) 695 7.

Maximum Dependable Capacity (Net MWe)

_610 8.

If Changes Occur in Capad ty Ratings (Items Nutr.ber 3 Througn 7) Since Last Report, Give Reasons:

JNne 9.

Power Level To Which Rest'Eicted, If Any (Net HWe)

Hone

~

10. Reasons for Restrictions, It Any N/A

^

This Month 1Edo-DAtt CumulA11Ye

11. Hours In Reporting Period 12Q,.0 655LD 10aB19J

12. Number Of Hours Reactor Was Critical 726.0 40fL2 9fffL3

13. Resctor Reserve Shutdown Hours 0.0 LD 00 2

14. Hours Generator On-Line

___Z202 0 392L2' 92S E 3'

15. Unit Reserve Shutdown Hours DJ 0.0 OJ

15. Gross Thermal Energy Generated (MWH) 1401ABLO

_ll3ElLD 16041951L.0

17. Gross Electrical Energy Generated (HWil)

_403040J

_lAA3380J _51090B94_&

18. Net Ciectrical Energy Generated (HWil) 46491LD

_ZHQ51.dJ Jil9]Jd5fA

20. Unit Availability Factor 100.0 59J' 563*

19. Unit Service factor 100J 59.9' 5523'

21. Unit Capacity Factor (Using MDC Net) 9hd Shh 47_d

22. Unit Capacity factor (Using DER Not)

_ __9BJ Sid.

--4ad

23. Unit Forced Outage Rate 0D LZ

_12.4 2

24. Shutdowns Scheduled Over Next 6 Honths (Type Date, and Duration of EN h):

40nt

25. If Shut Down At End Of Report Period, Estimated Date of Startup KlA Adjustment from August report.

1

BOSTON EDISON COMPANY PILGRIH NUCLEAR POWER STATION DOCKM jig-293 Ocerational Summary for Scotember 1991 The unit started the reporting period at 100 percent power with final reactor engineering testing completed and exiting the Power Ascension program.

During September 1 and 2, reactor power was trimmed on several occasions during low tides to maintain the average condenser circulating water temperature rise to less than 32*F per EPA guidelines.

The unit continued to operate at 100 percent power until September 7 when at 0020 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> power was reduced to 66 percent and "C"

Reactor Feedwater Pump

("C" RFP) was secured to replace a leaking inboard seal.

By 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> reactor power was increased to 85 percent i

and was maintained at that level through September 9 while repairs to the "C"

RFP were completed.

With "C" RFP back in service reactor power was increased to 100 percent.

On September 14, power was reduced to 50 percent to perform a thermal backwash of the main condensers.

Following the backwash, power was increased to-100 percent.

On September 24 the Hydrogen Injection System was placed into service.

The unit ended the reporting period at 100 percent power.

Power reductions to 95 percent were performed on September 20 and 28 for control rod exercising.

Safety Relief Valve Challenges Month of Sectember 1311 Requirement:

NUREG-0737 T.A.P. II.K.3.3 There were no safety relief valve ch:11enges 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).

Ref. BECo ltr. #81-01 dated 01/05/81.

REFUELING INFORMATIQH 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 netation 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: April 3, 1993 3.

Scheduled date for restart following next refueling:

June 8, 1993 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 1991 refueling cutage was of the same design as loaded in the previous outage and consisted of 168 assemblies.

7.

(a)

There are 580 fuel assemblies in the core.

(b) There are 1489 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 cssemblies.

9.

Hith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 8'1 fuel assemblies.

Month Seotember 1991 PILGRIM NUCLEAR POWER STATION

~

MAJOR SAFETY RELATED MAINTENANCE SYSTEM CQFPONENT MALFUNCTION CAUS6 MAINTENANCE CORRECTIVE ACTION TO ASSOCIATED-PREVENT RECURRENfCE_'

LER Feedwater Reactor Inboard mech-Under Rebuilt' seal with To be determined.

N/A System Feedwater anical seal investigation.

new parts, and (FH)*

Pump failed.

Installed same.

Medium 480 Volt breaker Failed to close Interference The TLRA in breaker Install new style TLRA LER 91-019-00 Voltage 52-602.

automatic 411y between 52-602 was machined in breaker 52-602.

Poter during a the breaker to satisfy during midcycle' outage System planned bis trip latch tolerances noted in

92. See associated LER.

transfer.

roller assembly GE SAL #306 and (TLRA) and cle-reinstaed in the vis. pin.

breaker oy GE (GE Type personnel.

The AK-2A-50)

TLRA's in two addit-ional type AK-2A-50 breakers were also replaced.

Non Safety Related, but caused reduction in power.

~

UNIT SHUTDOHNS AND POWER RED'JCTIONS DOCKET NO. 50-29'i NAME Pilarim 1 DATE_Dctober

. 1991 COMPLETED BY H. Munro t.

TELEPHONE (508) 747-8474 REPORT HONTH T,eotember 1991 CAUSE & CORRECTIVE

\\

METHOD OF LICENSE F

ACTION TO PREVENT DURATION SHUTTING EVENT SYSTEg COMPgNENT 3

REPORT #

CODE CODE RECURRENCE j

2 DOHN REACTOR NO.

DATE TYPEI (HOURS)

REASON 9 09/07/91 S

0.0 5

N/A N/A N/A Power reduction to perform maintenance on Reactor Feedwater Pump "C".

b 1

l l

I 1

2 2

3 4a5 h

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 p[

C-Refueling H-O':her 3-Auto Scram Preparation of

[

4-Continued Data Entry Sheet 0-Regulatory Restriction 5-Reduced Load Licensee Event Report

[-

E-Operator Training (LER) File (NUREG-1022) r

& License Examination 9-Other s

i

'1 w e - ~-x~ = w v= n w aye== ~=3