ML20042E326

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Mar 1990 for Seabrook Unit 1. W/900413 Ltr
ML20042E326
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 03/31/1990
From: Feigenbaum T, Nardone P
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-90092, NUDOCS 9004200620
Download: ML20042E326 (7)


Text

--

V

p. .>.

. . New Hampshire Yankee .

NYN-90092 April 15-, 1990 United States Nuclear Regulatory Commission Washington, DC 20555 Attention Document Control Desk References '(a) Facility Operating License NPF-67, Docket No. 50 443 (b) Facility Operating License NPF-86. Docket No. 50-443 l'

Subject Monthly Operating Report Gentlement Enclosed please find Monthly Operating Report 90-03, This repor't addresses the operating and shutdown experience relating to Seabrook Station Unit 1 for the month of March 1990 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very truly yours, f}&ff /4 Ted C. Feigenbaum Enclosure ces Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 '

Seabrook, NH 03874 m

9004200620 900331 PDR ADOCK0500g3 R

)

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

  • Seabrook, NH 03874
  • Telephone (603) 474 9521 -

s

~

o

~

i '%, a:&M

'~

1 4 p g.y:ij g  !

" ^

.*' , OPERATING DATA REPORT ,;

3 )

j

' DOCKET NO.- 50-443 ,

UNIT Seabrook 1- :1

' iDATE 04f13190~ 'I COWPLETED BY P. Nardone 1 (f

9' ,

YELEPHONE 1603) 474-9521

=(Ext, 4074)  !

k'oj OPERATING STATUS: .j

. iz z 1. , Unit Names' Stabrook Station Unit 1  !

[' l2. Reporting-Periodi; HARCH 3990 , ,.

3. Licensed 7hermal. Power (MWt):- 3411

/-

~

!4i Nameplate: Rating (Gross'HWe)t;

1197- <

'5

$. 'Dealgn E.lectrica11 Rating (Not MWe): 1148 F  !

j 6; Maxitnum Dependable Capacity -(Gross M!O 1197.(Initial design value) i 7.; Huximum Dependable. Capacity (Net HWe) , .

,1148 (Initial design'value):

8...If Chan.gesl0ccur:in Capacity-Ratings'(Items Number 3 Through-7) -

q j

Since Last ReportO Give Reasons _ Not ADD 11 cable _, ,

'j

9. Power Level To Which Restricted, If Anya, 'None-
10. Reasons For Re strictions. ,If Any a :,,,,,,,,,_AJDolicable ,

l c This Monti. Yr..to-Date Cumulative j l

11; Hours In Reporting Period 744.0' 2360.0- 3028950  :

12. Number of Hours. Reactor Was Critical , 227.9 227,97 422.3 13.: Reactor Reserve' Shutdown Hours 50.8' 50.8 50.8,

"> ;14. Hours Generator,On-Line 0.0 0,0- 0.0 5 1$. Unit Reserve ~ Shutdown Hours 0.0 -0;O '00-.

16; Gross Thermal Energy Generated (MWH). 31981- 31981 33071 'l

17. Gross Elec. Energy Generated (MWH) 0 0 0
. 18l, Net Electrical Energy Generated (MWH) 0 0 0 g L 19. Unit Service Factor 0.0 0.0 '0.0 j p 20. Unit ~ Availability Factor 0- 0

. 0.0 0.0

! 21. Unit Capacity Factor (Using HDC Net) 0.0- -0.0 'O.0  :!

22. Unit; Capacity Factor (Using~ DER Net)- 0.0 0. 0 ' O.0 j 23.= Unit Forced Outage Rate .

0.0 0.0 0.0- j l

1

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

-None d

25. If Shut Down At End Of Report Period. Estimated Date Of Startupi 04/01/90 j
26. Prior to Commercial Operations. Forecast Achieveds j

.i

, INITIAL CRITICALITY 1989' 06/13/89 i INITIAL ELECTRICITY 1990 Not ADolicable ' j COMMERCIAL' OPERATION 1990 Not ADDlicable '1 1

i l-o lof 6 l I

r d

W

- Wf 'm' On >.'

f '

ii k'

{4y jfj,jjf:glgle

, 1 f, '

l y+'

a .8 , .a.. .

5 5:S V, -AVERAGE DAILY-UNIT. POWER. LEVEL' My . cy,f , -

~

.g w- DOCKET NO.- '$0-443' W 4 ,

1UNITc Seabrook 1

.DATE 04113190 1

COMPLETED BY. P. Hardone-

. TELEPHONE (603) 474 9521

! , , (Ext. 4074)

), HONTH WARCH. 1990 >

(!-i , .+

!. 7, , \-

'O 2 UJ DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY.-POWER LEVEL-.

., .(MWe-Net)t  : (MWe-Ne t ) .

(n ,:

1 0 '

16 0 a

, ,2l 0 17- '0-3 0- 18 0-4 -0 -19 -0

'S '0 2 0 -' 0' 6- 0 21- 0-7 O 22 0' 6' O 23 6'

-9 0 24 0 10 0 2E O 11' O 26: 0 12 0 .27 0-s13 0- 28 0 m

14 0 29 0~

15 0' 30 0 31- O c,

INSTRNCTIONS

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

Compute to the nearest whole megawatt.

l

-2 of 6-lt k i il

.I b$ ,

^

- Aj

LNIT SHUITOWNS AND IONER REUCTICNS DOOTT NO. 50-443 LNIT S & vok 1 4 DME 04/13/90 REPCRT MNIH MARDI, 1990 QEPIEITD BT P. Nardone TELEPIENE (603) 474-9521 (Ext. 4074)

No. Date Type l Duration Reason2 Method of Licensee Cause & Corrective Shutting Event Action to (Hours)

Down Reactor3 Report # Prevent Recurrence 1

90-01 03/22/90 S 5.3 A/F 1 N/A Rector shutdown to replace failed oackup power supply in rod control cabinet.

90-02 03/29/90 S 50.8 B/F 1 N/A Reactor shutdown while turbine vanlux.- is evaluating rotor differential expension indication ubom.vul during initial shell waming.

1 2 3 F: Forcal Paeson: Method:

S: Scheduled A-Fquipmmt Failure (Explain) 1-Manual B-Maintmance or Test 2-Manual Scram C-Refueling 3-Automtic Scrm D-Regulatory Restriction 4-Continued fr a E-Operator Training & License Examination previous month F-Administrative 5-Power Reductico G-Operational Error (Explain) (Duration = 0)

H-Other (Explain) 9-Other (Mlain) 3 of 6

DOCKET NG. 50-443

~ ~

INIT __Seabrook 1 IRTE 04/13/90 umurrnVE 1%INITNANCE Sul99RY Em SAFEIY REIATED EQUIPMENT CMPIETED BY P. Nardone REPORT ENIH MAROL 1990 _

TEIEPHONE f 603) 474-9521 (Ext. 4074)

Page 1 of 2 DA"_E SYSITM GMEGENT MhINTENANCE ACTI(N 03/10/90 Safety IIot Ieg Check valvo leakage o cuu.sd during 5%

Injection Injection testing. Reworked each valve's disc and Check Valve seat.

Loops 1,2,3,4 03/10/90 Safety 1-SI-P-6A and 6B Inboard ard outboard seals leaked on Injection Train A and B both ptmps. Replaced all seals.

Safety Injectiart Ptmps 03/15/90 Safety Cold Iag Check valve leakage occurred during 5%

Injection Injection testing. Reworked Icop 1, 2 and 3 valve's Check Valve disc and seat. Repla d Icop. 4 valve.

Icops 1,2,3,4 03/16/90 Lau.pcy 1-DG-1B Ebel injector No. 5 leaked ir.ternally Diesel' Train B causing engine to misfire and vibrate Generator Diesel Gaterator excessively. Replaced defective fuel Engine injector.

4 of 6

j u , , . ... .

. l 50--443 DOOGT NO.

~ ~

TJGT Seabrook 1 DNIE 04/13/90 wKKtL'nVE MAINTENANO:

SUMMARY

EIR SAFETY REIATED EQUIPMENT CDfPIE1TD BY P. Nardone REPCRP KNIH MARGI, 1990 TELEPIINE (603) 475-9521 (Ext. 4074)

Page 2 of 2 DATE SYSTEM GlMPONENT MAINTENANCE ACTICN 4

03/18/90 Containment 1-00P-V-2 arxi 3 During containment purge operation, valves Bui3 ding Train B went to part-ially closed position. Re-On-Line Purge Inside Containment placed ruptured diyuam in both air o Isolation valves exhausters for each valve.

03/19/90 Main Steam 1-MS-V-86 Valve failed to close fr a Train B Remote Steam G eerator A Safe Shutdown Panel during surveillance Main Steam test. Repla d defective hydraulic Isolation valve solenoid valve.

03/21/90 Radiation 1-RM-RM-6506 A armi B Condensation in detector housings caused Monitoring Train A and B GM tubes to go into saturation. Replaced Control Rom both Gi tubes and installed desiccant in East Air Intake housings.

Monitor 5 of 6 L_ __ ___ _ _ --

+

DOCKET 10. ' 50-443 11 NIT h hrook 1 o DNTE 04/13/90 O NPIRIED BY P.- Nardone TELEPHDNE (603) 474-9521 (Ext. 4074)

RITUELI!G IN!TRVATICN RBJUEST

1. Name of facility: Seabrook 1) nit 1
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 liocwe amendnent?

tlnknown at this time.

5. Scheduled date(s) for subnitting licensing action and supporting information ,

Not Applicable ,

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

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

None

7. We number of fuel assemblies (a) in the core and (b) in the opent fuel attS ge pools i (a) In Core 193 (b) 0
8. We 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 assablies:

Present licensed capacity: 1236 No increase in storage capacity requested or planned.

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

i l

Licensed capacity of 1236 fuel assemblies based on sixteen  ;

refuelings and full core offload capability.  !

W e current licensed capacity is adequate until at least the  !

year 2010.

6 of 6 4

l

~