ML20042G944

Monthly Operating Rept for Apr 1990 for Seabrook Unit 1

ML20042G944
Person / Time
Site:	Seabrook
Issue date:	04/30/1990
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90109, NUDOCS 9005160317
Download: ML20042G944 (7)

Text

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e-LNew H.ampshire L

led C. Feigenboum i

Senior Vice President and Chief Operating Officer r

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1 NYN-90109 May 8, 1990 United States Nuclear Regulatory Commission Washington, DC 20555 t

3 Attention: Document Control Desk References Facility Operating License NPP-86, Docket No. 50-443

Subject:

Monthly Operating Report Gentlemen Enclosed please find Monthly Operating Report 90-04.

This report

. addresses the operating and shutdown experience relating to Seabrook Station Unit 1 for the month of April 1990 and is submitted in accordance with the i

requirements of Seabrook Station Technical Specification 6.8.1.5.

l Very truly yours, 7h/& M'h V

i Ted C. Feigenba m Enclosure t

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-l 9005160317 900430 PDR ADotg 0S000443 i

R PDC New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. M 300

• Seabrook, NH 03874

• Telephone (603) 474 9521

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..Unitqd States :Nucitar Regulat:ry.Comunission

. May 8 1990

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- Attentions: Document' control -

Pag? 2 s,

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'cc Mr. Thosee T. Martin

-Regional Administrator ff:,",

United States Nuclear Regulatory Consnis.sion pf

kegion 1 475.Allendale Road.

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~ King of. Prussia, PA 19406

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Mr.' Noel Dudley

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.NRC Senior. Resident Inspector-l g#

P.O. Box 1149-vt

'Seabrook, NH 03874.

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,m OPERATING DATA REPORT p.

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DOCKET NO.

50-443 c

UNIT Seabrook 1 I

DATE 05/08/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521

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(Ext. 4074) j

' OPERATING STATUS p,

1;- Unit Names Seabrook Station Unit 1 j"

2.

Reporting Periods.

APRIL 1990 E

3.

Licensed Thermal Power (MWt):

3411 4..

Nameplate Rating (Gross MWe):

1197

!S..: Design. Electrical Rating (Net MWe):

1148

6. -Maximum Dependable Capacity (Gross MWe):

1197 (Initial design value) 7.

Maximum Dependable Capacity.(Net MWe):

'1148 (Initial design value) 1 g

8..

If Changes occur in Capacity Ratings (Items Number 3 Through 7)

L Since Last Report Give Reasons:

Not Aeolicable 9..

Power Level To Which Restricted If Any:

None o

10. Reasons For Restrictions. If Any:

Not Aeolicable o

This Month Yr. to-Date cumulative 11.~ Hours In Reporting Period 719.0 2879.0 31008.0

12. Number Of Hours Reactor Was Critical 660,1 888.0 1082.4

13. Reactor Reserve Shutdown Hours 58.9 109.7 109.7

'14. Houre 00nerator On-Line 0,",___,

0.0 0.0

'15. Unit Reserve Shutdown Hours 0,

0.0 0.0 lj

-16. Gross Thermal Energy Generated (MWH) 127021 159001 160092

.17.: Gross Elec. Energy Generated (MW9) 0 0

0 18.~ Net Electrical Energy Generated (MWH) 0 0

0

19. Unit Service Factor 0.0 0.0 0.0 20'. Unit' Availability Factor 0.0 0.0 0.0 21.. Unit Capacity Factor (Uting MDC Net) 0,0 0.0 0.0 p

~22. Unit Capacity Factor (Using DER Net) 0.0 0.0 0.0

23. Unit Forced Outage Rate 0.0 0.0 0.0

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

L None 25.-If Shut Down At End Of Report Period Estimated Date Of Startup:

05/24/90 26.' Prior to Commercial Operation:

Forecast Achieved E

INITIAL CRITICALITY 1989 06/13/89

.i INITIAL ELECTRICITY 1990 Not ADolicable COMMERCIAL OPERATION 1990 Not Applicable 1 of 5

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-443 UNIT Seabrook 1 DATE 05/08/90 COMPLETED BY P. Nardone TELEPIl0NE (603) 474-9521 (Ext. 4074)

HONTH APRIL. 1990 DKl AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(We-Net) 0

'l 0

16 2

0 17 0

3 0

18 0

4 0

19 0

5 0

20 0

6 0

21 0

7 0

22 0

8 0

23 0

9 0

24 0

]

10 0

25 0

11 0

26 0

12 0

27 0

13 0

28 0

14 0

29 0

15 0

30 0

l INSTRUCTIONS On this format. list the average daily unit power level in HWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

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'l m--

____.mm.

_.m___.____.._____.._.____.m.

INIT SHUIDOWS AND POWER REDUCI'IOtS DOCIGT 10.

50-443 IMIT Sentrook 1 DPEE 05/08/90 REPCRT KNIH APRIL, 1990 CIMPIZIED BT P. Nardone MTMKME: f6031 474-9521 (Ext. 4074)

No.

Date Type Duration Paeson2 Method of Licensee Cause & Corrective l

(Hours)

Shutting Etat Acticn to Down Reactor 3 Rg ort #

rresmt Recuuum e 90-02 04/01/90 S

6.7 B/F 4

N/A Reactor shubi; sn ishile turbine verrk2r is evaluating rotor differstial ex-pansion indication h vad during initial shell idanning.

90-03 04/28/90 S

52.2 B/F 1

N/A Reactor shutdown inhile turbine vuh is nodifying low ge:>=ute turbine rotor blading as a result of turbine torsional test data.

1 2

3 F: For d Reason:

Method:

S: Scheduled A-Equipnst Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Autmetic Scram D-Regulatory Restriction 4-Continued frm E-Operator Training & Licmse Examination previous a m th F-Adit nistrative 5-Power Reducticn i

G-Operational Error (Explain)

(Duration = 0)

H-Otler (Explain) 9-Other (Explain) 3 of 5 i

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.j DOOTT No.

50-443'

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IstIT Saida.uA 1 DraE 05/08/90 CORRETIVE FAINMSNCE SW99RY Fm SAFErY RETEIED EQUIPMDff CIDIPLETTD BY P. Nardone REPCRP KNIH A' AIL, 1990 TEMPH3EE: (603) 474-9521 (Ext. 4074)

Page 1 of 1 DATE SYSIDI (IMPOTENT 19LIlm!NR14CE ACTICM 04/13/90 Rod Control 1-CP-CP-lli Herm.ha. trip breaker failai to close Train B during survpillance testing. Cleaned Reactor Trip auxiliary contacts and replaced breaker Switchgear anti-pump y* relay.

4 of 5 m

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DCuusr NO.

50-443 INIT Seabrook 3 DME 05/08/90 CXEPILTED BY P. Naltone TELEPHONE (603) 474-9521 (Dct. 4074)

REFUELI1G INKWATION REDUEST

1. Nam of facility: Seabrook thit 1 L

2. Scheduled date for next refueling shutdown: 06/08/91

3. Scheduled date for restart following refueling: 08/04/91

4. Will refueling or resunption of operation thereafter require a technical specification change or other license amrd-nt?

Unknown at this tim.

5. Scheduled date(s) for subnitting licensing action and supporting infonctions Not Applicable

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or perform nce analysis m thods, significant changes in fuel design, new operating procedures:

None

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a)

In Core 193 (b) 0

8. We present limnsed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present licensed capacity: 1236 No increase in storage capacity requested or pla,nned.

9. We projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Licensai capacity of 1236 fuel assablies based on sixteen refuelings and full core offload capability.

We current licensai ott icity is adequate until at least the year 2010.

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