ML20058H867
| ML20058H867 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/30/1993 |
| From: | Kraft E, Munro W BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-155, NUDOCS 9312130251 | |
| Download: ML20058H867 (7) | |
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j BOSTON EDISON i
Pilgrim Nuclear Power Stauon Pocky Hill Roso Plymouth, Massachusetts 02360 E. S. Kraft, Jr.
Vice Presider.t Nuclear Operations and Staten Drector December 10, 1993 BECo Ltr. #93-155 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
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License No. DPR-35
. Docket No. 50-293' l
f NOVEMBER 1993 MONTHLY REPORT l
i In accordance with PNPS Technical Specification' 6.9.A.2, a copy of the Operational-l Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning.
Should you have any questions concerning this report please contact me directly.
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E. S. Kr t Jb.
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Attachment cc:
Mr. Thomas T. Martin R?qional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road i
King of Prussia, PA 19406
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t Senior Resident Inspector i
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9312130251 931130'
.[DR ADOCK 05000293-
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OPERATING DATA REPORT DOCKET NO.
50-293 I
DATE December 10, 1993
(
COMPLETED BY:
W.
Munro l
TELEPHONE (508) 747-8474 y
OPERATING STATUS NOTES 1.
Unit Name Pilgrim I 2.
Reporting Period November 1993 3.
Licensed Thermal Power OKWt) 1998 l
4.
Nameplate Rating (Gross MWe) fla 5.
Design Electrical Rating (Net MWe)
' fil l
6.
Maximum Dependable Capacity (Gross MWe) fil 7.
Maximum Dependable Capacity (Net MWe) fla 8.
If Changes Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons:
None 1
9.
Power Level To Which Restricted, If Any (Net MWe): None 10.
Reasons For Restrictions, If Any: N/A f
This Month Yr-to-Date Cumulative 11.
Hours In Reporting Period 720.0 8016.0 183888.0 l
12.
Number of Hours Reactor Was Critical 643.3 6338.9 112197.5 13.
Reactor Reserve Shutdown Hours 0.0 0.0 0.0 j
14.
Hours Generator On-Line 615.1 6138.6 108045.0 15.
Unit Reserve Shutdown Hours 0.0 0.0 0.0 16.
Gross Thermal Energy Generated (MWH) 1170360.0 11708736.0 189717552.0 17.
Gross Electrical Energy Generated (MWH) 401170.0 4021150.0 64155144.0 I
18.
Net Electrical Energy Generated OKWH) 386159.0 3868361.0 61661277.0 19.
Unit Service Factor 85.4 76.6 58.8 l
20.
Unit Availablility Factor 85.4 76.6 58.8 21.
Unit Capacity Factor (Using MDC Net) 80.0 72.0 50.0 l
22.
Unit Capacity Factor (Using DER Net) 81.9 73.7 51.2 23.
Unit Forced Outage Rate 0.0 4.4 11.9 24.
Shutdowns scheduled over next 6 months (type, date, and duration of each) - None
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25.
If shutdown at end of report period, estimated date of startup - Unit operating l
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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-293 DATE Tin cnrnko v in '993 COMPLETED BY:
W. Munro
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TELEPHONE (508) 747-8474 MONTH November 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) l 1
663 17 629 2
663 18 388 3
662 19 661 4
663 20 663 i
1 1
5 64 21 481 6
0 22 665 l
7 0
23 663 l
8 0
24 655 9
49 25 664 10 577 26 665 11 661 27 665 12 660 28 665 13 648 29 664 14 663 30 663 f
15 663 31 N/A 16 663 This format lists the average daily unit power level in MWe-Net for each day in the-6 reporting month, computed to the nearest whole megawatt.
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r BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER. STATION DOCKET NO. 50-293 I
OPERATIONAL
SUMMARY
FOR NOVEMBER 1993 The unit started the reporting period at 100 percent core thermal power (CTP). This power level was essentially maintained until November 5, 1993, when at 0554 hours0.00641 days <br />0.154 hours <br />9.160053e-4 weeks <br />2.10797e-4 months <br /> the main turbine was manually tripped off line and a controlled shutdown of the reactor was initiated. The reactor mode switch was placed in shutdown at 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br /> on November 5, l
1993.
The shutdown was initiated to facilitate a leak repair on the "A" train 4th Point Feedwater Heater. While in cold shutdown, Safety Relief Valve (SRV) 203-3A was replaced.
On November 9, 1993, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, the reactor was made critical and the unit was synchronized to the grid at 1451 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.521055e-4 months <br />. Reactor power was increased and attained 100 percent CTP on November 10, 1993, at approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />. On November 12 and 13, i
1993, reactor power was briefly reduced to 95 percent and 60 percent CTP, respectively, to perfarm maintenance on Hydraulic Control Unit (HCU) 10-35.
On November 17, 1993 at approximately 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was reduced to approximately 58 percent CTP to facilitate a leak repair on the "A" train 2nd Point Feedwater Heater.
Following maintenance reactor power was increased to 100 percent CTP at approximately 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on November 19, 1993.
On November 21, 1993, at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, reactor power was reduced to 50 percent CTP to perform a scheduled thermal backwash of the main condenser, and accomplish maintenance on the 2nd Point Feedwater Heaters. The unit attained 100 percent CTP at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br /> on November 21, 1993.
On November 24, 1993, reactor power was briefly reduced in response to a problem with the "A" Recirculation Motor Generator Set.
Following the brief power reduction, 100 percent CTP was achieved and was maintained for the remainder of the reporting period.
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1 SAFETY RELIEF VALVE CHALLENGES MONTH OF NOVEMBER 1993 l
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Requirement:
NUREG-0737 T.A.P.
II.K.3.3 l
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DATE: November 9, 1993 i
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l VALVE:
- 203-3A
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t REASON:
Manually opened for testing purposes following replacement of the valve.
i An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor l
pressure, auto signal (ADS) or control switch (manual).
Ref. BECo ltr. #81-01 date 01/05/81.
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J REFUELING INFORMATION The follosing refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 18, 1978:
1 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: April 1, 1995 t
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Scheduled date for restart following next refueling: June 5, 1995 4.
Due to their similarity, requests 4, 5,
& 6 are responded to collectively under #6, 5.
See #6, 6.
The new fuel loaded during the 1993 refueling outage was of the same design as loaded in the previous refueling outage and consisted of 140 assemblies.
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7.
(a)
There are 580 fuel assemblies in the core.
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(b)
There are 1629 fuel assemblies in the spent fuel pool.
8.
(a)
The station is presently licensed to store 2320 spent fuel assemblies. The actual usel?e spent fuel storage capacity is 2320 fuel assemblies.
(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 691 fuel assemblies.
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MONTH NOVEMBER. 1993 PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED TO PREVENT LER-RECURRENCE MAIN STEAM (MS)
SAFETY RELIEF DISCHARGE UNDER REMOVED.SRV
'IO BE DETERMINED.
N/A SYSTEM VALVE (SRV)
TEMPERATURE INVESTIGATION.
BODY (SERIAL
- 203-3A INCREASED FROM
- 008) AND PILOT 115 DEGREES 'IO VALVE (SERIAL 240 DEGREES
- 1207), AND (PR93.9340)
INSTALLED BODY (SERIAL #1208).
AND PILOT VALVE (SERIAL #1040).
PERFORMED PROCEDURE 8.5.6.2 " MANUAL OPENING OF ADS VALVES" AT APPROXIMATELY 935 PSI, SUCCESSFULLY.
REACTOR CONTROL HCU 10-35 ACCUMUIATOR UNDER REPLACED TO BE DETERMINED.
N/A ROD DRIVES (CRD)
LEAKING.
INVESTIGATION.
ACCUMULATOR FOR AND HYDRAULIC HCU 10-35.
CONTROL UNIT POSTWORK TEST (HCU) SYSTEM PERFORMED SUCCESSFULLY.-
"A" TRAIN 4TH TUBE LEAKS.
UNDER' PERFORMED EDDY REFER 'IO 93-026-00 SYSTEM
- POINT HEATER (PR93.9450)
INVESTIGATION CURRENT ASSOCIATED LER.
E-102A.
TESTING; 44=
LEAKING TUBES-WERE IDENTIFIED-AND PLUGGED.
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- NOT SAFETY RELATED'
e.
e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET 50-293 NAME; PILGRIM DATE: Qccomber 10. 1941 COMPLE W.
MUNRO TELEPH (508) 747-8474 REPORT NOVEMBER 1993 NO.
DATE TYPE DURATION REASON METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION (HOURS)
SHUTTING EVENT CODE CODE TO PREVENT RECURRENCE DOWN REPORT #
REACTOR 12 11-5-93 S
104.9 B
1 93-026-00 SJ HX
'A' TRAIN 4TH POINT FEEDWATER HEATER REPAIR OUTAGE.
13 11-18-93 F
0.0 B
N/A POWER REDUCTION TO REPAIR LEAKS ON FLANGES OF 2ND POINT FEEDWATER HEATEF.
'A' TRAIN.
14 11-21-93 S
0.O B
N/A POWER REDUCTION TO PERFORM A THERMAL BACKWASH OF THE MAIN CONDENSER AND TO COMPLETE MAINTENANCE ON THE 2ND POINT FEEDWATER HEATERS, A AND B TRAINS.
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2 3
4&5 F-FORCED A-EOUIP FAILURE E-OPERATOR TRAINING & LICENSE EXAMINATION 1-MANUAL EXHIBIT F & H S-SCHED B-MAIN OR TEST F-ADMIN 2-MANUAL SCRAM INSTRUCTIONS FOR C-REFUELING G-OPER ERROR 3-AUTO SCRAM PREPARATIONS Of D-REGULATORY RESTRICTION H-OTHER 4-CONTINUED DATA ENTRY SHEET 5-REDUCED LOAD LICENSEE EVENT REPORT 9-OTHER (LER) FILE (NUREG-1022
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