ML20054A044

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Incident Reporting Sys Rept Re 810522 Reactor Site Alert Due to High Leakage Into Drywell
ML20054A044
Person / Time
Site: 05000000, Browns Ferry
Issue date: 05/29/1981
From:
ORGANIZATION FOR ECONOMIC COOPERATION & DEVELOPMENT
To:
Shared Package
ML19240B432 List:
References
FOIA-81-380 NUDOCS 8204150241
Download: ML20054A044 (2)


Text

i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-293 Pilgrim I 3/13/82 DATE COMPLETED BY C. G. Whitney 617-M -7900 TELEPHONE

""U' MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 0 0

1 g7 2

0 13 0

0 0

3 g9 4

0 20 O

0 0

5 33 6

0 0

7 y

0 0

3 24 0

9 3

10 26

!I 27 0

0 12 3

N/A 13 29 i

0 N/A I4 30 0

N/A 15 3j 0

16 INSTRUCTIONS On th:s format. list the aversge dady un:t power levelin MWe Net for each day in the reporting mentn. Compute to the nearest wnoie megawar t o /~7 )

8204150241 811109 PDR FOIA CONNOR 81-380 PDR

. = _ -

I

}

a OPERATING DATA REPORT DOCKET NO.

50-293 DATE 03/13/82 CONIPLETED BY G.G. Whitney TELEPil0NE 617-746-7900 OPERATING STATUS t

Pilgrim 1 Notes

1. Unit Name:
  • "" U '
2. Reporting Period:
3. Licensed Thermal Power (SlWt):

1998.

4. Nameplate Rating (Gross.\\lWe):

678.

5. Design Electrical Rating (Net 51We):

655.

690.

)

6. Slaximum Dependable Capacity (Gross SIWE):

l

7. Slarimum Dependable Capacity (Net 51We):

670.

S. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons:

NONE

9. Power Lesel To Which Restricted.lf Any (Net.\\lWe):

NONE

10. Reasons For Restrictions.If Any:

N/A This Slonth Yr..to.Date Cumulatise i

672.0 1416.0 80856.0

11. Hours in Reporting Period i
12. Number Of Hours Reactor Was Critical 0.0 0.0 56033.3
13. Reactor Resene Shutdown Hours 0.O nn n.n j
14. Hours Generator On.Line 0.0 0.0 54277.9
15. Unit Resene Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (.\\lWH) 0.0 0.0 92817888.0
17. Gross Electrical Energy Generated (NIWii, OJ 0.0 30911234.0 lb. Net Electrical Energy Generated (5thHs 0.0 0.0 29694484.0
19. Unit Service Factor 0.0 0.0 67.1 0.0 0.0 67.1
20. Unit Availability Factor 0.0 0.0 54.8
21. Unit Capacity Factor (Using SIDC Net) 0.0 0.0 56.1 1
22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Outage Rate nn 0.0 10.0
24. Shutdowns Scheduled Oser Nest 6 51onths (Type. Date.and Duration of Each t i

i Refuel and Maintenance Outage commenced 9/26/81 i

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

Scheduled for March 21, 1982 l

26. Units in Test Status (Prior to Commercial 0peration P Forecast Achiesed i

INITI A L CRITICA LITY INITIAL ELECTRICITY CO\\l\\lERCl \\L OPER ATION

~~

50-293 UNil SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N AME Pilcrim I DATE 1/11/M COMPLETED BY G. G. Whitnev REPORT MON 111 Februarv, 1982 TELEPHONE 617-746-7400 We E

E

$g 3

$ $Q Licensee E t, K

Cause & Corrective No.

Date g

3g 4

is5 Event gy pO Action to y5 5

3 g =g H

Report u v) L Present Recurrence o

u O

18 81/09/26 S

672.0 C

5 N/A RC FUELXX Refuel Outage Continues I

2 3

4 F: Forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A-Equipment Failure (Explain) 1 Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram.

Entr> Sheets for Licensee C Refueling 3-Automatic Scram.

Event Report (LER) File (NilRI.G-D-Regulatory Restriction 4-Oiher ( Explain) 0161)

E Operator Training & license Examination F-Administ rative 5

G-Operational Error (Explain)

Estubis 1 - Same Source (9/77)

Il Other (Explain)

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION Summary of Operations for February

, 1982 The unit has been shut down all month for the 1981 Refueling Outage. All outage work continues.

Safety / Relief Valve Challenges for February, 1982 Report Requirement: TMI T.A.P.

II.K.33 No challenges for this month.

Refuel Outage

REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in a letter to Mr. G.C. Andognini dated January 18, 1978:

For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.

1.

The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.

2.

Scheduled date for next Refueling Shutdown:

September, 1983 3.

Scheduled date for restart following refueling: November, 1983 4.

5.

Due to their similarity, requests 4, 5, 6 6 are responded to collect-ively:

6.

The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x8R design, as loaded the previous outage con-sisting of 112 P8DRB282 assemblies and 60 P8DRB265 assemblies.

7.

(a) There are 580 fuel assemblies in the core.

(b) There are 936 fuel assemblies in the spent fuel pool.

8.

(a) The station is presently licensed to store 2320 spent fuel assemblies.

The actual spent fuel storage capacity is 1770 fuel assemblies at present.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 834 fuel assemblies.

  • Note: The refueling information supplied with the January, 1982 Monthly Report was incorrect. The information supplied in this month's re-port is the same as was reported in December, 1981.

__ ~,

P1LGRiti NUCLEAR iuWtR 61A110a ov.a u MAJOR SAFETY RELATED MAINTENANCE

FEBRUARY, CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT RECURRENCE ASSOCIATED L.

61 Diesel Aux Gas Broken Choke Replaced Cable N/A Motor to Comp.

Cable 63 Door Interlocks Inop Abuse During Replaced Defec-N/A Outage tive components 10 1001-60 Removed Valve 81-53 Replaced - Set PM Operator Update Limits 10 1001-7A, 7C Logic Malfunction Corroded Rebuilt Electri-81-64 Open Con-cally - Replaced tacts flex & gaskets 10 1001-36A Sheared Bolts Replaced & Tor-81-057 qued Bolts Use Maximum Allowable Torque 29 P208-D & E Rebuild Pumps Vib Readings Normal Wear - Researching Material Balanced E Change 3

CRD Line Hangers Loose Bolts, Miss Tighten & Torque 82-005 ing Clamps HPCI Turbine SIL Performed SIL Repair RCIC Turbine SIL Performed SIL Repair 12 1201-5*

Seal Ring Leaking Replaced Seal Ring h

i

~

PMLut%1ki NUCLEAR l'UWER S tA11uN Hua Ait 1

m MAJOR SAFETY RELATED MAINTENANCE FEBRUARY CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT REConRENCE ASSOCIATED L.

3 CRD 30-15 Flange Leak Replace 111 Valve 3

CRD 30-35 Flange Leak Tightened Flange 3

CRD 06-35 Leaking Replace 111 Valve 3

'CRD 14-35 Leaking Replace 111 Valve 3

CRD 18-19 Leaking Replace 111 Valve 3

CRD 30-11 Leaking Replace 111 Valve 3

CRD 34-19 Leaking Replace 111 Valve 3

CRD 38-15 Leaking Replace 111 Valve 3

CRD 38-35 Leaking Replace 111 Valve 50 Torus Vessel Gouged Repaired Gouges 81-61 3

CRD 10-19 Flange Leak Retorqued 3

CRD '38-39 Flange Leak

.Retorqued.

e G

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