ML20044B217

Monthly Operating Rept for June 1990 for Seabrook Station, Unit 1.W/900711 Ltr

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 '.

L-Ted C. F '. -E n .

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,' ,

tvd / s?'

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 L>  ;

l L

90071so132 900630 )

PDR ADOCK 05000443

.. R PDC 1 hew Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

• Seo'o rook, NH 03874

• Telephone (603) 474 9521

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. 1197(Initialdesignvalue) fiaximumDependable 7.. Maximum Dependable Capacity Capacity ((Gross MWe):1148 (Initial design value)

Net MWe):

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

16. Gross Thermal Energy Generated (MWH 566463 761802 762892

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

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 l 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)

No. Date Typel Duration Reason2 Method of Licensee Cause' & Cvum: Live (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) 9-Other (Explain)

~

H-Other (Rmlain) 3 of 6

INIT SHUIDOhNS AND POWER REDUCTIOtS ' DOOTT NO. 50-443 .

INIT Seabrook 1 07/11/90 DATE REEWT KNIH JIME, 1990 0@!PIzrED BY P. Nardone N (603) 474-9521 (Ext. 4074)

No. Date Typel 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 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 ,

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REKRT ENTH JIME, 1990' 'ITLEPfDE (603) 474-9521 (Ext. 4074) ,

Page 1 of 1 ..

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 1

(Ext. 4074)

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 l> the spent fuel pool assuming the present licensed capacity:  ;

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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