ML20042E326

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Monthly Operating Rept for Mar 1990 for Seabrook Unit 1
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)


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.. 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 9004200620 900331 m

ADOCK0500g3 PDR R

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New Hampshire Yankee Division of Public Service Company of New Hampshire s

P.O. Box 300

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

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OPERATING DATA REPORT

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' DOCKET NO.-

50-443 UNIT Seabrook 1-

1 iDATE 04f13190~

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COWPLETED BY P. Nardone (f

YELEPHONE 1603) 474-9521 9'

=(Ext, 4074) k'oj OPERATING STATUS:

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1., Unit Names' Stabrook Station Unit 1

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l2. Reporting-Periodi; HARCH 3990

3.

Licensed 7hermal. Power (MWt):-

3411

'5

/ -

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

1197-

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1148 F

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

6; Maxitnum Dependable Capacity -(Gross M!O 1197.(Initial design value) j i

7.; Huximum Dependable. Capacity (Net HWe)

,1148 (Initial design'value):

8...If Chan.gesl0ccur:in Capacity-Ratings'(Items Number 3 Through-7) q Since Last ReportO Give Reasons Not ADD 11 cable _,

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Power Level To Which Restricted, If Anya,

'None-

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10. Reasons For Re strictions.,If Any a :,,,,,,,,,_AJDolicable l

Cumulative j

c This Monti.

Yr..to-Date 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

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17. Gross Elec. Energy Generated (MWH) 0 0

0 18l, Net Electrical Energy Generated (MWH) 0 0

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19. Unit Service Factor 0.0 0.0

'0.0 j

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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 R

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

l 1

-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

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-AVERAGE DAILY-UNIT. POWER. LEVEL' M. cy,f,

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'$0-443' W

1UNITc Seabrook 1 4

.DATE 04113190 COMPLETED BY.

P. Hardone-1

. TELEPHONE (603) 474 9521 (Ext. 4074)

),

HONTH WARCH. 1990

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

2

.(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.

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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) l 2

No.

Date Type Duration Reason Method of Licensee Cause & Corrective (Hours)

Shutting Event Action to 3

Down Reactor 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

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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.

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DOOGT NO.

50--443 TJGT Seabrook 1

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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 Isolation valves exhausters for each valve.

o 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:

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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.

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