ML20063Q127

Monthly Operating Rept for Jul 1990 for Seabrook Unit 1.W/

ML20063Q127
Person / Time
Site:	Seabrook
Issue date:	07/31/1990
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90153, NUDOCS 9008200073
Download: ML20063Q127 (9)

Text

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' Ted C. Feigenboom Senior vice President and Chief Operating Officer

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.NYN 90153.

0 August 13,1990-.

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jy l i-United States Nuclear Regulatory Commission-j Washington, DC ^ 20555 1

- Attention: ' Document Control Desk

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References:

Facility. Operating License NPF 86, Docket No. 50-443 -

i

Subject:

Monthly Operating Report d

- Gentlemen:

Enclosed please find Monthly Operating Report 90 07. -This' report addresses the operating and'sbutdown experience' mlating ta Seabrook' Station j

Unit 1 for the month of July,1990 and is' submitted in accordance with the requirements 'of Seabrook Station; Technical Specification 6 8.1.5.

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Very)tru'.y ycors,-

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Ted C. Feigenbaum Enclosure cc: Mr. Thomas T. Martin Regional Administrator i

United States Nuclear Regulatory Commission '

Region I' 475 Allen (tale Road

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King of Prussia, PA ' 19406 Mr.- Noel Dudley NRC Senior. Resident Inspector.

P.O. Box 1149 Seabrook, NH 03874

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Neu Hampshire YonkedDivision of Public Serwe Company of New Hampshire P.O. Box 300

• Scobrook, NH 03874 + Telephone (603) 474-9521 p.

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7' t.1 OPERATING DATA REPORT

/. -

DOCKET NO.-

50-443 UNIl Sea )roo c1 DATE 08/13/90 COMPLETED BY P.

tarane TELEPHONE (603) 4 4-9521 (Ext. 4074)

OPERATING STATUS 1.

Unit Name:

Seabrook-Station Unit 1 2.

Reporting. Period:

JULY-1994

-3.

, Licensed Thermal Power (MWt):

3411 ~

4.

Nameplate. Rating (GrossMWe):

liv /,

5.

DesignElectricalRating(NetMWe):

-1148

6. - Maximum Dependable Capacity (Gross MWe):

1200.

i 7.

Maximum Dependable Capacity (Net MWe):

_ 1150. -

8. -If Changes Occur in Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons::-

Items'6 and 7 chanaed to reflect operation at 100% 1)ad.

9.

Power Leve' To Whici Restricted, If Any:-

None

10. Reasons For Restrictions If Any:

Not Apolicable This Month-Yr.-to-Date Cumulative k

11'.-Hours-In Reporting Period 7L4.0 5087.0 _

33216.0_,_

i

12. Number Of Hours Reactor Was Critical

• 6D 1-

'2266.1 2460.5 13; Reactor Reserve Shutdown Hours 3:.5

=852.7_,

852.7

14. Hours Generator On-Line SCL.4 995.4 995.4

15. Unit Reserve Shutdown' Hours 0.0 0.0 0.0

16.GrossThermalEnergyGenerated(

)

_._1565543 2327345 2328436 1

17.GrossElec.EnergyGenerated(MW 525522 691544 691504 18.~ Net. Electrical Energy Generated

-*19. Unit Service Factor. '

HWH) 500476 650450-650L50 g

78.5 29.8 29.8 L

• 20.. Unit Availability Factor 78.5-29.8 29.8 4

• 21. Unit'CapacityFactor(UsingMOCNet) 58.6 17.0-

'17.0

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• 22. Unit Capacity Factor.(Using DER Net) 58.6 17.0-17.0 F

23. Unit Forced Outage Rate 15.7 26.4 26.4

=

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

~ Maintenance / Snubber Inspection. 11/03/90. 14 Days

25. If-Shut Down At;End Of Report Period, Estimated Date 0f Startup: Not Acolicable-26.l Prior to Commercial Operation:'

Forecast Achieved' INITIAL CRilICALITY 1989

'06/13/89 IkITIAL ELECTRICITY 1990

05/29/90 COMERCIk. OPERATION 1990

-Hot Apolicable y

• NOTE:

Year-to-Date and Cummulative values based on accumulated hours starting 03/15/90, date the full power license was issued.

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' AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO.c 5)-443

UNIT Sea > rook 1 L

DATE 08/13/90

'd l'

' COMPLETED BY P. Narcone

-i L-TELEPHONE 1603) 4}4-9521 c

(Ext. 4074)

. MONTH _ JULY. 1990'

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DAYL AVERAGE. DAILY POWER LEVELL

' DAY l

' AVERAGE DAILY. POWER LEVELL 1

(MWe-Net)>

<(MWe-Net)-

l-1-

216

^ 16 890 1

2

'488' 17

-873-3 2

-18 874-

4 92

-19

~957 '

l-487 20

'1053

- t, 0-

'21 991 7

69 22 "1149 l

8 755 23-

-1152 9

846 i24

1155 l

.10 858

'25-t1154 L

L 11 845 26-996' d

E l

12 612 27 524 13 515 28 if071 L

14 827

-29 386:

L 115 993-30 0-31 23 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day-intthe reporting month.

Compute to.the nearest whole. megawatt 2 of 8 i

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LNIT SHLffD0061S A20 IONER REDUCTICES D00ET NO.

50-443

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tmIT h - uuk 1 DATE 08/13/90 REEGT MNDI JULY, 1990 CWJMD BY P. Nardone

. MIEPH31E f603) 474-9521 :

L (Ext. 4074)-

1:

No.

Date Type Duratim ~Reasan2 Method of Licensee Cause' & Cou.ecilve' l

(Hours)

Shutting Event Action to Down Reactor 3 Report _#

Prevent Recurrence Page l'of 4 1

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90-11 07/01/90 F

11.8 A

4 N/A Seswun leak in heater drain niping.

Dirhine load reduced fran'720 lege.

Generator breaker opened. Reactor power being held at 15% RTP. Re.

<*wwr-in heater drain piping to -

l cmdenser Ina a crack in it.

Exmvated the crack area and per-fanmarl weld repair.

1 2

3 F: Ebrced Reason:

Method:

S: Scheduled.

A-Equipnent Failure (Explain).

1-Manual IHiaintenance or Test

.2-Menual Scran C-Ran =1ing 3-Autaastic Scram D-Regulatory Restriction 4-Continued fran E-Operatar. Training & Idoense Examination I_mevious month F-Administrative 5-Power Darhv-tion G-Operational Error '(Pmnlain)

(Not Factored Into Ebooed Outage Rate)

H-Other (Replain) 9-Other (Pmplain)-

5 E

e 3 of 8 i

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LWIT SHUIDOGES NO POWER REDUCTICNS.

DOCRET NO.

50-443

~

INIT Seabcocit 1 DATE 08/13/90 REPORT M'NIH JULY, 1990 (DEUTED BY P. Nardone TETEPHCNE (603)' 474-9521 (Ext.-4074) l 2

No.

Date-Type Duratim Rev. son.

Method of Licensee Cause & Coo mctive (liours)

Shutting Event Actim to-3 Report #

Prevent Recuuan Down Reactor Page 2 of 4.?

'90-12 07/02/90 F

16 H

5 N/A Fivvedure problem during routine

~

surveillance test caused w ;+Ne3 turbine runback ' cram 815 7ese.- Power avamd from 70% to 35% RTP. _ '1h

~

load stabili=1 at 360 Mec. During -

silmage==d. load increase piping problem ider.itified in heater drain nyouest. See Item 90-13.

^

90-13 07/03/90 F

39.3 A

9 N/A-Elbow in heater drain piping indicated below minimum well' thickness.- Turbine' load rei-ei frm 575 Ieee. - Generator breaker opened. Heactor power rduved to 10% RTP. Elbow was repls0ed.

90-14

.07/05/90 F

49.5 A

3-N/A EHC.ge:som.e switches on hwhim control; valves trirupi reactor ptotectim oyo^uem caf'"*Tautomatic Ieactor trip / turbine trip.. Pressure switches tripped falsely.

as a result of vibratim at mounting location. Pressure switches were re-mounted m separate wi.s.

4 of 8

INIT SHUIDOME AND 10HER REDUC'.fIONS DOOTT NO.

'50-443

- ~~

UEIT Sesi vrA 1 DME 08/13/90~

REPGE 10ml JULY, 1990 OCMPIEff!D BY P. N&1.d ass TE MPIDEE f603) 474-9521' (Ext. 4074) l 2

No.

Date Type Duration Reason Method of Licensee CauEe & Cuuecdve (Hours)

Shutting Event Acticn to 3

Down Reactor Report #

Prevmt Kunrrence Paga 3 of~4 90-15 07/12/90 S

55 B

5 N/A Performari Is ;a load reduct. ion test fr a 75% RIP. Return to 75% slowed by AFD penalty minutes and controller tuning on heater drain syste.

90-16 07/16/90 F

84.5 A

5 N/A Problems with s*dility in faadbeater syste forced reductim fra 90% to '

75% RTP. Placed moisture annarntors and rehestets in service. Perfrwaart aantroller tuning on heater drain oy L:==.

90-17 07/20/90 F

51 A

5 N/A Problems with stability in fec^eter systm forced reduction fra 300% to '

80%. Cleened strainer on N Tte plaqp.. Perfoomed controller tuning m heate-drain system and feedwater regulating control valves..

90-18 07/26/90 S

42.5 B

5-N/A Perfomed large load reduction test from 100% IUP. Return-to 100% slauei by AFD penalty minutes.

5 of 8

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-- e DOCKER E 443 tMIT WM1 DPEE G8/13/90 CNRECTIVE MAINTENANCE SG99RY RR SAFEIT RELMEED BQUII4ENT (IDE'IETED BY P. Nardane REPORT M)NDI JtKE, 1990 TELEPfDIE J603) 474-95!:

(Ext. 4074)

%ge 1 of l '

DPEE SYSTEM C(3EFOMPNf MPGNTENANCE ACION 07/06/90 Safety 1-SI-PB-936A/B Bistable' failed in service..Dani d Fwi.act.icn Set 2 -

histable.

. Injectimi HI Contairunent Pressure Bistable 07/13/90 Pr-innry 1-CC-V-1 Disdumoge check valve stuck open.

Cy== d.

Train A'

'IdEMt"Ifi881 during pump SN8pOUGE. Re ;

i

.. Cooling Primary Canpanent placed brolaen disc wesher.

Mter

~ @l_ing hter Pung C Discharge Check

. Valve

=

=

- =

f_

sq DOCKET NO..

50-443' INIT Raahrock 1 IRTE 08/13/90 OCNFLET!!D BY P. Nardane __

y TEU!REME-(603) 474-9521 i

(Ext. 4074) d REFUILIE II9mMATION REQUEST l

i

1. NEsHB of facility: Seabrook thit 1

2. Scheduled date for next refueling shutxkun: 07/27/91

3. Scheduled date for restart following refueling: 09/21/91

4. Will refueling or resunption of operatim thereafter require a' technical specificaticn change or other license amendment?

-1 Unknown at this time.

5. Scheduled date(s) for submitt'g licensig' action and supporting information Not Applicable

6. Inportant licensing mnsiderations associated with refueling, e.g.,-

new or different fuel design or supplier, unreviewed design or

-i performance analysis methods, significant changes in fuel design, naw operating s knw:

v None

7. 'Ibe number of fuel assenblies (a) in the core and (b) in the spent,

fuel storage pools (a) In Cores.

193 (b) 0

8. 'Ibe prasent licensed spent fuel pool storage capacity and the size of

.j any increase in limnaed storage capacity that has been requested or i

is planned, in ntanber of fuel assemblies:

Present licensed capacity: 1236 No increase in s h. age capacity requested or planned.

j q

9. '1he projected date of the-last refueling that can be discharged to -

the spent fuel pool assuning the present. licensed capacity Licensed capacity of 1236 fuel assemblies based on sixteen refnelings and full core offload capah!Hty.

'1he current licensed capacity is adequate until at least the.

year 2010.

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