ML20044B217

Monthly Operating Rept for June 1990 for Seabrook Station, Unit 1

ML20044B217
Person / Time
Site:	Seabrook
Issue date:	06/30/1990
From:	Feigenbaum T, Nardone P PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90-133, NUDOCS 9007180132
Download: ML20044B217 (7)

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t CNew Homoshire Ted C. F '. -E n.

L-Senior Vice President and Chief Operating Officer NYN-90133 July 11, 1990 United States Nuclear Regulatory Commission Washington, DC ~20555 Attention: Document Control Desk References _: Facility Operating License NPF-86, Docket No. 50-443

Subject:

Fonthly Operating Report Gentlemen

)

. Enclosed please find Monthly Operating Report 90-06. This' report addresses the operatin' and shutdown experience relating to Seabrook Station Unit 1.for the mon d uf June, 1990 and is submitted in accordance with thec

requirements of Seabrook Station Technical-. Specification 6.8.1.5.

/

Very tr 1y yours,'

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Ted C. Feigen Enclosure p.-

cc: Mr. Thomas T. Martin

- Regional Administrator.

1 United. States Nuclear Regulatory Commission t!

-Region.I 1

475 Allendale Road King of Prussia,-PA 19406-

]

MrJ Noel Dudley k

. NRC Senior Resident Inspector P.O. Box 1149' Seabrook, NH 03874 1

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90071so132 900630

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PDR ADOCK 05000443 R

PDC 1

hew Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

• Seo' rook, NH 03874

• Telephone (603) 474 9521 o

OPERATING DATA REPORT DOCKET NO.

50-443 UNIT -Sea > rook 1 DATE 07/11/90 COMPLETED BY P. Nardone-TELEPHONE

3) 474-9521 Ext. 4074)

OPERATING STATUS

~1.

Unit Name:

Seabrook Station Unit 1 2._

Reporting Period:

JUNE 1990 3.

LicensedThermalPower(MWt):

3411

'4.

NameplateRating(GrossMWe):

1197 5.

DesignElectricalRating(NetMWe):

1148

+

6.

fiaximum Dependable Capacity ((Gross MWe):1197(Initialdesignvalue) 7.. Maximum Dependable Capacity Net MWe):

1148 (Initial design value) 8.

IfChar.gesOccurinCapacityRatings(ItemsNumber3Through7)

Since Last Report, Give Reasons:

Not ADDlicable

- 9.

Power Level To Which. Restricted, If Any:

None

10. Reasons For Restrictions, If Any:

Not ADDlicable This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720.0 4343.0 32472.0 w:

12. Number Of Hours Reactor Was Critical 568.5 1595.0 1789.4

13. Reactor Reserve Shutdown Hours 106.0 821.2 821.2

14. Hours Generator On-Line 388.9 411.0 411.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

-17. Gross Elec. Energy Generated (MWH) )

16. Gross Thermal Energy Generated (MWH 566463 761802 762892 163067 166022 166022 18.-NetElectricalEnergyGenerated(MWH) 147893 14997a 149974

• 19. Unit Service Factor-54.0 15.9 15.9

• 20. Unit Availability Factor 54.0 15.9 15.9

• 21.UnitCapacityFactor(UsingMDCNet) 17.9 5.0 5.0

• 22. Unit Capacity Factor (Using DER Net) 17.9 5.0 5.0

23. Unit Forced Outage Rate 36.5 37.6 37.6

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

Maintenance / Snubber InsDection, 11/03/90. 14 Davs

25. If Shut Down At End Of Report Period, Estimated Date Of Startup:

Not ADDlicable

26. Prior to Commercial Operation:

Forecast Achieved INITIAL CRITICALITY 1989 06/13/89 INITIAL ELECTRICliY

__1990 05/29/90 COMMERCIAL CPERATION 1990 Not ADDlicable

• NOTE:

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

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'A ERAGE DAILYiUNIT POWER LEVEL I

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DOCKET NO.-

5')-443 0

UNIT Sea >roo:c1 DATE 07/11/90 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)-

jp,lNONTH JUNE. 1990

' DAY AVERAGE DAILY POWER'LEVELL DAY AVERAGE DAILY POWER LEVEL.

(MWe-Nat)

(MWe-Net) lr

1-0 16 114 2.

0 17 0

--3 56 -

18 0

.4' 138 19 0

5' 257 20 87 l

E 6

156 21 0

1.

l7 102 22 0

L 8-281 23 0

L 9

298 24 0

10 244 25 0

11 351 26 0

l-l 12 377 27 336 l-r l

13 490 28 630 t

14 461 29 722 15 453 30 610-

-INSTRUCTIONS On this, format, list the average daily unit power leve'l in MWe-Net for each: day in the

= reporting month. l Compute to the nearest whole megawatt.

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wi INIT SHUIDOMES AND FOWER REDUCTICNS DOCIET N00 50-443 4

^

INIT N1 IRTE 07/11/90

~~

REPORT K NDI JtRE, 1990 OMPIEfED BY P. Hardone TE EPH NE (603) 474-9521

.(Ext. 4074) l 2

Method of Licensee Cause' & Cvum: Live No.

Date Type Duration Reason (Hours)

Shutting Event Acticm to Down Reactor 3 Report #

Prevent Recuuuis Page 1 of 2 l

90-04 06/01/90 F

50.1 A

4 N/A Reactor power at 2% RTP. Generator bmaker opened. Turbine vedor repair-ing necnanical -g trip sechanima.

90-05 06/03/90 S

10.2 B

9 N/A Reactor power at 10% RTP. Generator bmaker opened. Testing hwhina over-Speed trip.

90-06 06/04/90 S

6.9 B

9 N/A Reactor power at 16% RTP. Generator bmaker opmed. Testing hwhine over -

speed trip.

1 2

3 F: Formd Reascm:

Method:

S: Scheduled A-Bguipnent Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-reb mling 3-Autcnatic Scram D-Regulatory Restriction 4-Continued from E%a'u.u. Training & License Examination pmvious month F-A*ninistrative 5-Power Raducticn G-Operational Error-(Rwp1ain)-

(Duration = 0)

H-Other (Rmlain)

~

9-Other (Explain) 3 of 6

INIT SHUIDOhNS AND POWER REDUCTIOtS '

DOOTT NO.

50-443 INIT Seabrook 1 DATE 07/11/90 REEWT KNIH JIME, 1990 0@!PIzrED BY P. Nardone N (603) 474-9521 (Ext. 4074) l No.

Date Type Duration Reason 2 Method of' Ideensee Cause & Cuualive (Hours)

Shutting Event Action to Down Reactor 3 Report #

Prevent Recurrence Page 2 of 2 90-07 06/06/90 F

18.8 A

9 N/A Reactor power reduced to 16% RTP.

Generator Ireaker opened. Repairing r

electrical connecticm that caused phase B 25 KV bus duct arcing.

90-08 06/07/90 F

2.7-A 9

N/A Reactor power at 17% RTP.

G&mn.atus.

breaker opened. perniring generator voltage regulator.

l 90-09 06/16/90 S-90.5 B

l

N/A Reactor drukkeen frun outside the contro1 mm test. Perfoontng scheduled maintenance. Ibllowing ah*w fma.0% RrP.

90-10 06/20/90 F

151.7 A

3 N/A Generator protective relaying tripped l

generator breaker open, causing auto-natic turbine / reactor trip. Analyzing svimetive relaying. Modifying energency feedwater isolation system l

instrtmientation.

90-11 06/30/90 F

.2 A

9-N/A Steam leak in anter drain piping.

'Dwhine load reduced from 720 MNe.

Generator breaker opened. Reactor pcwer at 20% RTP. Parhm in heater drain tank pipiry to uam.ki===x. has a crack in it.

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DOCEEr N01 50-443~

v-turf We,; d l-DATE 07/11/90' umeca;nVE MAINITNANCE SW99RY KR SAFEIY RELATED EQUIPMENT CDHEEED BY P. Nardme t

REKRT ENTH JIME, 1990'

'ITLEPfDE (603) 474-9521

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Page 1 of 1..

(Ext. 4074)

DATE SYSTEM 00MPONENT MAINIENANCE ACFIQi

%d."

i 06/07/90 Cantaiment 1-COP-V-2 and 3 During containemt purge operatim, valves.

Bdiding Train B failed to open.

pon1=,ari diaphrans in both On-Idne Purge

.Inside Containment air exhausters for each valve.

.Isolatim Valves 06/08/90 Main Steam 1-MS-V-128 Valve failed to reopen following time Train B i*padie survei11an test. Valve sten Main Steam to FN length adjusted to gevait '.-dve fran Ptap Turbine januning into seat.

Isolation Valve' 06/11/90 Reactor 1-RC-PCV-456B Valve leaking by seat. Steam cuts an plug Coolant Train B and seat. PapW cage, plug and seat.

Power Cwattai Relief Valve 5 of 6

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DOCKET NO.

50-443 INIT hhrook 1 DPGE 07/11/90

.. = -

O N PLETED BY P. Nardone TELEPH NE (603) _174-9521 (Ext. 4074) 1 REINELDG..INIUMM'ICH REDUEST 1; Name_of facility: hhn:ok Ihit 1

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

3. Scheduled'date' for restart following refueling:

09/21/91 n

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Unknown at this time, h

/j

-5. Scheduled date(s) for subnitting licensing action and supporting H

information:

1 Not Applicable L

i l

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

new or different f e l design or supplier, unreviewed design or.

perfomance analysis methods, significant changes in fuel design, new operating p. -:-4m:

None L

7. 'Ihe number of fuel assemblies (a) in the core and (b) in the spent L

fuel storage pool:

p

-(a) In Core:

193 (b) 0

8. 'Ihe present licensed 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:

l' Present licensed capacity: _1236 p

No increase in storage capacity requested or planned.

l=

[

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

l>

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

'Ihe current licensed capacity is adequate until at least the Ii year 2010.~

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