ML20043G130
| ML20043G130 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/31/1990 |
| From: | Eenigenburg E, Maxwell D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| 90-391, NUDOCS 9006190099 | |
| Download: ML20043G130 (31) | |
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Commonweakh Edison l
Deeseen Nuc'nt Power 8ttion U
R.R. 01
}
e Morris, Illinois 60460 e
Telephone 81b/942 2920 l
June 1,1990 i
EDE LTR: #90-391 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Subject:
Monthly Operating Data Report Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos.50-010. 50-237. and FD-lh2 Gentlemen:
Enclosed is the D m den Nuclear Power Sisttien Monthly _QPirAling SummAIX Reparl for May, 1990. This information is supplied to your office in accordance with the instructions set forth in Regulatory Guide 1.16.
Please note that the report contains information which had been previously submitted to your attention on an annual basis in accordance with 10CFR50.59.
Cincerely,
- E$f' _ _ a([f
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StationM[ agger
. D. Ee gebutgj Dresden Nuclear Power Station EDE:GPtbjs Enclosure cct U.S. NRC Region III Office Illinois Dept. of Nuclear Safety. State of Illinois v'U.S. NRC, Document Management Branch Nuclear Licensing Administrator Vice Pres. - BWR Operations General Manager - Nuclear Services T. S. ENGR. (2)
NRC Senior Resident inspector Nuclear Quality Programs - Dresden Nuclear Engineering Manager Comptro11er's Office D. Eggett - Reliability Programs INPO Records Center File /NRC Op. Data File / Numerical I?G/10/1 1
?OO6190009 900531 l
c'OR ADOCLx03000010 1i R
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IRWITELY IRC BREl&RLOF_QFERATIllG EEFERIBICE.
CE&llGES. TESTE. ARID ERFERIIMITE PER REGUIATOILY GUIDE 1.16 ^" 10 CFL50.59 EE IEEEDElf.ItucLa&R FOWER STATi(Rf ce nem amALTE EDISGN O WIFAWY FOR IELiff0 UNII DOCKET LICENSE 1
050-010 DPR-2 2
050-237 DPR-19 3
050-249 DPR-25 l
l 216/10/2
1 i
TAaLE OF CONTENIS 1.0 Introduction
-2.0 S' - - rv of Operatina Experience l
2.1 Unit 2 Monthly Operating Experience Summary for May,1990 2.2 Unit 3 Monthly Operating Experience Summary for May, 1990 l'
3.0 Operatine Data Statistics 1
3.1 Monthly Operating Data Report - Unit 2 3.2 Monthly Operating Data Report - Unit 3 3.3 Average Daily Power Level Data - Unit 2 3.4 Average Daily Power Level Data - Unit 3 3.5 Unit Shutdown and Power Reduction Data - Unit 2 3.6 Unit Shutdown and Power Reduction Data - Unit 3 3.7 Station Maximum Daily Load Data 4.0 1!nisut_Reportine Reanirements t
j 4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 4.2 Off-Site Dose Calculation Manual Changes 4.3 Major changes to the Radioactive Waste Treatment 4.4 Failed Fuel Element Indications 4.4.1 Unit 2 4.4.2 Unit 3 5.0 Ilant or Procedure changea. Testa. Experiments. and Safety Related i
MA ntenance l
5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 5.1.2 Unit 3 5.2 Changes to Procedures Which are Described in the Final Safety Analysis Report (FSAR) (Units 2 and 3) 5.3 Significant Tests and Experimm<ts Not Described in the FSAR (Units 2 and 3) l 5.4 Safety Related Maintenance (Units 2 and 3) l 5.5 Completed Safety Related Modifications 5.6 Temporary System Alterations 5.6.1 Unit 2 J
5.6.2 Unit 3 L
Z16/10/3
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1.0 Introduction Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Commonwealth Edison Company of Chicago, Illinois. Dresden Station is located at the confluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris, Illinois.
Dresden Unit 1 is a General Electric Boiling Water Reactor with a design net electrical output rating of 200 megawatts electrical (MWe). The unit is retired in place with all nuclear fuel removed from the reactor vessel. Therefore, no Unit 1 operating data is provided in this report.
Dresden Units 2 and 3 are General Electric Boiling Water Reactors with design net electrical output ratings of 794 MWe each.
Waste heat is rejected to a man-made cooling lake using the Kankakee River for make-up and the Illinois River for blowdown.
The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.
This report was compiled by Donald C. Maxwell of the Dresden Technical Staff, telephone number (815)942-2920 extension 2489.
4 Z16/10/4
?.0 StBetARY OF OPERATINC EEPERIENCE FOR MAY. 1990 i
2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE
SUMMARY
05-01-90 to 05-31-90 Unit 2 entered the month on line and. operating at approximately 803 MWe. The unit cperated in Economic Generation Control or a'. loads requested by the System Load Dispatcher f9r the remainder of the month with an availability of 100% and a capacity factor of 94.4%.
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7 S190ERY OF OPERATING EXPERIENCE FOR MJLY.1990 o
2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE SUlfRRY j
1 :,
i 05-01-90 to 05-31-90 Unit 3 entered the month on line and operating i
at approximately 751 MWe. The Unit operated in Economic Generation Control or at loads requested by the System Load Dispatcher for tne j
remainder of the month with an availability of 100% and a capacity factor of 95.11.
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Z16/10/6
o 3.0 OPERATING DATA REPORT 3.1 OPERATING DATA REPORT - UNIT 'IWO DOCKET NO._
050-237 DATE __)une 1. 1990 COMPLETED BY D. C. Maxwell TELEPHONE 815/942-2920 OPERATING STATUS 1.
REPORTING PERIOD: MAY. 1990 GROSS HOURS IN REPORTING PERIOD 744 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWe):
2,527 MAX DEPEND CAPACITY (MWe-Net) 772 DESIGN ELECTRICAL RATING (MWe-Net) 794 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A 4.
REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA This Month Yr-to-Date Cumulative 5.
TIME REACTOR CRITICAL (HOURS) 744.0 3,350.7 134,130.9 6.
TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 7.
TIME GENERATOR ON-LINE (HOURS) 744.0 3,326.7 128,378.2 8.
TIME GENERATOP RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 9.
THERMAL ENERGY GENERATED (MWHt-GROSS) 1,832,747 7,988,953 266,106,144 10.
ELECTRICAL ENERGY GENERATED (MWHe GROSS) 585,669 2,566.492 85,060,841 11.
ELECTRICAL ENERGY GENERATED (MWHe-NET) 558,387 2,447,824 80,435,988 12.
REACTOR SERVICE FACTOR (%)
100.0 92.5 76.3
- 13. REACTOR AVAILABILITY FACTOR (%)
100.0 92.5 76.3 14.
SERVICE FACTOR (%)
100.0 91.8 73.0
- 15. AVAILABILITY FACTOR 100.0 91.8 73.0 16.
CAPACITY FACTOR (USING MDC) (%)
97.2 87.5 59.3 17.
CAPACITY FACTOR (USING DESIGN MWe) (%)
94.5 85.1 57.6 18.
FORCED OUTAGE FACTOR (%)
0.0 8.2 10.8 19.
SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE DATE AND DURATION OF EACH)
REFUELING OUTAGE CURRENTLY SCHEDULED for 9-1-90 thru 11-11-90 20.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A Z16/10/7
3.0 OPERATING DATA REPORT 3.2 OPERATING DATA REPORT - UNIT THREE DOCKET NO.
050-249 DATE June 1. 1990 COMPLETED BY D.C. h well TELEPHONE 815/942-2920 OPERATING STATUS 1.
REPORTING PERIOD:.MAY. 1990 GROSS HOURS IN REPORTING PERIOD 744 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWe):
2,527 MAX DEPEND CAPACITY (MWe-Net) 773 DESIGN ELECTRICAL RATING (MWe-Net) 794 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A 4.
REASONS FOR RESTRICTIONS (IF ANY): N/A REPORTING PERIOD DATA This Month Yr-to-Date Cumulative 5.
TIME REACTOR CRITICAL (HOURS) 744.0 2,462.1 122,696.5 6.
TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0.
7.
TIME GENERATOR ON-LINE (HOURS) 744.0 2.325.9 114,688.1 8.
TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 9.
THERMAL ENERGY GENERATED (MWHt-GROSS) 1,829,578 5,577,055 237,204,475 10.
ELECTRICAL ENERGY GENERATED (MWHe GROSS) 588,751 1,807,671 76,519,916 11.
ELECTRICAL ENERGY GENERATED (MWHe-NET) 562,425 1,719,395 72,574,765 12.
REACTOR SERVICE FACTOR (%)
100.0 68.0 74.2 13.
REACTOR AVAILABILITY FACTOR (%)
100.0 68.0 74.2 14.
SERVICE FACTOR (1) 100.0 64.2 69.4
- 15. AVAILABILITY FACTOR 100.0 64.2 69.4 16.
CAPACITY FACTOR (USING MDC) (%).
97.8 61.4 56.8 17.
CAPACITY FACTOR (USING DESIGN MWe) (%)
95.2 59.8 55.3 18.
FORCED OUTAGE FACTOR (%)
0.0 11.2 12.1 19.
SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE DATE AND DURATION OF EACH)
NONE 20.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A Z16/10/8
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3.3 AVERAGE MILY UNIT POWER LEVEL DOCKET NO. 050-237 UNIT 11 DATE_).une 1.1990 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920 MONTH MAY. 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 767 17 769 2
763 18 724 3
754 19 7_68 4
770 2fs 741 5
767 21
_Z72 6
751 22 769 7
766 23 756 8
752 24 751 9
759 25 726 10 761 26 695 11 759 27 742 12 743 28
-731 13 723 29 735
'14 751 30 755 15.
760 31 74.2 16 758 Z16/10/9
j 3.4 AVERAGE DAILY llNIT POWER LEVEL i
DOCKET NO, 050-249 UNIT III
)
DATE June 1. 1990 COMPLETED BY D.C. Maxwell TELEPHONE 815/942-2920 MONTH MAY. 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 717 17 774 2
772 18 775 3
761 19 755 4
781 20 743 5
763 21 762 6
749 22 743 7
764 23 738 8
753 24 756 9
765 25 733 10 767 26 722 11 764 27 723-12 748 28 774 13 739 29 774 14 759 30 771 15 768 31 770 16 764 216/10/10
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DOCKET NO. 050-249 UNIT NAME na m eg uh1T 111 3.6 UNIT SHUTDOWNS AND POWER REDUCTIONS DATE Ji=== 1. 1990 COMPLETED BY D. C. 18-mil' TELEPHONE (815)942-2920 REPORT MONTH MAY. 1990 METHOD OF LICENSEE SYSTEg COMPO f CAUSE & CORRECTIVE-1 2
NO.
DATE TYPE DURATION REASON SHUTTING EVENT CODE CODE ACTION TO (HOURS)
DOWN REACTOR REPORT #
PREVENT RECURRENCE NONE i
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4 F: Forced Reason:
Method:
Exhibit G-Instructions for S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Ecram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & Licensee Examination 5-Load Reduction F-Administrative G-Operational Error 5 Exhibit I - Same Source ZR16/10 H-Other (Explain)
nf.
t 307 C0fMONWEALTL' EDISON COMPANY - DRESDEN NUCLEAR POWER STATION a
o MAXWUM DAILY ELEC11tICAL LOAD FORM IVR THE MONTH OF MAY, 1990 HOUR MAXIMUM DAILY LOAD DAY ENDING KW 1
2000 1.594.100 2
0600 1.61.2.300 3
2300 1.614.000 4
2200 1.6214500 5
0100 1 1212hD0 6
1100 1.588 100 7
0900 1.605.800 8
1100 1.603.300 9
1000 1.608.900 10 1100 1.618.700 11 1100 1.624.800 12 1700__
1.592.600 13 1000 1.560.400 r'
14 1400 1.612.600 15 1000 1.608.100 16 1600 1.603 QQO 17 2400 1 111.100 1:
1800 1.613.900 19 1200 1.615.900 20 1900 1.583.500 21 1300 1.611.800 22 0900 l'.581.300 23 0100 1.578.500 24 0900 1.599.400 25 1200 1.534.800 26 2200 1.567.200 27 1900 1.592.200 28 1000 1.606.900 29 1200 1.604.600 30 0100 1.600.300 l
31 1200 1.596.300 l
ER16/10/13 1
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'f 4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period, May,1990, are sununarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.
l No. and Type Valves of Plant Description Unil Dale Actuated Actuations ConditinnA pf Events 2
No Unit 2 Main Steam Relief and/or safety valve actuations occurred during this reporting period.
3 No Unit 3 Main Steam Relief and/or safety valve actuations occurred during this reporting period.
b ZR16/10/14
I 4.2 0FF-SITE DOSE CALCULATION MANUAL (ODOM) CHANGES j
I No ODCM changes were reported for the month of May,1990.
4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREAIMENT SYSTEMS There were no major changes to the Radioactive Waste Treatment Systems at Dresden during the May, 1990 reporting period.
l 4.4 FAILED FUEL' ELEMENT INDICATIONS 4.4.1 Unit 2 Dresden Unit 2 fuel performance during May, 1990 continued to show nn 1
indications of leaking fuel.
This is based on the sum of the l
activities of the six noble gases as measured at the recombiner.
Based on the reported data. Unit 2 had acceptable fuel performance.
4.4.2 Unit 3 Dresden Unit 3 fuel performance during May,1990 continued to show no in(.ications of leaking fuel. This is based on the sum of the activities of the six noble gases as measured at the recombiner.
Based or the reported data. Unit 3 had acceptable its.1 perf ormance.
5.0 EIANT OR PROCEDl!RE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RE1AIED MAINTENANCE 5.1 Amendments to Facility License or Technical Specifications' No new amendments to facility license or technical specifications were approved for use during May, 1990.
5.2 Changes to Procedures Which are Described in the FSAR (Units 2 and 3)
Table 5.2.1, attached, summarizes the revisions to procedures described in the FSAR which were approved during the May, 1990 reporting period.
ZR16/10/15
.n TABLE 5.2.1 CE*JiGES TO PROCEDURES WHICH ARE DESCRIBED IN THE FSAR (UNITS 2 AND 3)
PROCEDURE TYPE PROCEDURE NO.
PROCEDURE TITLE / DESCRIPTION SW9mRY OF CHANGES __
4 Dresden Administration DAP 12-2 Notification Criteria for Unplanned Radiological Procedure (DAP)
Events and Performance Parameters i
NOTES: 1.
Administrative change; intent of procedure unchanged.
2.
Changed for clarification, intent of procedure unchanged.
3.
Changed to incorporate requirements for new equipment; intent of procedure unchanged 4.
Changed to implement impreved testing / calibration methodology; intent of procedure unchanged.
i ZR16/10/16
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5.3 Significant tcsts and cxperiments est d:scrib;d in tha TSAR (Units 2
& 3)
Significant special procedures involving tests not described in the FSAR which were approved during the month of May, 1990 are listed below.
Procedure No.
Procedure Title / Description SP 90-05-81 Post-LOCA Containment Hydrogen and Oxygen Analyzer System Functional Test The purpose of this procedure is to provide inscructions to Functionally Test the Drywell and Torus Containment Atmosphere (CAM) System as required by Technical Specification 4.2.E., Post Accident Monitoring Instrumentation.
5.4 Safety Related Maintenance (Unit 2 and 3)
Safety related maintenance activities are summarized in the attached tables.
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Z16/10/17 l
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4 5d DRESDEN UNIT ?
F.
SMETY RELATED MAINTENANCE NATURE OF LER DR DUTAGE MALFtmCTION EDUIPMENT MAINTENANCE MUMBER CAUSE RESULT CORRECTIVE ACTION CR0 E-9 18-35 CtRRECTIVE N/A REBUILT DRIVE WR Db5799 CLASS 1 PIPING (MSIP)
PREVENTIVE N/A PECTORNED MSIP ON WELDS
..:s WR D78946 MOV 2-1001-5B PREVENTIVE N/A MOUNTED VOTES SENSOR ON VALVE VDKE AND WR D79003 TESTED 2-1705-2F PREVENTIVE ve/A REPLACED MSL RAD RECORDER 2A AND 2C MSL RAD MONITOR WR DS3011 RECORDER 2-1705-2K PREVENTIVE N/A REPLACED MSL RAD RECURDER 2D AND 20 MSL RAD MONITOR WR D33012 RECORDER 2-2406A PREVENTIVE N/A CALIBRATED RECORDER CH. A POST-LOCA H2 RECORDER WR D84647 L'CI GLAND SEAL COND. Il0TWELL PREVENTIVE N/A FtmCTIONALLY TESTED SWITCHES Hl/LO LEVEL ALARM WR D85390 LPRM 38 40-41 LORRECTIVE N/A WROTE WRSSs746 TO RD TACE DETECTOR WR D85492 APRM 92 CORRECTIVE N/A REPLACED F'0WER TEST POT MR DS6335 D2 CRD ANCHOR BOLT PREVENTIVE N/A TOROUED ALL BOLTS WR D87903 2
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e-DRESDEN UNIT 3 SAF ETY RELATED MAINTENANCE NAT1RE OF LER DR DUTAGE MALFUNCTIDN EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CDRRECTIVE ACTIDN 3-MO-1001-2A PREVENTIVE N/A REBUILT LIMITOR90E, REPLACED IkIFTER NR D70230 SPRING, M.S. CLUTCH STEM NUT.
LOCRNUT AND ALL GASKETS AND SEALS LINE 3-1402-16" LX PREVENTIVE N/A (FSRADED SUPPORT NR D70960
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MR D74895 6723-73009 152-3323 CURRECTIVE N/A
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CORRECTIVE N/A REBUILD CRD AND REFtACED ALL SEALS NR D71913 2/3 SPARE ELECTEDMATIC CORRECTIVE' M/A REBUILT VALUE AND TESTED NR D72972 2/3 SPARE ELECTROMATIC CORRECTIVE N/A REBUILT VALVE NR U72973 2-7504D PREVENTIVE N/A REPLACED COVER AND TIGHTENED SCREWS AMBIENT AIR INLET M0 HR D87904 2-7504A PREVENTIVE N/A F(EPLACED CDVER AND TIGHTENED SCREWS AMBIENT AIR INLET MD NR D87905 LIMITokDUE DP-7507A lREVENTIVE N/A CllECRED GUALITY OF GREASE AND C1EANED NR D87906 AND LUCED VALVE STEM 2-7505A PREVENTIVE N/A CHECKED QUALITY OF GREASE AND CLEANED LIMITOROUE NR D87907 AND LUBED VALVE STEN LIMITOROUE 7504A PREVENTIVE N/A CHECKED QUALITY OF GREASE AND CLEANED NR D8/908 AND LUBED VALVE STEM MOV 2/3 7504A
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.'5 5 Complot:d Safoty Raletsd Modifiestions_(Units 2 cnd 3)
'l Unit 2 and Unit 3 safety related modification packages closed during v
the month of May, 1990 are_ listed below. Only modifications which have been completely closed are listed; modifications which are authorized for use but not completely closed will be reported based on the date of their final closure.
For ease of reference, the j
changes have been identified by their design change control'
'j modification number, j
l Modification No.
Description M12-2(3)-80-16 This modification was performed to upgrade the existing Service Water Effluent Radiation Monitoring System by replacing the old monitor with Eberline Off-Line Liquid Samplers having a
~
shielded detector and background subtraction.
Thenewmonitorhas'grabsamplecapgeityand i
responds to activity of 10- to 10- pCi/cc in accordance with Technical Specification j
requirements. The safety evaluation concluded that the margin of safety is not reduced.
l M12-2-87-20 The purpose of this modification was to reduce the possibility of inadvertant override of an automatic initiation signal to the Isolation Condenser Return Valve M0-1301-3. This was done by replacing the control switch with a four position switch (pull-to-lock, close, auto, open). The sofety
[
eval'uation concluded that the margin of safety is not reduced.
M12-2-89-13 This modification was performed to replace the existing underdrain strainer assemblies of the Condensate Demineralizer Cation Tank 2-5508 with new-
.l Johnson Screen Element strainer assemblies in the cation tank vent line.- The safety evaluation concluded'that the margin of safety is not. reduced.
1 5.6 Temporary System Alterations (Unit 2 and Unit 3)
A " Temporary System Alteration refers to ciectrical, jumpers, lif ted l -l
' leads, removed fuses, fuses turned to non-conducting position, fuses moved from normal to reserve holder, temporary power supplies, test 7
switches in alternate positions, temporary blank flanges, and spool D'
pieces. Alterations controlled and documented as part of a routine out-of-service or other procedure, alterations which are a normal feature of system design, and hoses installed as part of a venting'or draining process are not included.
5.6.1 Unit 2 Z16/10/18
L v.
,.1 Tempor:ry-
- ',s'*
Systes-.
Installation Removc1
-,1
. Alteration No.
Description Dalm Date II-12-90 Installed temporary 5/08/90 Furmanite seal on leaking
}
portion of High Pressure Coolant Injection (HPCI)
System Condensate Drain Line (2-2323-1"-LX) pending permanent repairs.
5.6.2 Unit 3
+'
2 g
Temporary System Installation Removal p'#'
Alteration No.
Description Data Date III-14-90 Alteration to remove the 5/09/90 5/22/90 junction box (K3015) cf the 30 circulation Water Pump to facilitate cleaning of the motor.
}
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.zi6/10/19
.