ML20137T341
| ML20137T341 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/31/1997 |
| From: | Abrell G, Jamila Perry COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JSPLTR-97-0070, JSPLTR-97-70, NUDOCS 9704160074 | |
| Download: ML20137T341 (13) | |
Text
Comnionwealth Edison Company I
Dresden Generating St.ition MOO North Dresden Road Morris, !!,6(H 50 rei sis.94nu0 April 10,1997 l
J JSPLTR 97-0070 U. S. Nuclear Regulatory Commission ATTN: Document ControlDesk Washington, DC 20555 1
Subject:
Monthly Operating Data Report for March 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 March 1997.
This information is supplied to your oflice as required by Technical Specification 6.9. A.5, in accordance with the instructions set forth in Regulatory Guide 1.16.
Sincerely, 4
Ste' hen Perry Site Vice President Dresden Station Enclosure i
f cc:
NRC Region III Office g%g Illinois Dept. of Nucleat Safety, State ofIllinois g
NRC Senior Resident Inspector UDI, Inc. - Washington, DC File / Numerical 970416 h$ob10 PDR A
PDR lll3,I,lllllI!lI!l.l!$l!!lkbh A Unkom Compan}
s MONTHLY NRC SU M Y OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION COM40NWEALTH EDISON COMPANY FOR MARCH 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 i
3 MARCH 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 i
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 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 5.1.2 Unit 3 2
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t 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.
-j Dreuden 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 i
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 r
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 i
the Kankakee River for make-up and the Illinois River for blowdown.
t The Architect-Engineer for Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.
r This report for MARCH 1997, was compiled by Gary A.
Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 1749.
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I 2.0 SUbHARY OF OPERATING EXPERIENCE FOR MARCH 1997 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE
SUMMARY
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Unit 2 was on system at the beginning of the period near full power.
At 0510 on March 15, 1997, began load drop for scram testing, timing of control rod G-6, and to gather data associated with the Recirculation Pump l
speed mismatch.
At 1710 commenced load increase j
. and reached full power at 2100.
At 0200 on March 24 began load drop to enter the low pressure heater bay'to determine the extent of a leak on the of 2C3 Feedwater Heater operating vent line.
At 0440, Unit was at 550 MWE for the J
inspection.
At 1955 commenced load increase, and reached 819 MWE at 1628 on March 27, 1997.
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2.0 SU144ARY OF OPERATING EXPERIENCE FOR MARCH 1997 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 3 was on system in coastdown throughout the period until the shutdown began at 1506 on March 28 for the start of refueling outage D3R14.
At 0113 March 29, 1997 generator was separated from the system.
At 0229 March 29 Reactor was manually scrammed in accordance with shutdown procedure.
Mode switch was placed in REFUEL at 1219 on March 30.
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i 3.0 OPERATING DATA STATISTICS i
3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No.
050-237 l
DATE APRIL 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 i
OPERATING STATUS 1.
REPORTING PERIOD:
MARCH 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 j
PARAMETER
.THIS MONTH YEAR TO DATE CUMllLATIVE H"'fRS IN PERIOD 144 2,160 233,496 U b REACTOR CRITICAL 744 2,160 169,322 TIME REACTOR RESERVE SHUTDOM( (Hours) 0 0
0 TINE GENERATOR ON-LINE (Hours) 744 2,160 161,175 TDE GENERATOR RE5ERVE SHU1DO44 (Hours) 0 0
1 THERMAL ENERGY GENERATED (M4Ht Gross) 1,786,799 4,977,282 336,681,183 ELECTRICAL ENERGY GENERATED (WNEHe Gross) 579,764 1,616,301 107,514,237 ELECTRICAL ENERGY GENERATED (MfEHe Net) 553,794 1,545,378 101,647,107 REACTOR SERVICE FACTOR (%)
100.0%
100.0%
72.5%
REACTOR AVAILABILITY FACTOR (%)
100.0%
100.0%
72.5%
GENERATOR SERVICE FACTOR (%)
100.0%
100.0%
69.0%
GENERATOR AVAILABLILITY FACTOR (%)
100.O%
100.O%
69.O%
CAPACITY FACTOR (Using MCD Net) (%)
96.4%
92.7%
56.4%
CAPACITY FACTOR (Using DER Net) (%)
93.7%
90.1%
54.8%
FORCED OUTAGE FACTOR (%)
01 0.O%
12.5%
20.
SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: NONE 21.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 6
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3.0 OPERATING DATA STATISTICS 3.2 OPERATING DATA REPORT - DRESDEN UNIT TrfREE DOCKET No.
050-249 DATE APRIL 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS 1.
REPORTING PERIOD:
MARCH 1997 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWth) :
2,527 1
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 CUMULATNE HOURS IN PERIOD 744 2,160 222,816 TIME REACTOR CRITICAL 675 1395.8 157,253 TDS REACTOR RESERVE SHUTDOWN (Hours) 0.0 0
0 TDS GENERATOR ON-LINE (Hours) 674 1,356 149,880 TIME GENERATOR RESERVE SHUTDONN (Hours) 0., 0 0
0 THERMkL ENERGY GENERATED (MfHt Gross) 1,089,01 2,267,378 312,479,855 ELECTRICAL ENERGY GENERATED (MWEHe Gross) 349,078 729,656 100,002,797 ELECTRICAL ENERGY GENERATED (M4EHe Net) 332,339 690,417 94,772,918 REACTOR SERVICE FACTOR (%)
90.7%
64.6%
70.6%
REACTOR AVAILABILITY FACTOR (%)
90.7%
64.6%
70.6%
GENERA 1DR SERVICE FACTOR (%)
90.6%
62.8%
67.3%
GENERATOR AVAILABLILITY FACTOR (%)
90.6%
62.8%
67.3%
CAPACITY FACTOR (Using MCD Net) (%)
57.9%
41.4%
55.1%
CAPACITY FACTOR (Using DER Net) (%)
56.3%
40.3%
53.6%
EURCED OUTAGE FACTOR (%)
0.0%
35.1%
14.3%
20.
SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: In refuel outage D3R14.
21.
IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: June 2, 1997.
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1 3.3 AVERAGE DAILY UNIT 2 POWER LEVEL l
DOCKET No. 050-237 UNIT Dresden 2 DATE APRIL 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 l
MONTH:
March-97 j
DRESDEN 2 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET
)
POWER LEVEL (MWe)
POWER LEVEL (MWe) 1 721 17 785 2
716 18 783 3
724 19 783 4
773 20 782 5
768 21 781 6
775 22 782 7
776 23 782 8
776 24 557 9
775 25 538 10 776 26 616 11 779 27 675 12 782 28 781 13 782 29 784 14 782 30 787 15 607 31 790 16 756 (Note:
negative values represent station loads) 8 La\\8360\\8301\\ MISC \\97\\97040001.GA
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3.4 AVERAGE DAILY UNIT 3 POWER LEVEL DOCKET No. 050-249 UNIT Dresden 3 DATE APRIL 7, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH:
March-97 DRESDEN 3 j
DAY AVERAGE DAILY NET DAY AVERAGE DAILY NE?
POWER LEVEL (MWe)
POWER LEVEL (MWe) 1 528 17 495 2
528 18 491 3
524 19 488 4
521 20 484 5
518 21 483 6
518 22 482 7
516 23 480 8
513 24 478 9
511 25 476 10 508 26 474 11 504 27 472 12 501 28 382 13 499 29
-4 14 498 30
-8 15 496 31
-8 16 497 (Note:
Negative values represent station loads) 9 Lt\\8360\\9301% MISC \\97\\97040801.GA
. - - -. -.. - - - _ ~. _ -.. -.. -. -.
. _. -. ~.. -. - -. -. -... -. - -
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- e 3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS l
REPORT MONTH OF MARCH'1997 NO DATE TYPE DURATION REASON METHOD LICENSEE SYSTEM COMPO-CORREC-(1)
(HOURS)*
(2)
OF EVENT CODE (4)
NENT TIVE SHUTTING REPRT #
CODE ACTIONS /
DOWN (5)
COM-REACTOR MENTS l
(3) 1 970315 S
0 B
4 N/A N/A N/A 2.1 2
970323 S
0 B
4 N/A N/A N/A 2.1-l i
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l Year-to-date forced outage hours = 0 l
Cumulative forced outage hours = 22,935 TABLE KEY:
i (1)
(3)
F:
Forced Method:
S:
Scheduled 1.
Manual i
2.
Manual Scram (2) 3.
Automatic Scram Reason:
4.
Other (Explain)
A Equipment Failure (Explain) 5.
Load Reduction 4
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) l (5)
Exhibit I Same Source as i
Above.
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3.6 UNIT 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH MARCH 1997 NO DATE TYPE (1)
DURATION FI.ASON (2)
METHOD OF LICENSEE SYSTEM COHPONENT CORPIC-(HOURS)*
SHUTTING EVENT CODE CODE (5)
TIVE DOWN FIPORT 5 (4)
ACTIONS /
REACTOR CCMMENTS (3) 1 970328 S
70 C
1 2.2 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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O 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 Unit 3 Previous operation indicated a single fuel rod failure.
5.0 TECHNICAL SPECIFICATION AMENDMENTS 5.1 Amendments to Facility License or Technical Specifications implemented during March 1997.
Amendments 153 and 148 for Dresden 2 and 3 respectively became effective on February 28, 1997.
These amendments revised the Pressure-Temperature limit curves for the reactor vessels.
Revised curves were provided for limits on vessel pressure testing, non-nuclear heatup and cooldown as well as critical operation up to 22 EFPYs.
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