ML20134L608
| ML20134L608 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/31/1997 |
| From: | Abrell G, Jamila Perry COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JSPLTR-97-0026, JSPLTR-97-26, NUDOCS 9702190228 | |
| Download: ML20134L608 (14) | |
Text
- - ** Commonweahh Edison Gimpany Dresten Generating Station 65(X) North Drewicn Ro.id Mqrris. IL 60450 Tel H 153142-2920 February 10,1997 JSPLTR 97-0026 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Monthly Operating Data Report for January 1997 Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos.50-010, 50-237, and 50-249 Gentlemen:
Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for January 1997.
This information is supplied to your office as required by Technical Specification 6.9. A.5, in accordance with the instructions set forth in Regulatory Guide 1.16.
Sincerely,
,Q,
. Step en Pe Site Vice President Dresden Station Enclosure
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cc: NRC Region III Oflice Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident Inspector UDI, Inc. - Washington, DC < mC , 1!
File / Numerical j Ud 'I I 190007 9702190228 970131 PDR ADOCK 05000010 R PDR-A rnitom oimpan>
MONTHLY NRC :
SIDHARY OF OPERATING EXPERIENCE, PER REGUIATORY GUIDE 1.16 :
FOR i DRESDEN NUCLEAR POWER STATION CCM40NNEALTH EDISON cot 4PANY ;
i FOR JANUARY 1997 UNIT DOCKET LICENSE 1 050-010 DPR-2 :
2 050-237 DPR-19 3 050-249 DPR-25 i
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TABLE OF CONTENTS 1 JANUARY 1997 NRC REPORT 1.0 Introduction 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 3.1 Operating Data Report - Dresden Unit 2 3.2 Operating Data Report - Dresden Unit 3 3.3 Average Daily Unit 2 Power Level 3.4 Average Daily Unit 3 Power Level-3.5 Unit 2 Shutdowns and Power Reductions 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 l 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 i 5.1.2 Unit 3 l
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1.0 Introduction 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 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, 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.
1 This report for January 1997, was compiled by Gary A.
Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 3749.
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1 t 2.0 SUte4ARY OF OPERATING EXPERIENCE FOR January 199'J i 1 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE SUMM7 e'.-
! Unit 2 was on system at the beginning of >
period at approximately 300 MWE while trcub.e 5
shooting #1 Turbine Control Valve. At 1815 on January 3, 1997, the control' valve was .
! successfully reopened. At 1859 on January 4, }
l 1997, commenced load pick-up and achieved full l j; power at 1330 on January 6, 1997. l J
! The unit remained at full power the remainder of !
! the period _except for minor. load drops for i surveillance and testing. ;
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! 3.0 sthe4ARY OF OPERATING EXPERIENCE FOR January 1997 l l
'2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 3 was shutdown at the beginning of the period ,
I for repairs to the 3B recirculating pump motor and !
completion of other outage tasks.
l On December 20, 1996, an error was discovered in l energency core cooling analysis calculation. The !
revised calculation revealed.a deficit in the net i positive suction head required for the ECCS pumps l l during the design basis accident. An emergency :
technical specification amendment was submitted on !
l January 13, 1997 to permit restart of the unit. l l The amendment was received on January 28, 1997. {
At 2314 on January 29, 1997, the reactor was made };
critical and was synchronized to the grid at 1444
! on January 31, 1997. i
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3.0 OPERATING DATA STATISTICS 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO
! DOCKET No. 050-237 !
l DATE February 4, 1997 l COMPLETED BY G. A. ABRELL i TELEPHONE (815) 942-2920 ,
OPERATING STATUS ,
- 1. REPORTING PERIOD: January 1997
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe NET): 772 DESIGN ELECTRICAL RATING (MWe Net) : 794
- 3. POWER LEVEL TO WHICH RESTRICTED (MWe Net): No restrictions
- 4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.1 of this report.
REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE HOURS IN PERIOD 744 744 232,080 TIME REACTOR CRITICAL 744 744 167,906 TIME REACTOR RESERVE SHUTDOWN (Hours) 0 0 0 TIME GENERATOR ON-LINE (Hours) 744 744 159,759 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0 0 1 THERMAL ENERGY GENERATED (MWHt Gross) 1,686,231 1,686,231 333,390,132 ELECTRICAL ENERGY GENERATED (MWEHe Gross) 549,061 549,061 106,446,997 ELECTRICAL ENERGY GENERATED (MWEHe Net) 526,180 526,180 100,627,909 REACTOR SERVICE FACTOR (t) 100.0% 100.0% 72.3%
REACTOR AVAILABILITY FACTOR (t) 100.0% 100.0% 72.3% o GENERATOR SERVICE FACTOR (t) 100.0% 100.0% 68.8% .
GENEPATOR AVAILABLILITY FACTOR (t) 100.0% 100.0% 68.8%
CAPACITY FACTOR (Using MCD Net) (t) 91.6% 91.6% 56.2%
CAPACITY FACTOR (Using DER Net) (t) 89.1% 89.1% $4.6%
FORCED OUTAGE FACTOR (t) 0% 0.05 12.6%
- 20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: NONE
- 21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A l
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l 3.0 OPERATING DATA STATISTICS I 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No. 050-249 I
DATE February 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 ,
i OPERATING S'l'ATUS l I
- 1. REPORTING PERIOD: January 1997 ,
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 l MAXIMUM DEPENDABLE CAPACITY (MWe Net): 773 ,
794 DESIGN ELECTRICAL RATING (MWe Net):
- 3. POWER LEVEL TO WHICH RESTRICTED: No restriction
- 4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.2 of J this report.
1 REPORTING PERIOD DATA i PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE j HOURS IN PERIOD 744 744 221,400 l TIME REACTOR CRITICAL 48.8 48.8 355,906 TIME REACTOR RESERVE SNUTDONN (Hours) 0.0 0 0 TIME GENERATOR ON-LINE (Hours) 10.0 10 148,534 TIME GENERATOR RESERVE SHUTDONN (Hours) 0.0 0 0 THERMAL ENERGY GENERATED (MOtt Gross) 1,636 1, 63 (. 310,214,113 ELECTRICAL ENERGY GENERATED (MNEBe Gross) 1,320 1,320 99,274,461 ELECTRICAL ENERGY GENERA 1T.D (MNEHe Net) -4,648 -4,648 94,077,853 REACTOR SERVICE FACTOR (%) 6.6% 6.6% 70.4%
REACTOR AVAIIABILITY FACTOR (%) 6.6% 6.6% 70.4%
GENERATOR SERVICE FACTOR (%) 1.3% 1.3% 67.1%
GENERATOR AVAITART TLITY FACTOR (%) 1.3% 1.3% 67.1%
CAPACITY FACTOR (Using MCD Net) (%) -0.8% -0.8% 55.0%
CAPACITY FAC1DR (Using DER Net) (%) -0.8% -0.8% 53.5%
EURCED OUTAGE FACTOR (%) 98.7% 98.7% 14.8%
- 20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: March 29, 1997 for D3R14.
- 21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 7
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3.3 AVERAGE DAILY UNIT 2 POWER LEVEL i
DOCKET No. 050-237 l UNIT Dresden 2 DATE February 4, 1997 COMPLETED BY G. A. ABRELL ,
TELEPHONE (815) 942-2920 MONTH: January-97 DRESDEN 2 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET .
POWER LEVEL (MWe) POWER LEVEL (MWe) 1 285 17 792 2 286 18 792 3 278 19 790 4 262 20 793 5 299 21 793 6 743 22 792 7 787 23 791 8 792 24 791 9 794 25 792 10 793 26 790 11 792 27 792 12 791 28 791 l 13 792 29 791 14 792 30 787 15 791 31 787 16 784 (Note: negative values represent station loads) i l
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I 3.4 AVERAGE DAILY UNIT 3 POWER LEVEL DOCKET No. 050-249 UNIT Dresden 3 .
DATE February 7, 1997 '
COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 ,
MONTH: January-97 DRESDEN 3 DAY AVERAGE DAILY HET DAY AVERAGE DAILY NET I POWER LEVEL (MWe) POWER LEVEL (14We) 1 -8 17 -8 2 -8 18 -8 3 -8 19 -8 4 -8 20 -8 5 -8 21 -8 6 -8 22 -8 7 -8 23 -8 8 -8 24 -8 9 -8 25 -8 10 -8 26 -8 11 -8 27 -8 12 -8 28 -8 13 -8 29 -8 i 14 -8 30 -8 15 -8 31 46 16 -8 l l
(Note: Negative values represent station loads)
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3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH OF January 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) 10 961220 s 0 B/A 5 N/A N/A N/A 2.1 Year-to-date forced outage hours = 0 Cumulative forced outage hours = 22,935 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 (Explain) 5. Load Reduction B Maintenance or Test C Refueling (4)
D Regulatory Restriction Exhibit G Instruction for E Operator Training & Preparation of Data Entry Licensing Exam Sheets for Licensee Event F Administrative Reports (LER) File G Operational Error (NUREG-0161)
H Other (Explain)
(5)
Exhibit I Same Source as Above.
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3.6 UNIT 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH January 1997 1
'l NO DATE TYPE (1) DUPATION PIASON(2) METHOD OF LICENSEE SYSTEM- COMPONENT CORREC-(HOURS)
- SHUTTING EVENT CODE CODE (5) TIVE DOWN REPORT f (4) ACTIONS /
REACTOR COMMENTS (3) ;
4 961027 r 734- A 1 N/A AD HO 2.2 i
Year-to-date forced outage hours = 734 Cumulative 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.O UNIQUE REPORTING REQUIREMENTS j 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - UNIT 2 AND UNIT 3 Unit 3 3D electromatic relief valve was tested at low pressure on January 31, 1997.
4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES l <
In addition to numerous editorial changes, the following revisions were made.
12-13 Changed requirements for the Reactor Building I Vent Exhaust Duct Radiation Monitor minimum channels to say "See Technical Specifications Section 3/4.2". This will ensure the user is cognizant that this item appears in the Technical Specifications.
12-14 Deleted 7 day clock and reporting requirement for Action 20. Upgraded Tech Specs do not address Low Range 2 (3) Chimney noble gas monitoring and change is consistent with current Tech Specs and Quad Cities and i LaSalle ODCM requirements for comparable monitors. Deleted Action 24 associated with the Reactor Building Vent Exhaust Duct Radiation Monitor (see change for page 12-13).
12-16 Offgas monitor Functional Test frequency changed from daily to quarterly and Instrument check changed from quarterly to daily to comply with current Tech Specs.
11-2 Removed D-05 and footnote. D-05 deleted in 1995 as indicated by the footnote. Removed asterisk by D-45 indicating it replaced D-05 in 1995.
11-6 Added D-46 as a unit 2/3 Cooling Water Sample location.
11-14 Removed an incorrect milk location from the map; two locations were noted for D-26.
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4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT j I SYSTEMS ;
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! None .
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4.4 EAILED FUEL ELEMENT INDICATIONS [
1 4.4.1 Unit 2 i l
Unit 2 has no indications of fuel failures.
I 4.4.2 Unit 3 i i
Unit 3 Previous operation indicated a single fuel rod !
failure. i 5.0 TECHNICAL SPECIFICATION AMENDMENTS i 5.1 Amendments to Facility License or Technical Specifications implemented during January 1997.
January 13, 1997 implemented the Upgraded Technical 4 Specifications (TSUP) for Units 2 and 3 except for the section dealing with control room ventilation which was implemented on January 15, 1997. l January 28, 1997 received amendment 152 to DPR 19 and amendment 147 to DPR 25. The amendment evaluated an unreviewed safety question as a result of an error discovered in the calculation of head loss across the Emergency Core Cooling Suction Strainers. The amendment lowered the allowable torus water temperature and the ultimate heat sink temperature. In addition it changed the basis of the technical specification to allow credit for two pounds containment overpressure during the first ten minutes of the Design Basis Accident. These changes compensated for the deficiency in the net positive suction head available to the ECCS.
The new limits on torus water and ultimate heat sink temperature will not be achievable during the late j spring and summer months. Therefore, a new amendment will be necessary to restart the unit following the refueling outage.
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