Text

Monthly Operating Rept for Jan 1991 for Pilgrim
	ML20067E332
Person / Time
Site:	Pilgrim
Issue date:	01/31/1991
From:	Richard Anderson, Munro W; BOSTON EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	91-014, 91-14, NUDOCS 9102140188
	Download: ML20067E332 (7)
	v • d • e

_ -... _. _ _ _. - -. _..

g h

nosronumsou Pilgtem Nuclear Power Station 6

Rocky Hill Road Plymouth, Massachusetts 02300 R. A. Anderson Vee Prescent &

&'u'N"cEM', Ton.

February 13, 1991.

BECo Ltr. #91-014

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

Subject:

January 1991'Honthly Report

Dear Sir:

In accordance With'PNPS. Technical $pecification 6.9 A.2, a copy of the Operational, Status Summary for Pilgrim Nuclear Pover Station is attached for your information

=and planning. Should-you have any questions concerning this report please contact

- me directly.

. A.' Anderson t

?

HJM/bal

[

Attachment-e cc: Regional' Administrator. Region 1 U.S._ Nuclear Regulatory Commission 475 Allendale RC.

King of Prussia,.PA.19406

. Senior Resident Inspector m

h 9102140188 910131-

-PDR ADOCK 05000293 R

PDR L

f

N tp

-7 Y4 s.-tw*^sma*-tog ye p - y eww me-p,-

aty g-g-e-4.we-arw

--e*me=g-s-.e e-r + er n'.e-

- * + -

e y.yv w w = -ma a, e-m w ea we=-=g--eepsp*-_3'--

W-9e*N's:v==*D wr i e +' W

-*T

^

-. ~

AVERAGE DAILY UNIT POWER LEVEL-

~

DOCKET NO.

50-293 UNIT Pilarim i DATE February 13, 1991 COMPLETED BY H. Munro TELEPHONE, (508) 747-8474 HONTH January 1991

- DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)-

(HWe-Net) 1 355 17 664 2

475 18 664 3-505 19 663 4 --

630 20 665

- 5 664:

21=

-665 6

662 22 664 7

663 23 665 8

663 24 665 9

664' 25 663 10-664

- 26 663 4

11 1' 628 27 665

- 12 620 28 664 13'

-664 29 664 14-665-230 664 15 664 31 663 16-

-664 This format'11sts.the average daily unit power level in MWe-Net for each' day in the reporting month, computed'to the. nearest whole megawatt.:

V

+~?-

we1ks a-w w e t

-# +vwse

+emrw ysm-ry'=m5i gt u + w 4a-

+v=We--

9.-

gp rme de sv W +

r--e-r myw -w w-y is v re yr-,eipt-gyv-stwyw e gy=

w ye yww--yept-

++--1-TM**-syv t-

OPERATING DATA REPORT DOCKET NO.

50-293 DATE ram, m, n

ioni COMPLETED BV~~H. Mun s ~~'~

TELEPHONE (508) 747-8474 OPERATING STATUS Notes

1. ' Unit Name Pilorim 1 2.

Reporting Period January 1991 3.

Licensed Thermal Power (HHt) 1998 4.

Nameplate Rating (Gross HHe) 678 5.

Design Electrical Rating (Net HHe) 655 6.

Maximum Dependable Capacity (Gross HHe) 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 9.

Power Level To Hhich Restricted, If Any (Net HHe)

None

10. Reasons For Restrictions -If Any N/A This Month Yr-to-Date Cumulative 11'. Hours In Reporting Period.

744.0 744.0 159072.0

12. Number Of Hours Reactor Has Critical 744.0 744.0-93344.7'

13. Reactor Reserve Shutdown Hours 0-0 0.0 0.0

14. Hours Generator On-Line 744.0 744.0 89660.1

15. Unit Reserve Shutdown Hours 0.0 0.0.

0.0

16. Gross Thermal Energy Generated (HHH)-

1433016.0 143301 M 16767165.0

- 17. Gross Electrical Energy Generated (HHH) 493840.0 493840.0- 52141354.0

18. Net' Electrical Energy Genereted (NHH)-

475427.0 475427.0 50101835.0:

19. Unit Service Factor 100.0' 100.0 56.4

20. Unit Availability Factor 1003 100.0 56.4

-21. Unit Capacity Factor (Using HDC Net).

97.6 97.6 48.1 95.4 95.4 47.0

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 0.0 0.0-12.7-24.' Shutdowns Scheduled 0ver Next 6 Honths (Type, Date, and Duration of Each):

Refuelina Outaae No.-8.

Hav 1991. anoroximatelv 70 days

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

l BOSTON EDISON COMPANY

. PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 l

Qperational Summarv for Jarluary 1991 l

1 The unit started the reporting period at approximately 76 percent power with the "C" Reactor feedwater Pump (RFP) secured for repairs. On January 1, 1991 at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months a power reduction to approximately 50 percent was made to conduct a backwash of the main condenser, and to replace the brushes on the "A" Recirculation Motor Generator Set.

At 2043 hours0.0236 days 0.568 hours 0.00338 weeks 7.773615e-4 months the "A" Recirculation Motor Generator. Set was restarted, and by 0303 hours0.00351 days 0.0842 hours 5.009921e-4 weeks 1.152915e-4 months on January 2, 1991 reactor power was increased to 76 percent. On January 3 1991 power was reduced to approximately 52 percent _to perform a control rod pattern change.

Power was again increased to 100 percent on January 4, 1991 and remained there until January.11. 1991 when at 2009 hours0.0233 days 0.558 hours 0.00332 weeks 7.644245e-4 months , maintenance personnel, welding on the turbine butiding exhaust fan above the "A" RFP, reported smoldering on the

-roof.

Power was reduced-to 70 percent and the "A" RFP was secured. An Unusual Event was declared at 2031 hours0.0235 days 0.564 hours 0.00336 weeks 7.727955e-4 months and terminated at 2201 hours0.0255 days 0.611 hours 0.00364 weeks 8.374805e-4 months .--On.

January 12, 1991 the "A" RFP was returned to service, power was increased to 100 percent and remained there for the remainder of the reporting period.

Power reductions to 90 percent were performed on January 6, 11, 19 and 26 for control rod exercising.

Safety Relief Valve Challenges-Month of January 1991 4

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 i

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

m._

---w.--i____

._mm-m_

___m s_______i__

REFUELING INFORMATION ThefoklowingrefuelinginformationisincludedintheMonthlyReportas 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.

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 1991 4.

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

5.

See #6.

6.

Me 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.

9.

With present spent fuel in storage, the

pent fuel pool now has the capacity to accommodate an additional 1000 fuel assemblies, l

l 1

i I

-Month. January 1991 l;

PILGRIM NUCLEAR POWER. STATION l 1.

^

MAJOR SAFETY'RELATED MAINTENANCE SYSTEM.

COMPONENT.

MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO

. ASSOCIATED

.[

PREVENT RECURRENCE LER i

Feed-

"C"' Reactor Feed -

Pipe cracked

. Physical contact Installed Temporary-Replacement of inlet N/A water-water Pump'(RFP).

and leaking..

of'the two (2)

Modification TM 91-01 pipe during RFO-8.

~

System

. suction-relief-(F&MR 90-426) inch outlet pipe. consisting of a-cel-

~

valve standpipe.

with the wall lar welded-together 4

caused a twist-axially, and then ing moment on

- welded around the "C" the' inlet. stand-RFP suction relief ~

pipe.-

valve (PSV-3444) inlet pipe. The two (2) inch outlet pipe was shortened to remove interference with the wall.

Reactor Control cable bet-Turbine tripped Faulty control-. Replaced control Refurbish M01301-61 LER 91-001-00 Core ween the Electronic on high steam. cable due to cable and signal con-valve. (MR 19013040)

(To be issued)

Isola-Speed Controller flow. (F&MR environmental verter card. Perform-tion (EGM) and the 91-33).

conditions res-ed Proc. 8.E.13.1 Cooling Electro-Hydraulic' ulting from seat successfully to prove f

System Valve Actuator (EGR).

leakage on MO operability.

l 1301-61 valve.

Reactor Turbine Exhaust Failed rupture Extreme environ-Installed new rupture Refurbish M01301-61 N/A 4

Core line.

disc PSD-9 mental condit-disc.

valve. (MR 19013040) 4 i

Isola-(F&MR 90-128).

ions resulting i

tion from seat leak-Cooling age on M01301-System 61 valve.

I

~

b p._

,m-3.

UNIT SHUTDOWNS AND' POWER REDUCTIONS

. DOCKET NO. 50-293 NAME Pilorin 1 DATE ' February 13. 1991.

COMPLETED BY H. Munro f.

TELEPHONE (508) 747-8474 REPORT MONTH January 1991

. METHOD OF_'

LICENSE CAUSE&CORRECTkVE-ENT

' ACTION TO PREVENT DURATION

~ SHUTTING' EVENT-SYSTEg COMyE (HOURS)

REASON 2 DOWN' REACTOR 3-

. REPORT #

'NO.

DATE.

-TYPEI CODE COD RECURRENCE-18 01/01/91 F.

0.0 N/A

-5 N/A N/A N/A Power reduction to backwash main condenser and replace brushes on "A" Recirc...

MG set.

1 2

2 3

4&5 F-Forced A-Equip Failure idmin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram-Instructions for C-Refueling H-Other:

13-Auto Scram Preparation of D-Regulatory. Restriction 4-Continued flata Entry Sheet E-Operator Training'.

5-Reduced Load Licensee Event Report

& License Examination.

9-Other (LER) File (NUREG-1022) i 1

i.

i

=...

_-- -

ML20067E332

Text

Subject:

Dear Sir:

Navigation menu

Search