ML20246A207
| ML20246A207 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/31/1989 |
| From: | Eenigenburg E, Paramore G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| 89-625, NUDOCS 8908220406 | |
| Download: ML20246A207 (29) | |
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j/_h Commonwrith Edison 7
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O f Dresdin NuclStr Powsr StIllon -
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Morris, lilinois 60450
Telephone 815/942-2920 August 1,l1989-
.EDE LTR: #89-625 Directhr, 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 50-249 Gentlemen:
Enclosed is the Dresden Nuclear Powe'r Station Month 1v Ooeratina Summary Report for July 1989.. This information is supplied to your office in accordance with'.the instructions set-forth in Regulatory Guide 1.16.
Please note that the report format has been restructured in order to provide a more comprehensive data base.- Beginning with the January, 1989 report, the information which had been previously submitted to your attention on an-annual basis in accordance with 10CFR50.59 is being included on a monthly basis as part of the monthly summary report.
In-this manner, the 10CFR50.59 reporting information (including descriptions of facility changes, tests and experiments) will be submitted.in a more timely manner.
c-Sincerely, E. D. Eenigenburg Station Manager-Dresden Nuclear Power Station EDE:GP:jmt Enclosure j
cc: Region III, Regulatory Operations, U.S. NRC Illinois Dept. of Nuclear Safety, State of Illinois U.S. NRC, Document Management-Branch L
Nuclear-Licensing Administrator Vice Pres. - BWR Operations General Manager, Tech. Serv.
G. Paramore (2)
NRC Senior Resident Inspector Site Quality Assurance Superintendent l-BWR Systems Group Comptroller's Office INPO Records Center File /NRC Op. Data
$f File / Numerical 1
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MONTHLY.NRC SUfflARY OF OPERATING EXPERIENCE.
CHAMEES. TF.STS. AND EXPERIMENTS r-PER REGULATORY GUIDE 1.16 AND 10 CFR 50.59 EQR DRESDEN NUCLEAR POWER STATION
'CG990NWEALTH EDISON CGIPANY llHLT DOCKET LICENSE 1
050-010 DPR-2 2
050-237 DPR-19 3
050-249 DPR-25 4054a
=.y-TABLE OF CONTENTS 4
E 1.0 Introduction b
2.0' Sr--rv of Operatine Eroerlence o
L
-2.1 Unit 2 Monthly Operating Experience Summary 2.2 Unit 3 Monthly Operating Experience Summary
'3.0 Operating Data Statistics j
3.1 Monthly ~0perating Data'. Report - Unit 2 L.
3.2 Monthly l Operating' Data Report - Unit 3 3.3 Average' Daily Power I4 vel 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. Unique Reporting Requirements 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 ' Plant or Procedure Changes. Tests. Experiments.-and Safety Related Maintenance.
-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 Experiments Not Described in the FSAR
-(Units l2'and~3)'
5.4 Safety Related Maintenance (Units 2 and 3) 5.5 Completed Safety Related Modifications 5.6 Temporary System Alterations 5.6.1 Unit 2 l
5.6.2 Unit.3 4054a i
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___________________.--_________J
i 4
i 1.0 Introduction l
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 all three Dresden units was Sargent and Lundy of Chicago, Illinois.
This report was compiled by Gerrine Paramore of the Dresden Technical
' Staff, telephone number (815)942-2920 extension 2364.
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,b 2.0'
SUMMARY
OF' OPERATING EXPERIENCE FOR JULY. 1989 a
L'
~
2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE
SUMMARY
'07-01-89 to-07-11-89f
'Dresden Unit 2 entered the month on line and operating at approximately 672 MWe as. requested by:the Load Dispatcher.
07-12-89 to 07-14-89 On July 12, 1989 at 1049 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.991445e-4 months <br /> with Unit 2 operating at 63% power while performing Dresden l.
Technical Staff Surveillance (DTS) 500-2, Functional Testing of Reactor 1 Protection System (RPS) Motor Generator (MG) Set and RPS Reserve Power Supply,' Channel
'A' half primary containment Group I isolation and half scram
+
signals could not be reset promptly due to difficulties encountered in resetting the
'A' main steao line (MSL) logrithmic radiation monitor (LRM). A spurious MSL tunnel area high temperature trip then' occurred, resulting in a full primary containment Group I-isolation and reactor scram. The cause of the MSL area high l
temperature trip was attributed to setpoint
' drift. The root cause of the MSL LRM reset difficulties.(which occurred during transfer of power supplies in accordance with DTS 500-2) is under investigation. As corrective action, the
'A' MSL LRM was replaced, in addition to all of the Channel
'B' MSL tunnel area temperature switches. The safety significance of this event was minimal since the primary containment isolation and reactor scram functions occurred as designed. Operations Department personnel responded immediately by verifying that a valid Group I condition had not occurred and proceeded with a controlled scram recovery.
07-15-89 to 07-31-89 For the remainder of the month Unit 2 remained on line and operated at loads requested by-the Load Dispatcher.
i
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2.0
SUMMARY
OF OPERATING EXPERIENCE FOR JULY.'1989 f,
.'2.2 UNIT.3 MONTHLY OPERATING EXPERIENCE
SUMMARY
.07-01-89 to'07-22-89 Unit 3 entered the month on line and operating at approximately 560,MWe...The unit operated.in.
Economic Generation Control.or as'~ directed.by the Load Dispatcher for the remainder of the month.'
07-22-89 A load reduction was-initiated at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> ~on. July H
22,;1989,.in order to bring turbine first stage pressure below 45% rated steam-flow in accordance with Technical Specification Table 3.1.1 upon'.
~ discovery that the No. 2 turbine stop' valve would not. provide a half scram signal during surveillance
. testing..A load _ increase.from 200 MWe was begun at
.:1615 hours on July 22, 1989, following completion of repairs and. testing.
07-22-89 to 07-31-89 Unit 3 operated the remainder of the month at loads requested by the Load Dispatcher.
l l
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- 3.0 OPERATING DATA STATISTICS '
3.1.0 PIRATING DATA REPDRT-UNIT TWO
.-f DOCKET NO. 050-237
~'
UNIT DRESDEN TWO DATE AUGUST 1, 1989 COMPLETED BY G.M. PARAMORE TELEPHONE (815)-942-2920 l '0PER AT!'NG ' ST ATUS.
- 1. - REPORTING PERIOD:
JULY 1989~
GROSS HOURS IN REPORTING PERIOD:
744
- 2. ; CURRENTLY AUTHORIZED POWER LEUEL (MWt>s 2,527-HAX DEPEND CAPACITY (MWe-Net):
772 DESIGN ELECTRICAL RATIWG (MWe-het) 794'
- 3.. PONR LEVEL TD WHICH RESTRICTED (IF ANV) (MWe-Net):
n/a
- 4. ' REASONS FOR RESTRICTION (IF ANY):
REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CUMULATIVE
-~5.
TIME REACTOR CRITICAL (HOURS) -
712.7 3,624.2 127,370.1
.6.
TIQE REACTOR RESERVE' SHUTDOWN (HOURS) 0.0
' O.0 0.0
7.
- TIQE GENERATOR ON-LINE (HOURS!
696.7 3,723.2 121,748.6 8.
TIRE GENERATDR RESERVE SH'JTDOWN (HOURS) 0.0 0.0
- 0. 0 -
19e THERQAL ENER0V GENERATED (MWHt4ross) 1,314,532 7,980,709 250,472,571
- 10. ELECTR'ICAL ENERGY CENERATED (MWHe-Gross)-
412,048 2,549,623 80,034,356 111. ELECTRICAL ENERGY GENERATED (MWHe-Net) 389,654 2,418,355 75,661,261
- 12. REACTOR SERVICE FACTOR (%)
95.8 75.2 75.6 13.- REACTOR AVAILABILITY FACTOR (%)
95.8 75.2 75.6
- 14. SERUICE FACTOR (%)
93.6 73.2 72.3
- 15. AVAILABILITY FACTOR'(%)-
93.6 73.2 72.3
- M. CAPACITY FACTOR (USING MDC) (%)
67.8 61.6 58.2 l-17. CAPACITY FACTOR (U$lk0 DESIGN KWe) (%)
66.0 59.9 56.6
- 18.- FORCED OUTAGE FACTOR (%)
6.4 3.3 11.1 1
E l19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
L 125VDC Test Outage, 12-9-89, 7 days l
l.
20.. IF SHUTDOWN AT END OF REPOET PERIOD, ESTIMATED DATE OF STARTUP:
l n/a l
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.~,3.0 0FERATING DATA STATISTICS:
RL2.'0PERRf!NG DATA REPORT-UNIT THREE.'
DOCKET NO. 050-249 L
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'E UNIT DRESDEN THREE
^
DATE AUGUST 1, 1989 COMPLETED FY G.M. PAR AMORE TELEPHONE (815)-942-2920
- OPERATING STATUS -
4 (1.60EPORTINGPERIOD:.
JULY 1989.
GROSS HOURS IN REPORTING FERIDB:
744 (21 ' CURRENTLY AUTHORIZED F0WER LEVEL (MWt):
2,527 MAX DEFEND CAPACITY (MWe-Net):
773
- DESIGN ELECTRICAL RATING,.(Me-Net) 794
- 3. > POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
n/a 3 REASONS FGR RESTRICTION (IF ANY):-
REPORTING PERIOD DATA-
'THIS MONTH YEAR-TO-DATE CUMULATIVE-
'5: TIME REACTOR CRITICAL (HOURS)L 744.0 4,350.4 117,258.7
- . 6.-s TIGE REAtTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 7.
TIME GENERATOR DN-LINE.(HOURS).
744,0 4,257.2 109,381.3 l8.-? T!WE SENERATOR RESERVE SHUIDOWN (HOURS) 0.0 0.0 0.0
- 9.E THERMAL ENERGV GENERATED IMHt-Gross) 1,574,837 9,641,871-224,626,330 19.. ELECTRICAL ~ ENERGY DENERATED (MWHe-Gross) 499,727 3,114,648
.72,503,357 l
l 111 ELECTRICAL ENERGY CENERATED (MWHe-Wet) 475,224 2,967,617
' 68,785,043 l-I
- 12. AEACTOR SERUICE' FACTOR (t) 100.0 85.5 74.2
- 13.- REACTOR AVAILABILITY FACTOR (%)
100.0 85.5 74.2 Id. ERU!CE FACTOR (%)
100.0 83.7 69.2 p
.a.' AVAILABILITY FACTOR (%).
100.0 83.7 69.2 l!
4 l[ '16. CAPACITY FACTOR.(USING MDC) (%)
82.6 75.5 56.2-17cCAPACITV FACTOR (USING DESIGN Se) (%)
B0.4 73.5 54.8 g
' 18. FORCED OUTAGE FACTOR (%)
0.0 5.1 12.4 i
I I I19. SRUTbOWNS SC4EDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
I; Refuel Outage, 12.19-89,' 11 weeks
- t..
1-
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUF:
n/a i
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y m
- y.i;'l t..
3.3 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-237 2
+
UNIT II-
'\\
DATE August 1. 1989 COMPLETED BY_Q.P. Paramore TELEPHONE 815/942-2920
-[ MONTH JULY. -' 1989 '
r
' DAY'
- nVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 672
-17 571
'2-576 18 698
- 659~
19 748
~4-
'440 20 757 LS.
494' 21 573-6-
'506 22 632
~7 513 23 622
-8L 476' 24 760 9
"443 25 744 10' 411 26 676 11 387 27 589 12 205 28 524 13
-8 29 501 14-196 30-503 15 423 31 522 16 474' l
.4054a
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3.4 AVERAGE ~ DAILY UNIT POWER LEVEL-i" DOCKET NO. 050-249-UNIT III DATE August 1. 1989 COMPLETED BY G.P. Paramore
,[
TELEPHONE-815/942-2920
~ MONTH-JULY.-1989
. DAY AVERAGE DAILY POWER LEVEL
' DAY AVERAGE DAILY POWER LEVEL' (MWe-Net).
(MWe-Net),
- 1 561' 17 745
'762-2
-570 18.
!3 732 19 759 j
J41 514-20 757 15' -
553 21 745 6-564 22 1.t01 7
644 23 582 8
-477 24 754 9-466 25 759
- 10 480 26
-758 11L 457 27 710 12 551 28 687 13 665-29 749 14 670 30 763 s
15 651
'31 757 16 623 L
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3.7 STATION MAXIMUM DAILY R1RCTRICAL LOAD DATA l
.DRESDEN STATION L,
l-
. JULY, 1989 HOUR-MAXIMUM DAILY LOAD
^
ENDING KW L
if 1-2200 1.405.600 2
2400 1 423.200 3
0900 1.504.200 4
0100
-1.199.900 5
1400 1.141.100 6
1600 1.144.500 7
1900 1.327.800 8
0100 1.093.700 9
2400 957.300 10 0000 0
11
'2200 982.100 12 0100 976.800 13 2200 759.900 14 2000 1.237.800 15
'2400-1.220.800 16 2400 1.280.900 17
-2400 1.473.200
'18 1000 1.553.900 19 2100 1.594.500 20 1100 1.594.100 21 2400 1.494.700 22 0100 1.473.000 23 2400
'1.535.500 24 1300 1.600.500 25 1700 1.590.600 26 1700 1.586.100 27 1100 1.390.500 28' 1000 1.290.800 29 2400 1.325.900 30 0100 1.328.500 31 0800 1.364.000
-4054a
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4.0.UNIOUE REPORTING REOUIROMENTS h
4.1 MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period. July, 1989, are summarized in the following table. The table includes information as to which a
relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.
No. and Type Valvea of Plant Description Unit Date Actuated Actuationa Conditions of Events 2
No Unit 2 main steam relief and/or safety valve actuations occurred during this reporting interval.
3 No Unit 3 main steam relief and/or safety valve actuations occurred during this reporting interval.
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L'2 4.2 0FF-SITE DOSE CALCULATION MANUAL CHANGES j
V I
There were no changes to the Off-Site Dose Calculation Manual during July, 1989.
4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREA*IMENT SYSTEMS There were no major changes to the radioactive waste treatment systems at Dresden during July, 1989. A commercial vendor is hired to package, process, and transport solid radioactive wastes to burial in accordance with 49CFR, 10CFR71, and 10CFR61 guidelines.
4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 Dresden Unit 2 fuel performance during July 1989 continued to show no indications of leaking fuel. Ynis is based on the sum of the 1
activities of the six noble gases as measured at the condenser off-gas recombiner. Based on the reported data, Unit 2 had acceptable fuel performance during July, 1989.
4.4.2 Unit 3 Dresden Unit 3 fuel performance during July 1989 continued to show no indications of leaking fuel. This is based on the sum of the activities of the six noble gases as measured at the condenser of f-gas recombiner. Based on the reported data, Unit 3 had acceptable fue) performance during July 1989.
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, 5.0-ILANT OR PROCEDUEE CHANGES; TESTS. EXPERIMENTS. AND SAFETY RELATEL MAINTENANCE
'l i
5.1 Amendments to Facility License or Technical Specifications i
The license amendments and/or Technical Specification changes which were approved and implemented for use during the reporting period'are listed below.
5.1.1 Unit 2 None l
i 5.1.2 Unit 3 None j
I i
5.2 Changes'to Procedures Which are Described in the FSAR (Units 2 and 3) l Table 5.2.1, attached, summarizes the revisions to procedures described in the FSAR which were approved during the month of July, 1989.
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I 5.3 Significant Tests and Experiments Not Described in the FSAR (UNITS 2 and 3)
{
Significant special procedures involving tests not described in the FSAR which were approved during the month of July 1989 are listed below.
Erocedure No.
Procedure Title / Description SP 89-6-66 Unit 2/3 daily construction testing of Reactor Building (RB) differential pressure (dP) during RB roof replacement to provide indication of RB secondary containment status in relation to roofing activities.
I SP 89-6-68 Unit 2/3 Secondary Containment Leak Rate. Test during the RB roof replacement to provide indication of secondary containment status in relation to the roofing activities.
5.4 Safety related maintenance (Units 2 and 3)
Safety related maintenance activities are summarized in the attached tables.
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5.5 Completed S:fsty Related Modifiestions (Units 2 and 3)
Unit 2 and Unit 3 safety related modification packages closed during the month of July, 1989 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 changes have been identified by their Design Change Control Modification Number.
Modification Nqi Description M12-2/3-81-24 This modification to the primary containment post-accident monitoring system provided improved sample piping. The sample piping was modified to route the containment samples to a monitor panel located outside the primar,7 containment.
M12-2-86-33 This modification provides an improved tube material, (AL-6XN) for use in the Low Pressure Coolant Injection (LPCI) heat exchangers. The new AL-6XN material was selected because it is less susceptible to pitting, which has been the major cause of tube failure with the original (70-30 Cu-Ni) tube material.
)
M12-3-86-47 This modification required the installation of new cables and rerouting of existing cables to maintain physical separation of two redundant channels within the suppression pool temperature monitoring system. The safety evaluation concluded that a postulated single failure of the redundant channels will not cause total loss of the suppression pool temperature monitoring systems.
4054a l
l
~
~
4
, 5.6 T;mporary Systcm Alteradmns (Unit 2 and Unit 3)
A " Temporary System Alteration" refers to electrical jumpers, lifted leads, removed fuses, fuses turned to non-conducting position, fuses moved from normal to reserve holder, temporary power supplies, test switches in alternate positions, temporary blank flanges, and spool pieces. 'dxerations controlled and documented as part of a routing out-of-service or other procedure, alterations which are a normal feature of system design, and hoses installed as part of a venting or p
draining process are not included.
The following tables summarize the temporary system alterations performed during July, 1989.
5.6.1 Unit 2 lemporary System Installation Removal Alteration Not Description Dalg Date II-49-89 Alteration to bypass 7-7-89 7/18/89 2C Reactor bailding exhaust fan back-draft damper air supply solenoid valve to close the damper during fan replacement.
II-50-89' Alteration to install 7-13-89 a jumper at the junction box of the #6 turbine bypass valve to clear an Electro Hydraulic Control (EHC) electrical malfunction alarm in the control room pending repairs to a broken cable.
II-52-89 Alteration to remove Low 7-18-89 7-18-89 Pressure Coolant Injection temperature recorder (TR-2-1540-5) for calibration.
4054a l
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________________________L
~
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-5.6.1.-Unit 2 Temporary System Installation Removal l
Alteration No.
Description Date Date
- j. -
II-53-89 Alteration to insta11' 7-19-89
. jumper in panel 902-4 to defeat isolation logic to permit operation of the Shutdown Cooling (SDC) heat exchanger. inlet valve (MOV-2-1001-?C) with recirculation water temperature greater than 350*F. This allows alignment of the 20 SDC system for fuel pool cooling, which is a normal feature of the i
SDC system.
11-54-89 Alteration to Jnstall 7-25-89 7-25-89 a dampening snubber in the sensing line of the Main Steam Line (MSL) low pressure switch (PS2-261-30B) to supress pressure surges and perturbations.
II-55-89 Alteration to install 7-28-89 dampening snubber in the sensing line of the SML low pressure switch (PS2-261-30B) to supress pressure surges and perturbations.
1 4054a
n y..
c i.
- 5. '6. 2 Unit 3-
. Temporary System
- Installation Removal Alteration No.
. Description ~
Date Date-III-21-89
_ Alteration-to remove 125VDC 7-5-89 7-6-89 the positive ground monitoring recorder for i:
repairs.
. III-22-89 Alteration to install
.7-11-89 separate cooling and return lines,to feed the
~ inner and after after coolers on the 30 Instrument air compressor.
- III-23-89 Alteration to remove 7-31-89 7-31-89' main steam line radiation-recorder (3-1705-11) in the control room back panel for, repairs.
. Radiation levels were l
monitored hourly from L
the MSL radiation monitors Luntil the recorder was repaired..
l 1
l 1.
4054a I'
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