ML20132A954
ML20132A954 | |
Person / Time | |
---|---|
Site: | Dresden |
Issue date: | 11/30/1996 |
From: | Abrell G, Jamila Perry COMMONWEALTH EDISON CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
JSPLTR-96-0231, JSPLTR-96-231, NUDOCS 9612160396 | |
Download: ML20132A954 (13) | |
Text
_.
Commonacalth Edivan Company
(
Dresten Generating Station 650) North l)rexten Road Morrh. IL G) 650 Tcl HIW12-2920 i
1 December 6,1996 l
JSPLTR 96-0231 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Monthly Operating Data Report for November 1996 Dresden Nuclear Power Station Commonwealth Edison Company 1
l Docket Nos.50-010,50-237, and 50-249 Gentlemen:
Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for November 1996.
This information is supplied to your office as required by Technical Specification 6.6. A.3, 1
in accordance with the instructions set forth in Regulatory Guide 1.16.
l Sincerely, J. Stehhen Perry Site Vice President Dresden Station
, p(
Enclosure
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NRC Region III Office 1
Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident Inspector UDI, Inc. - Washington, DC i
File / Numerical j
4 "612160396 961130 PDR ADOCK 05000010 PDR R
A t!nicom company
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l MONTHLY NRC l
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l SUte&RY OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION l
l COtetONWEALTH EDISON COMPANY FOR November 1996 l
l 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 November 1996 NRC REPORT l
1.0 Introduction l
2.0 Sunnary 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 I
3.6 Unit 3 Shutdowns and Power Reductions i
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 l
4.3 Major Changes to the Radioactive Waste Treatment j
Systems 4.4 Failed Fuel Element Indications i
4.4.1 Unit 2 l
4.4.2 Unit 3 5.0 Technical Specification Amendments j
5.1 Amendments to Facility License or Technical i
Specifications I
5.1.1 Unit 2 5.1.2 Unit 3 1
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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 i
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 l
Reactor with a design net electrical output rating of l
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.
1 Dresden Units 2 and 3 are General Electric Boiling l
Water Reactors, each licensed at 2527 megawatts l
thermal.
The gross outputs of Units 2 and 3 are 832 and 834 megawatts electrical, respectively, with design l
net electrical output ratings of 794 MWe each.
The i
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 l
the Kankakee River for make-up and the Illinois River l
for blowdown.
The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.
i This report for November 1996, was compiled by Gary A.
I Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 3749.
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1 2.0 SUte4ARY OF OPERATING EXPERIENCE FOR November 1996 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 2 was on system at the beginning of the period near full power.
l At 0126 on November 17, 1996, a load drop began l
for routine surveillance testing.
Following circulating water flow reversal, load increase began'at 1300 from 650 MWE.
At 2100 on November 23, 1996, load drop began to time main steam isolation valves, to scram test l
control rod drives, and to enter the drywell to add oil to 2A Recirc Pump motor.
Commenced load increase at 1430 on November 24, 1996, and reached full power at 0130 on November 26, 1996.
On November 26, the 2% thermal power derating caused by feedwater flow measurement uncertainty was lifted.
At 2000 on November 28, 1996, commenced load drop to change condensate demineralizers and perform i
control rod drive exercising.
Power was l
stabilized at 550MWE at 2245 on November 28 and remained at that level for the remainder of the period.
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i 3.0 StM4ARY OF OPERATING EXPERIENCE FOR November 1996 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 3 was shutdown for the entire month for repairs to the 3B recirculating pump motor were i
planned and executed.
Numerous other outage tasks were conducted at this time.
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l 3.0 OPERATING DATA STATISTICS I
l 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO l
DOCKET No.
050-237 j
DATE December 3,1996
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l COMPLETED BY G. A. ABRELL l
TELEPHONE (815) 942-2920 l
l OPERATING STATUS 1.
REPORTING PERIOD:
November 1996 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWth):
2,527 i
MAXIMUM DEPENDABLE CAPACITY (MWe NET):
772 l
DESIGN ELECTRICAL RATING (MWe Net):
794 3.
POWER LEVEL TO WHICH RESTRICTED (MWe Net): No r
l restrictions I
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 720 8,040 230,592 TIME REACTOR CRITICAL 720 3,286 l'6,418
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TIME REACTOR RESERVE SHUTDOWN (Hours) 0.0 0
0 TIME GENERATOR ON-LINE (Hours) 720.0 2,987
.8,271 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0.0 0
1 THERMAL ENERGY GENERATED (MWHt Gross) 1,696,889 5,703,171 is,240,245 ELECTRICAL ENERGY GENERATED (MWEHe Gross) 552,858 1,798,638 1r.;, 4 2 6, 6 4 2 ELECTRICAL ENERGY GENERATED (MWEHe Net) 532,844 1,680,049 99,649,758 REACTOR SERVICE FACTOR (%)
100.0%
40.9%
72 g REACTOR AVAILABILITY FACTOR (%)
100.0%
40.9%
72.2%
GENERATOR SERVICE FACTOR (%)
100.0%
37.2%
68.6%
GENERATOR AVAILABLILITY FACTOR (t) 100.0%
37.2%
68.6%
CAPACITY FACTOR (Using MCD Net) (%)
95.9%
27.1%
56.0%
CAPACITY FACTOR (Using DER Net) (%)
93.2%
26.3%
54.4%
FORCED OUTAGE FACTOR (%)
0%
43.3%
12.7%
20.
SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: NONE 21.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF i
STARTUP: N/A 4
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i 3.0 OPERATING DATA STATISTICS i
3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE t
1 DOCKET No.
050-249 DATE December 3,1996 l
COMPLETED BY G. A. ABRELL l
TELEPHONE (815) 942-2920 OPERATING STATUS 1.
REPORTING PERIOD:
November 1996 l
2.
CURRENTLY AUTHORIZED POWER LEVEL (MWth) :
2,527 j
MAXIMUM DEPENDABLE CAPACITY (MWe Net) :
773 1
DESIGN ELECTRICAL RATING (MWe Net):
794
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3.
POWER LEVEL TO WHICH RESTRICTED: No restriction
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4.
REASONS FOR RESTRICTIONS (IF ANY):
See Section 2.2 of this report.
REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 1
HOURS IN PERIOD 720 8,040 219,912 TDS REACTOR CRITICAL 0
4,358 155,857 TDS REACTOR RESERVE SHUTDONN (Hours) 0.0 0
0 TDS GENERATOR ON-LINE (Hours) 0.0 4,273 148,524 TDS GENERATOR RESERVE SHUTDONN (Hours) 0.0 0
0 THERMkL ENERGY GENERATED QSfHt Gross) 0 9,508,540 310,212,477 ELECTRICAL ENERGY GENERATED 00lEBe Gross) 0 3,096,338 99,273,141 ELECTRICAL EMERGY GENERATED QSERHe Net)
-5,760 2,947,476 94,088,453 REACTOR SERVICE FACTOR (4) 0.0%
54.2%
70.9%
REACTOR AVmTTamrLITY FACTOR (%)
0.0%
54.2%
70.9%
GENERATOR SERVICE FACTOR (4) 0.0%
53.1%
67.5%
GENERATOR AVAITART.TT. TTY FACTOR (%)
0.0%
53.1%
67.5%
CAPACITY FACTOR (Using ICD Net) (t)
~1.0%
47.5%
55.4%
CAPACITY FACTOR (Using DER Net) (%)
-1.0%
46.2%
53.9%
NORCED OUTAGE FACTOR (%)
100.0%
46.9%
14.1%
20.
SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: 1 March 1997.
21.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: December 27, 1996.
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3.3 AVERAGE DAILY UNIT 7. POWER LEVEL DOCKET No. 050-237 l
UNIT Dresden 2 DATE December 3,1996 l
COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 i
MONTH:
November-96 DRESDEN 2 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET I
POWER LEVEL (MWe)
POWER LEVEL (MWe) 1 773 17 735 2
772 18 781 3
772 19 780 l
4 777 20 763 5
778 21 776 6
778 22 781 7
778 23 762 t
778 24 357 9
778 25 661 j
10 763 26 793 l
11 776 27 794 12 776 28 766 13 764 29 527 1
14 777 30 528 15 779 16 780 (Note:
negative values represent station loads) i l
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l 3.4 AVERAGE DAILY UNIT 3 POWER LEVEL l
DOCKET No. 050-249 UNIT Dresden 3 DATE December 3, 1996 COMPLETED BY G. A. ABRELL i
TELEPHONE s815) 942-2920 MONTH:
November 96 DRESDEN 3
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DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe)
POWER LEVEL (MWe)
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-8 17
-8 2
-8 18
-8 3
-8 19
-8 4
-8 20
-8 5
-8 21
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6
-8 22
-8 7
-8 23
-8 8
-8 24
-8 9
-8 25
-8 10
_-8 26
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11
-8 27
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-8 28
-8 13
-8 29
-8 i
14
-8 30
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-8 16
-8 (Note:
Negative values represent station loads) 9 L:\\8360\\8301\\ MISC \\96\\96120501.GA l
3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH OF November 1996 l
NO DATE TYPE DURATION REASON METHOD LICENSEE SYSTEM COMPO-CORREC-i l
(1)
(HOURS)*
(2)
OF EVENT CODE (4)
NENT TIVE SHUTTING REPORT #
CODE ACTIONS /
DOWN (5)
COM-I REACTOR MENTS (3)
I 7
961117 S
0 B
5 N/A N/A N/A 2.1 i
8 961123 S
0 B
5 N/A N/A N/A 2.1 l
9 961128 S
0 B
5 N/A N/A N/A 2.1 l
Year-to-date forced outage hours = 2,281 Cumulative forced outage hours = 22,935 1
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 l
Above.
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3.6 UNIT 3 SHUTDOWNS AND POWER REDUCTIONS i
REPORT MONTH November 1996 NO DATE TYPEtt)
DUPATION REASOtf(2)
HETHOD Or LICENSEE SYSTEM COMPotr NT CORREC-(HOURS)
- SHUTTING EVENT CODE CODE (5)
TIVE DCHN REPORT i (4)
ACTIONS /
REACTOR COMMENTS (3) 4 961028 r
720 A
1 N/A AD MO 2.2 l
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Year-to-date forced outage hours = 3,767 Cumulative forced outage hours = 24,332 TABLE KEY:
(1)
(3)
F:
Forced Method:
S:
Scheduled 1.
Manual i
1 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 l
Above.
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l 4.0 UNIQUE REPORTING REQUIREMENTS l
l 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS -
UNIT 2 AND UNIT 3 l
l 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 EUEL ELEMENT INDICATIONS 1
l 4.4.1 Unit 2 Unit 2 has no indications of fuel failures.
l 4.4.2 Unit 3 l
Unit 3 Previous operation indicated a single fuel rod failure.
5.0 TECHNICAL SPECIFICATION AMENDMENTS l
l 5.1 Amendments to Facility License or Technical Specifications implemented during November 1996.
l None 1
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