ML20141A986
| ML20141A986 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/30/1997 |
| From: | Abrell G, Jamila Perry COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.016, RTR-REGGD-1.016 JSPLTR-97-0093, JSPLTR-97-93, NUDOCS 9705150088 | |
| Download: ML20141A986 (14) | |
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Cornmonwealth idiwan Company
. Dresden Generating Station '
- ' 55c0 Norih Drexten Road ,
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, Morris. IL 60450 I
Tel 815-942 2920 May 5,1997 JSPLTR 97-0093 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Monthly Operating Data Report for April 1997 Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos.50-010,50-237, and 50-249 Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for April 1997.
This information is supplied to your ollice as required by Technical Specification 6.9.A.5, in accordance with the instructions set forth in Regulatory Guide 1.16. .
Sincerely, r
[/
. eple *r
. ' e Vice Pres ent Dresden Station Enclosure gL cc: NRC Region 111 Oflice Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident Inspector UDI,Inc. . Washington, DC File / Numerical 9705150080 970430 -
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MONTHLY NRC
SUMMARY
OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 !
FOR 6
DRESDEN NUCLEAR POWER STATION ?
cot 440NWEALTH EDISON COMPANY FOR APRIL 1997 a
i UNIT DOCKET LICENSE 1 050-010 DPR-2 i n
2 050-237 DPR-19 .
5 3 050-249 DPR-25 l i
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TABLE OF CONTENTS APRIL 1997 NRC REPORT t
4 l 1.0 Introduction :
i 2.0 Summary of Operating Experience 3
2.1 Unit 2 Monthly Operating Experience Summary. ;
2.2 Unit 3 Monthly Operating Experience Summary. ;
l 3.0 Operating Data Statistics l 3.1 Operating Data Report - Dresden Unit 2 !
3.2 . Operating Data Report - Dresden Unit 3 l 3.3 Average Daily Unit 2 Power Level ,
l 3.4 Average Daily Unit 3 Power. Level i 3.5 Unit.2 Shutdowns and Power Reductions F 3.6 Unit 3 Shutdowns and Power Reductions
- 4.0 Unique Reporting Requirements 4.1 Main Steam Relief and/or Safety Valve Operations -
Unit 2 and' Unit 3 1
4.2 Off-Site Dose Calculation Manual Changes 4.3 Major Changes to the Radioactive Waste Treatment Systems 4.4 Failed Fuel Element-Indications
- . 4 . 4 .1- Unit 2 4.4.2 Unit 3
'5.0 Technical Specification Amendments 5.1 Amendments to Facility License or Technical Specifications 5.1.1 Unit 2 1 5.1.2 Unit 3 i
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1.0 Introduction i l
Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Comed Company of Chicago, Illinois. Dresden Station is located at the confluence of the Kankakee and Des l Plaines Rivers, in Grundy County, near Morris, Illinois.
l 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 being decommissioned 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 i Water Reactors, each licensed at 2527 megawatts thermal. The gross outputs of Units 2 and 3 are 832 and 834 megawatts electrical, respectively, with design net electrical output ratings of 794 MWe each. The commercial service date for Unit 2 is 11 August 1970, and 30 October 1971 for Unit 3. ,
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. l This report for APRIL 1997, was compiled by Gary A.
Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 3749.
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2.0
SUMMARY
OF OPERATING EXPERIENCE FOR APRIL 1997 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 2 was on system at the beginning of the period near full power.
On April 10, 1997 the auxiliary contact assembly was found damaged for the bus 23 to 23-1 feed breaker during an inspection of electrical breakers. At 2112 all the Merlin Gerin electrical breakers were declared inoperable and preparations began for a unit shutdown. At 2236, commenced a load drop at 100 MWE per hour for a unit shutdown.
At 0857 on April 11, 1997 a manual scram was initiated at 150 MWE to complete the unit shutdown.
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SUMMARY
OF OPERATING EXPERIENCE FOR APRIL 1997 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 3 was shutdown during this period for refueling outage D3R14. s April 1, 1997, the Mode Switch was placed in REFUEL at 1245.
April 3, 1997, the first fuel bundle was removed from the core for sipping at 0210.
April 10, 1997, the core off-load was completed at 2104.
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- I 3.0 OPERATING DATA STATISTICS 3.1 OPERATING' DATA REPORT - DRESDEN UNIT TWO 1 l
l DOCKET No. 050-237 MAY 1, 1997 DATE
- COMPLETED BY G. A. ABRELL .,
TELEPHONE (815) 942-2920 1 OPERATING STATUS ,
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- 1. REPORTING PERIOD: APRIL 1997 1
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 772 ]
. ' MAXIMUM DEPENDABLE CAPACITY (MWe NET) : i DESIGN ELECTRICAL RATING (MWe Net): 794 !
- 3. POWER LEVEL TO WHICH RESTRICTED (MWe Net): No l j restrictions _
- 4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.1 of 1 this report. 1 REPORTING PERIOD DATA l PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE
, HOUh5 IN PERIOD 719 2,879 234,215 '
TTAE REACTOR CRITICAL 248 2,408 169,570 TD4R REACTOR RESERVE SHUTDolei (Hours) 0 0 0 l TIME GENERATOR ON-LINE (Hours) 248 2,408 161,423 TIME GENERATOR RESERVE SHUTDOtti (Hours) 0 0 1 THERMAL ENERGY GENERATED (MWHt Gross) 615,786 5,593,068 337,296,969 ELECYRICAL ENERGY GENERATED (MtfEHe Gross) 198,498 1,814,199 107,712,735 ELECTRICAL ENERGY GENERT.TED (MWEHe Net) 189,400 1,734,786 101,836,515 REACTOR SERVICE FACTOR (4) 34.5% 83.6% 72.4%
REACTOR AVAILABILITY FACTOR (%) 34.5% 83.6% 72.4%
GENERATOR SERVICE FACTOR (t) 34.5% 83.6% 68.9%
' 34.5% 83.6% 68.9%
GENERATOR AVAIIABLILITY FACTOR (%)
CAPACITY FACTOR (Using MCD Net) (%) 34.1% 78.1% 56.3% !
CAPACITY FACTOR (Using DER Net) (t) 33.24 75.9% 54.8%
FORCED OUTAGE FACTOR (t) 664 16.4% 12.9%
- 20. SHUTDOWN' 3CHEDULED OVER THE NEXT 6 MONTHS: NONE -
- 21. IF SHUTD001 AT END OF REPORT PERIOD, ESTIMATED DATE OF i
ST7tRTUP: May 2, 1997 t
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i 3.0 OPERATING DATA STATISTICS 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No. 050-249 DATE MAY 1, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS
- 1. REPORTING PERIOD: APRIL 1997
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe Net) : 773 DESIGN ELECTRICAL RATING (MWe Net): 794
- 3. POWER LEVEL TO WHICH RESTRICTED: No restriction
- 4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.2 of ;
this report.
REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE
$ HOURS IN PERIOD 719 2,879 223,535 6 TIM REACTOR CRITICAL 0 139$.6 157,253 7 TI M PEACTOR RESERVE SHUTDOWN (Hours) O.c e 0 8 TIM GENEHATOR ON-LINE (Hours) 0 1, 3 S e 14 9,8 H O 9 TIM GENERATOR RESERVE SHUTDOWN (Hours) 0.0 0 0 10 THERMAL ENERGY GENENATED (MWHt Gross) U 2,267,379 312,479,0bb 11 E12CTRICAL ENERGY GENERATED (DefEHe Gross) C 729,66/ 100,002,191 12 ELECTRICAL ENERGY GENERATED (MWEHe Net) - 4 , 0 S t. 686,361 94,768,862 l 13 REACTOR SERVICE FACTOR (4) 0.0% 48.5% 70.3%
14 REACTOR AVAILABILITY FACTOR (t) 0.04 48.5% 70.34 15 GENERATOR SERVICE FACTOR (4) 0.04 47.1% 67.09 16 GENERATOR AVAILABLILITY FACTOR (t) O.Oe 4 'l . I t 67.OV 17 CAPACITY FACTOR (Using MCD Net) (%) -0.7% 30.9% 54.94 18 CAPACITY FACTOR (Using DER Net) (%) -0.74 30.04 53.44 19 FORCED OUTAGE FACTOR (t) 0.uk 35.14 14.39
- 20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: In refuel outage D3R14. j i
- 21. IF SHUTDOWN A1 END OF REPORT PERIOD, ESTIMATED DATE OF J STARTUP: June 2, 1997.
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3.3 AVERAGE DAILY UNIT 2 POWER LEVEL DOCKET No. 050-237 UNIT Dresden 2 DATE. MAY 1, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTit : April-97 DRESDEN 2 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) 1 791 17 -4 ,
2 790 18 -4 3 785 19 -4 4 784 20 -4 5 788 21 -4 l 6 756 22 -4 l 7 792 23 -5 .)
8 792 24 -5 l 9 793 25 -5 j 10 787 26 -4 11 122 27 -4 )
12 -6 28 -4 13 -5 29 -5 14 -5 30 -6 15 -5 16 -4 (Note: negative values represent station loads) i j
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3.4 AVERAGE DAILY UNIT 3 POWER LEVEL 1 1
i DOCKET No. 050-249 :
UNIT Dresden 3 DATE MAY 1, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH: April-97 DRESDFE 3 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) ;
1 -8 17 -4 )
2 -8 18 -3 3 -8 19 -3 4 -0 20 -3 5 -8 21 -4 6 -8 22 -4 7 -8 23 -5 8 -8 24 -5 ;
9 -8 25 -5 1 10 -8 26 -4 11 -7 27 -4 j 12 -6 28 -4 13 -5 29 -4 14 -5 30 -5 15 -5 l 16 -4 (Note: Negative values represent station loads) i l
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3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS i l
REPORT MONTH OF APRIL 1997 NO DATE TYPE DURATION REASON METHOD LICENSEE SYSTEM COMPO- CORREC- ;
(1) (HOURS)* (2) OF EVENT CODE (4) NENT TIVE !
SHUTTING REPORT # CODE ACTIONS /
DOWN (5) COM-REACTOR MENTS (3) 3 970411 F 471 A 1 9708 EA BKR 2.1 i
i Year-to-date forced outage hours = 471 l Cumulative forced outage hours = 23,406 TABLE KEY:
(1) (3)
F: Forced Method: l S: Scheduled 1. Manual l
- 2. Manual Scram )
(2) 3. Automatic Scram j Reason: 4. Other (Explain) i A Equipment Failure (Explain) 5. Load Reduction j B Maintenance or Test C Refueling (4)
D Regulatory Restriction Exhibit G Instruction for E Operator Training & Preparation of Data Entry i Licensing Exam Sheets for Licensee Event j F Administrative Reports (LER) File !
G Operational Error (NUREG-0161) l I
H Other (Explain)
(5)
Exhibit I Same Source as Above. j i
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l 3.6 ' UNIT 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH APRIL 1997 NO DATE TYPE (1) DuPATION PIASON (2 ) METHOD OF LICEN?EE SYSTEM CCHPONENT CORPIC-(HOURS)* $ HUTTING EVENT CODE CODE (5) TIVE IGIN FEPOeT e (4) ACTIONS /
PI.ACTOP, COMMENTS (3) 1 970320 S 719 c 1 2.2 Year-to-date forced outage hours = 734 Cumulativt forced outage hours = 25,810 TABLE KEY:
(1) (3)
F: Forced Method:
S: Scheduled 1. Manual
- 2. Manual Scram (2) 3. Automatic Scram Reason: 4. Other (Explain)
A ., Equipment Failure 5. Load Reduction (Explain)
B Maintenance or Test (4)
C Refueling Exhibit G Instruction for D Regulatory Restriction Preparation of Data Entry E Operator Training & Sheets for Licensee Event Licensing Exam Reports (LER) File F Administrative (NUREG-0161)
G Operational Error H Other (Explain) (5)
Exhibit I Same Source as Above.
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4 4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - UNIT 2 AND UNIT 3 None
- 4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES None 4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS None 4.4 FAILED FUEL ELEMENT INDICATIONS 4.4.1 Unit 2 Unit 2 has no indications of fuel failures.
4.4.2 Unit 3 i
Un.'st 3 is defueled for D3R14. The leaking fuel element was identified by sipping and will not be reloaded. ;
1 5.0 TECHNICAL SPECIFICATION AMENDMENTS 5.1 Amendments to Facility License or Technical Specifications implemented during April 1997.
April 10, Received amendment 156 and 151 which permitted the removal of the Unit 3 24/48 VDC battery.
April 25, received amendment 158 and 153 which raised the minimum iodine removal efficiency of the Standby Gas Treatment Charcoal Filters from 90% to 97.5%. This was done because a recalculation of the secondary cor.tainment volume resulted in a smaller volume. The smaller volume, when used as a input to the calculation of post accident exposure to the control room operators, raised the predictec exposure above acceptable limits. This was offset by the improved iodine remv/al ef ficiency of the Standby Gas Treatment Charcoal Filters.
April 30, received amendment 157 and 152 which evaluated the Unreviewed Safety Question (US0) associated with the use of containment overpressure to compensate for a deficiency in the net positive suction head for the emergency core cooling pumps following a design basis accident. The amendment raised the 12 La \$ MC\f 301\MIKT 97970$0501.GA L
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maximum suppression chamber water temperature and ,
ultimate heat' sink temperat'ure from 75 F to 95* F.
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