ML20128P509
| ML20128P509 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/30/1996 |
| From: | Abrell G, Jamila Perry COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JSPLTR-96-0183, JSPLTR-96-183, NUDOCS 9610170282 | |
| Download: ML20128P509 (13) | |
Text
Comnhmwcalth 1:dimn Company Dresden Generating Nation 6500 North Drei. den Road Morris, 11.60150 ret,m sm2 292o October 9,1996 JSPLTR 96-0183 U. S. Nuclear Regulatory Conw4.sion ATTN: Document Control Desk Washington. DC 20555
Subject:
Monthly Operating Data Report for September 1996 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 September 1996.
Cumulative totals for Gross and Net electrical generation are being compared to the of6cial Comed Production Data Bank records. Should discrepancies be found in these 6gures, they will be corrected in the October monthly report.
Cumulative totals for megawatt thennal hours (MWTitr) have been adjusted to .. gree with of6cial Company records as of 1 January 1996. The adjustments were less than one percent for each unit.
This information is supplied to your of6ce as required by Technical Specification 6.6.A.3, in accordance with the instructions set forth in Regulatory Guide 1.16.
Sincerely.
tept n Perry Site Vice President Dresden Station l
l JSP/GA:pt i I I 9610170282 960930 i i !
PDR ADOCK 05000010 i Enclosure R PDR '
cc: NRC Region ill Of6ce '(b s
lilinois Dept. of Nuclear Safety. State of Ilhnois
, NRC Senior Resident inspector g((G UDI. Inc. - Washington. DC File / Numerical A i nicom Compan>
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j MONTHLY NRC 4
SUMMARY
OF OPERATING EXPERIENCE, u
!; PER REGULATORY GUIDE 1.16 i
FOR DRESDEN NUCLEAR POWER STATION 4
COMMONWEALTP EDISON COMPANY FOR September 1996 UNIT DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 1
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a TABLE OF CONTENTS September 1996 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 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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l 1.0 Introduction '
Dresden Nuclear Power Station is a three reactor generating facility owned and operated by the Comed I Company of Chicago, Illinois. Dresden Station is located at the confluence of the Kankakee and Des Plaines Rivers, in Grundy County, near Morris, 2
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 831 megawatts electrical, respectively, 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 Dresden Units 2 and 3 was Sargent and Lundy of Chicago, Illinois.
This report for September 1996, was compiled by Gary A.
Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 3749.
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3 t.nsum w now % o m
2.0
SUMMARY
OF OPERATING EXPERIENCE FOR September 1996 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE
SUMMARY
1 Unit 2 was on system at the beginning of the l period with power ascension and start-up testing in progress. i l
Power was reduced from 413 to 320 MWE at 1430 on 3 September because of recirculation pump flow oscillations. Beginning at 1430 on 6 September, l load was increased to 504 MWE following adjustments to the speed control circuit.
Feedwater control testing began at 0700 on 7 September. At 0035 on 14 September, load was )
dropped from 670 MWE to 510 MWE for control rod l drive exercising. A load increase to 800 MWE l began at 0615 on 17 September. The Unit held 800 MWE from 0015 on 20 September until a load drop to 590 MWE at 0600 on 30 September as a result of a run of gizzard shad which impinged on the traveling screens and threatened service ' rater and circulating water supplies. I Unit is currently derated 2% because of feedwater flow element uncertainty. This derating may be reduced based on the results of startup testing.
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i 2.0
SUMMARY
OF OPERATING EXPERIENCE FOR September 1996 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE
SUMMARY
Unit 3 began the period in cold shutdown while l modific&tions to the low pressure coolant I injection system heat exchanger support steel and j control rod drive gallery steel, originally I planned for the refueling outage, were completed.
Inspection of the reactor water clean-up heat exchangers in accordance with the ASME Code was completed satisfactorily.
l Unit 3 was made critical at 0520 on 22 September and synchronized to the grid at 1250 on 23 September. Control Rod drive scram timing, minor maintenance, and testing were completed during power ascension. Unit was at 700 MWE at 0700 on 29 September. Beginning at 0600 on 30 September, load was dropped to 430 MWE because a run of ;
gizzard shad impinged on the traveling screens and I threatened the service water and circulating water supplies. At 1130 on 30 September, load was increased to 590 MWE. ,
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l 3.0 OPERATING DATA STATISTICS 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 DATE October 3,1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS
- 1. REPORTING PERIOD: September 1996
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 1
IIAYIMUM DEPENDABLE CAPACITY (MWe NET) : 772 l DESIGN ELECTRICAL RATING (MWe Net): 794 i
- 3. POWER LEVEL TO WHICH RESTRICTED (MWe Net): 2477 MWth .
(approximately 778.1 MWe Net)
- 4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.1 of '
this report.
l REPORTING PERIOD DATA PARAMETER ITHIS MONTHIYEAR 10 DATEi CUMULATIVE l 5 HOURS It1 PERInD 12C 6,575 230,543 6 TIME REACTOR CRIT ICAL IJC 1,821 164,953 l 7 TIME REACTOR REEEhVE CHIJTLktt;J (Hours) U.C 0 C l 8 TIME GEtJERATOR Oti-LItJE (Hours) 120.C 1,522 154,705 9 FIME GEtiEkATOR RESERVE SHUTDONJ (Hours) 0.0 C 1 10 THERMAL EtJERGY GEliERATE D (tS0it Gross) 1,379,41b J,2 b l,1 W J26,U04,271 11 ELECTHICAL ENERGY GENERATED (TMH Gr oss) 4J6,411 b5'O, S m 104,585,186 1 12 ELECTRICAL ErJEhdY GE!JERATED (tWH ikt) 416,ho! 616,55 98,805,134 1 13 kEACTOR SERVICE F/G >R (t) 100.ut J 7.14 71.5% l 14 kEACTOR AVAllABIL!TY FAUTtR (t) 100.0V J7./t 11 54 15 GEf4ERAloh SEkVICE FACTuk (v) 100.0* ;J.It bl.1%
16 GEt4ERATOR AVAllABLI LITY FACTuh (%) 100.Os J3.it 67.14 l 17 CAPACITY FACTOh (UrineritCD Ikt) ( v. ) L.Ue 12.1% 55.bV l 18 CAEACITY FART (ik (I f s i rst DEk h. :) (%) < % 11.bV 54.04 19 FORCED ultrAGE FA:Jruh (*) of no.0* 11.8%
- 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 THREE I i
DOCKET No. 050-249 DATE October 3,1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 l OPERATING STATUS
- 1. REPOR' ING PERIOD: September 1996
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MFe 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.
I REPORTING PERIOD DATA I
PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE j 5 HOURS IN PEH i t iD 2( b,575 221,592 6 TIME REACTOR CRITICAL 210.7 3,730 15S,229 7 TIME REACTOR kEFERVE SHUTLxtlM (Hours) U.' o 0 8 T1tt, GENERATuR UN-LINE (Haurs) 180.0 3,b45 147,082 9 TIME GENEPATOR kESERVE SHUTDOW!! ( Hou rs ) 0.0 0 0 10 rHERMAL ENER ;Y GENERATED (t t,vH t urors) 321,UM4 ,260,5S3 308,970,500 11 ELECTRICAL ENERGY GENERATED (!MH G ro s s ) 101,090 2,695,014 99,457,182 12 ELECTRICAL ENERGY GENERATED OT4H Net) 91,4 % 3 571,020 94,227,619 13 REACTCR SERVICE FACTOR (t) 25.M 56.74 70.14 14 REACTGR AVAIllBILITY FACTok (s) 29.3$ 16.71 70.14 15 3ENERATOR SERVICE FACTuk (%) 25.0't 55.41 bb.4%
16 3EMERATOR AVAILABLI LITY FACTuk ( 'a l 5.09 SS.4% bb.44 17 NAC I T Y F AC roR ( Us i n't MCl> Net) (%) 16. M $1: /* 55.1%
18 2APACITY FACT <k (Usina DER Net ) (s) 16.15 49.2% 53.64 19 FORCEli OUTAGE F ACTOR (%) ik.U* 4 4.H 13.4V
- 20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: 1 March 1997.
- 21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A l
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- 21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 3 AVERAGE DAILY UNIT 2 POWER LEVEL DOCKET No. 050-237 UNIT Dresden 2 DATE October 3,1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH: September-96 DRESDEN 2 DAY AVERAGE DAILY. NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) 1 119 18 690 2 181 19 740 3 355 20 764 4 297 21 766 5 281 22 764 6 292 23 730 7 476 24 759 8 559 25 760 9 600 26 765 10 595 27 765 11 636 28 765 12 635 29 744 13 637 30 618 14 491 15 482 16 486 17 614 _
(Note: negative values represent station' loads) 8 Li\8360\8301\ MISC \96\96100901.GA
4 3.4 AVERAGE DAIhY UNIT 3 POWER LEVEL DOCKET No. 050-249 UNIT Dresden 3 DATE October 3, 1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH: September-96 DRESDEN 3 DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) 1 -9 18 -9 2 -9 19 -9 3 -8 20 -9 4 -8 21 -9 5 -8 22 -9 6 -8 23 55 7 -9 24 241 8 -9 25 535 9 -9 26 687 10 -9 27 672 11 -9 28 665 12 -9 29 664 13 -9 30 499 14 -8 15 -8 16 -8 {
17 -8 (Note: Negative values represent station loads) 9 L:\8360\8301\ MISC \96\96100801.GA
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3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH OF September 1996 NO DATE TYPE DURATION REASON METHOD LICENSEE SYSTEM COMPO- CORREC-(1) (HOURS)* (2) OF EVENT CODF' NENT TIVE SHUTTING REPORT # CODE ACTIONS /
DOWN (5) COM-REACTOR MENTS l (3) ]
3 960914 5 0 B 5 N/A N/A N/A 2.1 l
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Year-to-date forced outage hours = 2,281 l Cumulative forced outage hours = 20,706.00 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 l B Maintenance or Test I C Refueling (4) l l
D Regulatory Restriction Exhibit G Instruction for E Operator Training & Preparation of Data Entry ,
Licensing Exam Sheets for Licensee Event l F Administrative Reports (LER) File l G Operational Error (NUREG-0161) ;
H Other (Explain)
(5) l Exhibit I Same Source as l Above.
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3.6 UNIT 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH September 1996 NO DATE TY f'E ( 1 ) (CPATION PEASDN(2} METHOD Cf' 1.lCENSEE SYiTEM CrugantNT cngpyc.
(HOOFS)' SHUTTING EVENT t DE COLE ( *A TIVE f(Mi FEFGPT e (4i ACTICWS /
FLACTC R 0:HMENTS (3) 2 960621 l' 53'i A 1 t!/ A FA R 2.2 3 9609.50 F 0 H 5 t1/A NeA N/A 2.2 b
Year-to-date forced outage hours = 2,929 Cumulative forced outage hours = 22,844 TABLE KEY:
4 (1) (3)
F: Evcced Method:
S: Jcheduled 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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4.0 UNIQUE REPORTING REQUIREMENTS 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS - ;
UNIT 2 AND UNIT 3 None l 4.2 OFF-SITE DOSE CALCULATION MANUAL (ODCM) CHANGES None ,
4.3 MAJOR CHANGES TO THE RADIOACTIVE WASTE TREATMENT SYSTEMS None 1
4.4 FAILED FUEL ELEMENT INDICATIONS I 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 AMENDMENTf, 5.1 Amendments to Facility License or Technical Specifications implemented durinq September 1996.
Amendments 150 for Unit 2 and 145 for Unit 3 were partially implemented. Specifically, the location of accident monitoring instrumentatian was deleted from j table 3.2.6, and the total maximun combined I surveillr ce interval time for any three consecutive )
intervalt 3.25 times the specified surveillance l interval was eliminated, j 12 L:\8360\8301 sHl:C\%i% icEl,GA