ML20244E564
| ML20244E564 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/31/1989 |
| From: | Eenigenburg E, Paramore G, Reid J COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| 3752A, 87-471, NUDOCS 8906200394 | |
| Download: ML20244E564 (45) | |
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.) Dr:sdtn Nucher Power Stition i
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R.R. #1
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Morris, Illinois 60450 i
b - Telephone 815/942-2920(
June 1, 1989 EDE LTR: #89-471 I
Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC~
20555 Attention:- Document Control Desk l
Subject:
Monthly Operating Data Report Dresden Nuclear Power Station Commonwealth Edison Company pocket Nos.50-010. 50-237 and 50-249 Gentlemen:
l 1
Enclosed is the Dresden Nuclear Power Station Monthiv Operating Summary Report for May 1989. This information is supplied to your office in accordance with the instructions set forth in Regulatory Guide 1.16.
l Please note that the report format has been restructured in order to i
' 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.100FR50.59 reporting information (including descriptions of facility changes, tests and experiments) will be submitted in a more j
timely manner.
Sincerely, E. z D. Eenig'en urg I
Station Md er Dresden Nuclear Power Station
)
EDE:GP:jmt Enclosure cc: Region III, Regulatory Operations, U.S. NRC lilinois Dept. of Nuclear Safety State of Illinois U.S. NRC, Document Management Branch Nuclear Licensing Administrator Nuc. Sta. Div. Vice Pres.
Manager, Tech. Serv. Nuc. Sta, j
G. Paramore (2) 3 NRC Senior Resident Inspector Site Quality Assurance Superintendent BWR Engineering Group Comptroller's Office PIP Coordinator INP0 Records Center File /NRC Op. Data File / Numerical
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4 I M TELY NRC SUfftARY OF OPERATING EXPERIENCE.
CHANGES. TESTS. AND EXPERIMENTS PFA REGUTA1 DRY CUIDE 1.1.6 AND 10 CFR 50.59 ZDR DRESDEN NUCLEAR POWER STATION CQ990NWEALTH EDISON CGtPANY IMII DOCKET LICENSE 1
050-010 DPR-2 2
050-237
'DPR-19 3
050-249 DPR-25 1
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i4 r 16BLE OF CONTENTS 1.0 Introduction j
2.0 Summary of Operating Experience 2.1 Unit 2 Monthly Operating Experience Summary 2.2 Unit 3 Monthly Operating Experience Summary 3.0 Operating Data Statistics l
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 Unique R' porting Requirements 4.0 e
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 Elgnt or Procedure Chances. 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 2 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 5.6.2 Unit 3 l
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1.0 Introduttinn 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 and John Reid of the Dresden Technical Staff, telephone numbers (815)942-2920 extension 2364 and 2334 respectively.
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~2.0 SIDMARY OF OPERATING RYPERIENCE FOR MAY. 1989 1b 2.1 UNIT'2 MONTHLY OPERATING EXPERIENCE
SUMMARY
l 05-01-89'to'05131-89
.. Unit'2 entered'the month on_line and operating at'
.approximately 645 MWe. :The Unit was operated.in:
F
-Economic Generation. Control,'or.'as directed.by the Corporate Load Dispatcher. -The Unit remained on line for the' duration'of the month.
~
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'2.0'
SUMMARY
'OF OPE 3ATING EXPERIENCE FOR MAY. 1989 IL h
'2.2l UNIT 3' MONTHLY OPERATING EXPERIENCE
SUMMARY
- . H 05-01-89 to 05-06-89.
. Unit'3 entered the month on line, operating at
- approximately 768 MWe.
05-06-89 to 05-29-89 At approximately 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on May 6,.1989, the Unit.
was shut down for a planned transformer (TR-3)-
replacement..
~05-29-89 At approximately 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, the reactor was made critical.
05-30-89 At approximately 0046 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />, control rods were re-inserted bringing. the reactor to a.'suberitical=
conditionLto investigate a double ~ indication problem-on reactor head vent valve 3-220-46.. After the valve was successfully exercised through three open/ closed > cycles, startup.was recommenced..The reactor was again made critical at 0324' hours'.
The reactor was subsequently saberitical between 0340-and 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br /> while a rod block alarm was repaired.. 31-89 At 0440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br />, the main generator was synchronized.
An orderly unit shutdown was then initiated to cold shutdown conditions ~in order to perform repairs:to the primary containment drywell-inner interlock door.
(Unsatisfactory leakage of the inner door was observed during a local: leak rate - test. Although' the outer door was satisfactory, the shutdown was performed prior to entering the interlock in order to ensure that no violation of primary containment integrity requirements occurred). At 2037 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.750785e-4 months <br />, the reactor was made subcritical and remained suberitical for the remainder of the month.
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.3.0 OPERATING DATA STATISTICS
- 3J 0PERATING DATA REPORT-UNIT TWO -
DOCKET NO. 050-237 UNIT DRESDEN TWD.
DATE Ane 1,1989 COMPLETED BY G.M. PARAMORE TELEPHONE (815)-942-2920 DPERATING STATUS
- 1.. REPORTING PERIOD:
May 1989 GROSS HOURS IN REPORTING PERIOD:
744
- 2.. CURRENTLY AUTHORIZED POWER LEVEL (MWt):-
2,527-MAX DEPEND CAPACITY (MWe-Net):
77*
DESIGN ELECTRICAL RATING (MWe-Net) 794 3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Met):
n/A 4.
REASONS FOR RESTRICTION (IF ANY):
N/A REPGRTING PERIOD DATA THIS MONTH YEAR-TO-DAli CUMULATIVE 5.
TIME REACTOR CRITICAL (HOURS) 744.0 2,391.5 125,937.4
' 6.
TIME REACTOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0
- 7. - TIME GENERATOR ON-LINE (HOURS) 744,0 2,306.5 120,331.9 8.
TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 9.
THERMAL ENERGY GENEPATED (MWHt-Gross) 1,753,519 5,283,479 247,775,341
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 562,698 1,783.,503 79,188,236 1
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 536,239 1,617,344 74,860,250
- 12. REACTOR SERUICE FACTOR (%)
100.0 66.0 75.4
'I
- 13. REACTOR AVAILABILITY FACTOR (%)
10 0.0 66.0 75.4 l
1
- 14. SERVICE FACTOR (%)
100.0 63.7 72.1
- 15. AVAILIS!LITY FACTOR (%)
10 0.0 63.7 72.1
- 16. CAPACITY FACTOR (USING MDC) (%)
93.4 57.8 58.1
- 17. CAPACITY FACTOR (USING DESIGN MWe) (%)
98.8 56.2 56.5
- 18. FORCED OUTAGE FnCTOR (%)
0.0 3.3 11.1
- 19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Unit 2 is currently scheduled to begin a 7 day outage on 12/09/89 in order to facilitate performance of a Unit 3 125VDC battery discharge test.
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
NONE
bl'3.2OPERATiljDATAREPORT-UNITTHREE 3,
3.0 OPERATING DATA STATISTICS DOCKET NO. 050-249 UNIT DRESDEN THREE DATE hne 1,1989 COMPLETED BY G.M. PARAMORE TELEPHONE (815)-942-2920 -
.I OPERATING STATUS 1.
REPORTINGPERIOD:
May 1989 GROSS HOURS IN REPORTING PERIOD:
74 4 i
l 2.
CURRENTLY AUTHDRIZED POWER LEVEL (MWt):
2,527-MAX DEPEND CAPACITY (MWe-Net):
773 1
DESIGN ELECTRICAL RATING (MWe-Net) 794 4
3.
POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Met):
N/A 1
l 4.
REASONS FOR RESTRICTION (IF ANY): N/A REPORTING PERIOD DATA THIS MONTH YEAR-TO-DATE CliMULATIVE
- 5.. TIME REACTOR CRITICAL (HOURS) -
162.7
'2,872.9 115,781.2 6.
TIME REACTOR RESERVE SHUTDOWN (HCURS) 0.0 0.0 0.0
- 7.. TIME GENERATOR ON-LINE (HOURS) 135.5 2,b'07.1 107,931.2 8.
TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 0.0 l
9.
THERMAL ENERGY GENERATED (MWHt-Gross) 300,856 6,630,525 221,614,984 i
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 95,999 2,163,670 71,552,379'
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 87,045 2,063,078 67,800,504
- 12. REACTOR SERVICE FACTOR (t) 21.9 79.3 73.9
- 13. REACTOR AVAILABILITY FACTOR (t) 21.9 79.3 73.9
- 14. SERVICE FACTOR (t) 18.2 77.5 68.9
- 15. AVAIL 181LITY FACTOR (%)
18.2 77.5 68.9
- 16. CAPACITY FACTOR (USING MDC) (t) 15.1 73.7 56.0
- 17. CAPACITY FACTOR (USING DESIGN MWe) (%)
14.7 71.7 54.5
- 18. FORCED OUTAGE FACTOR (t) 5.4 7.1 12.5
- 19. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION CF EACHh Unit 3 is currently scheduled to begin its eleventh refuel outage on 11/18/89; the scheduled return-to-service date is 01/27/90, after completion of a ten week refuel outage.
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, ESilMATED DATE OF STARTUP:
06-01-89 i
_____-____=_______--________-___-___-O
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- ';, 2 - sl $ 'l's _-
3.3 AVERAGE DA'ILY UNIT POWER LEVEL pa
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-r DOCKET NO. 050-237 UNIT II DATE June ~l'. 1989-COMPLETED BY J. Reid i
TELE' HONE 815/942-2920-MONTH MAY. 1989 DAY ~
. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met)
-(MWe-Net) 1 734 17 743 l
'2 757 18 762-3 726 19 763 4
707 20 765 5
747 21-674 6
709 22 688 7
-696 23 689 8
696 24
-675 9
727 25 744 a
10 773 26 718 11 779 27 734 12 783 28 629 13 778 29 629 14 716 30 710 15 682 31 737 16 674 3752a
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.. 3.4 AVERAGE DAILY UNIT POWER LEVEL'
,y DOCKET NO. 050-249 l.
' UNIT III-
'DATE June 1. 1989 1'
COMPLETED'BY J. Reid
' TELEPHONE 815/942-2920
-MONTH' MAY. ' 1989 DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL -
(MWe-Net)
(MWe-Net)
.1
~771 17
- 8'
-2' 766-18 '
3-760
- 19. '4 727 20
-8 5
714 21
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3.7 STATION MAXIMUM DAILY ELECTRICAL LOAD DATA l
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DRESDEN STATION f.
MAY, 1989'
'i i
' HOUR MAXIMUM DAILY LOAD gy.
ENDING KW-1 1500 1.596.000 2
1600 1.595.800 i
.i 3'
0100 1'.583.700-J l
4 1600 1.598.600 je.
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5 1100 1.602.700 1
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1500 787.600
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8 0800 758.000 j
9 1800 801.000 10 1200 812.200
'11 1800 812.500
.l 12 1800 813.100 13' 1900 812.300 l
14 2400 761.200 l
15 2200 803.400 l
16 2200 796.500 17 1400 800.000 18 1200 803.100 19 1:?00 802.400 j
20 1400 799.900 i
21 2300 791.700
.l 22 1900 796.500 l
1 23 1900 789.100
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24 1900 768.000
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25 1800 790.100 26 1900 804.200 27 2000 802.600 28 2100 714.400 29 1900 722.100 30 0900 777.900 j
31 1400 949.800 j
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4.1- ' MAIN STEAM RELIEF VALVE OPERATIONS Relief valve' operations during the reporting period. May, 1989, are summarized in the following table. The table includes-information as to'which re'ief:
valve'was actuated, how it was actuated, and the circumstances resulting in its actuation.
No. and Type-Valves of Plant' Description Unit Date Actuated Actuations Conditions of Events 2
No Unit 2 main steam relief and/or. safety valve actuations occurred during this reporting interval.
3 05-30-89 3-203-3A
-Simulated -
Startup A simulated Automatic automatic actuation Actuation test was performed Test-on relief valve 3-203-3A'in accordance with Dresden Operating.
Surveillance (DOS)
~
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l 4.2 0FF-SITE DOSE CALCULATION MANUAL CHANGES-i p
Most of the-
. Revision of the Off-Site Dose Calculation Manual (ODCM).
changes were editorial in. nature. Major substantial changes include
-using the child thyroid as critical receptor. Adding a' factor of 5 for-l sky _ shine calculations with' hydrogen addition, corrections of inaccuracies and inconsistencies in the text, and elimination of sections and equations not used.- Review number 89-8 was on-site reviewed on March 22.'1989. Off-site review was completed on May 4, 1989.-
i 4.3
' MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS'
\\
1 There were no major changes to the radioactive waste treatment systems l
J
'at Dresden during May, 1989. A commercial vendor is hired to-package, process, and transport solid radioactive wastes to burial in' accordance j
with 49CFR, 10CFR71, and 10CFR61 guidelines, i
)
1 4.4 FAILED FUEL ELEMENT INDICATIONS 1
I 4.4.1. Unit 2 j
Dresden Unit 2 fuel performance during May 1989 continued to show no indications of leaking fuel. This is based on the sum of the j
activities of the six noble gases as measured at the recombiner.- Based-1 on the reported data, Unit 2 had acceptable fuel performance during
'I May, 1989.
{
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4.4.2 Unit 3 j
i Dresden Unit 3 fuel performance during May 1989 continued to show no I
indications of leaking fuel. This-is based on the sum of.the activities of the six noble gases as measured at the.recombiner. Based
-)
on the reported data, Unit 3 had acceptable fuel performance during May 1989.
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-5.0-IL&NT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS; AND SAFETY RRt.ATED' l'
MAINTENANCE 1
5.1 Amendments to Facility' License or Technical Specifications The license amendments and/or Technical Specification changes which were approved and implemented for use during the reporting period are listed l
.below.-
.I 5.1.1 Unit 2
'None n
i 5.1.2 Unit 3 None 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.
3 described in the FSAR which were approved during the month of May, l
1989.
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5.3 Significant Tests and Experiments.Not Described in the FSAR (UNITS 2 and-3) y Significant special proce'dures involving tests not describedfin the FSAR which were approved during the month of May 1989 are listed below.
Procedure No.
Procedure Title / Description-SP 89-5-54 Post-LOCA Containment Hydrogen and Oxygen Monitor System maintenance and inspection.' This Special Procedure was written to allow required testing, until a permanent instrument surveillance revision concerning the oxygen monitors is implemented.
SP 89-5-60 This procedure was needed for calibration of survey meters and the HP-220A hand held directional probe to' allow use of the instruments in the Unit 3 Drywell.
SP 89-5-59 This special procedure was performed to analyze.
performance of the Unit 2 High Pressure Coolant Injection (HPCI) system turbine hydraulic control system.
SP 89-5-58 This special procedure verifies the proper operation of.the Exception Report Sequence Monitoring Program that monitors the operation of the Bailey network 90 feedwater level control system.
SP 89-5-57 This procedure test monitors Transformer 3 after the transformer was replaced and returned to service.
SP 89-5-56 This Special Procedure was written to implement additional ASME Code requirements for leak rate testing. This one time test will be used to acquire baseline leak rate data.
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.Completsd S;fsty Ralotcd Modifications (Unita'.2 cnd 3)
~ ' -
4 t
Unit 2 and Unit'3 safety related modification packages closed during the month of May, 1989.are listed below.. Only modifications which have been.
L,
' 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..
l Modification No.
Description i
u.
M12-2-86-24D This modification provided for the rearrangement-of the High Pressure Coolant Injection'(HPCI) system controls and' indicators. A HPCI flow
.)
indicating controller was replaced with a signal i
converter on Panel 902(3)-3 and a square root converter on Panel 902(3)-3.
l M12-2-86-41A This modification was to upgrade small bore torus piping and supports to meet the Mark I design j
loads. The modification consists of' rerouting the' Containment Atmosphere Dilution and Monitoring (ACAD/ CAM) piping lines from the torus i
such that the lines are no longer attached to.the catwalk and installing an anchor to isolate the l
Mark I loads.
i
- )
1
'1 I
4 i
3752a
is' d); a
$I m
..5.6 Temporary System Altarctions (Uniti 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. ~ Alterations. 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 draining process.are not included.
L The ' fo11owing tables summarize the' temporary-system alterations -
performed during May, 1989.
Temporary JSystem.
Installation Removal' Alteration No.
Description.
Daig
'Date-II-38-69 902-54 Panel to silence 5-1-89 5/1/89 spurious alarm.
II-39-89'
-Jumper prevents the motor.
5-2-89 6-1-89 for damper 2/3-9472E from running continuously.
Pending repairs.
,II-40-89 Alteration adds an 5-10-89 additional bearing to the HPCI room cooler.
.II-41-89 Alteration removed 5-11-89 5-11-89 the master recirculation flow controller for repair and calibration.
II-42-89 Alteration installed 5-27-89 pressure dampening snubber on the MSL Low pressure sensing line.
l l
I 3752a
=:q,7, _..
'nuv sin >
'/
b/;
~
v, 5.6;2) Unit 3-r i
3
?~
L'lemporary; e
TSystem
' Installation
-Removal-
- Alteration No.
Description :
Date Date
~III-11-89 Alteration utilized the 5-4-89.
6-2 30 cire water pump breaker
'to-perform a.through 1 '
fault test'on'the' Unit 3 main power transformer.
'III-12-89 Alteration allows line:
.5-5-89:
5-21-89 n
bus transfers between busses 35,36, and 37 for
' breaker, maintenance.
111-13-89 Alteration disabled'the.
5-6-89 5-27-89:
~ deluge system for the main D
power. transformer to
- facilitate replacement.
~
"III-14-89 Alteration removed the:
.5-17-89:
5-18-89 master'recirc. flow controller.for-repair
.and calibration.-
i l
l.
i 1.'
3752a