ML20134K568

Monthly Operating Repts for Oct 1996 for Dresden Nuclear Power Station

ML20134K568
Person / Time
Site:	Dresden
Issue date:	10/31/1996
From:	Abrell G, Jamila Perry COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JSPLTR-96-0214, JSPLTR-96-214, NUDOCS 9611190207
Download: ML20134K568 (13)

Text

. Commonwealth I

diwn Company Drexten Generating Station 6500 North Dresden Read Morris,11. 60 ISO Te181sv12 2920 i

November 8,1996 l JSPLTR 96-0214 i U.S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D.C. 20555 j

Subject:

Monthly Operating Data Report for October 1996 Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos.50-010,50-237,50-249 I Gent!cmen: l Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for October 1996. i i

As noted in the previous report for September 1996, cumulative totals for Gross and Net electrical generation, Hours in the period, Time Generator On-line, and Forced Outage Hours have been revised to agree with the oflicial Comed Production Data Bank records from the commercial senice date to the present. Commercial Senice dates are noted in section 1 of the enclosure.

3 J

No changes were made to any year-to-date totals. l This information is supplied to your office as required by Technical Specification 6.6. A.3, in accordance with the instructions set forth in Regulatory Guide 1.16.

Sincerely, tcp n Perry Site Vice President Dresden Station JSP/GA:pt Enclosure h .j cc: NRC Region III Oflice Illinois Dept. of Nuclear Safety, State ofIllinois l NRC Senior Resident Inspector UDI, Inc. - Washington, DC File / Numerical 9611190207 961031 PDR ADOCK 05000010 R PDR A linicom Company

i e 4

MONTHLY NRC

SUMMARY

OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 i

1 FOR j DRESDEN NUCLEAR POWER STATION 1

COtedONWEALTH EDISON COMPANY

, FOR October 1996 i

l i

UNIT DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 i

1 Li\8360\8301\ MISC \96\96110801,GA

l l

0 l

TABLE OF CONTENTS October 1996 NRC REPORT 1.0 Introduction l 2.0 Summary of Operating Experience l'

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 l 3.5 Unit 2 Shutdowns and Power Reductions l 3.6 Unit 3 Shutdowns and Power Reductions 4.0 Unique Reporting Requirements'

4.1 Main Steam Relief and/or Safety Valve Operations -

l 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 l

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

Lt\8360\8301\ MISC \96\96110001.GA

l i

1.0 Introduction i 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 i R

200 megawatts electrical (MWe). The unit is retired-in place with all nuclear fuel removed from the reactor l vessel. Therefore, no Unit 1 operating data'is provided in this report.

Dresden Units 2 and 3 are General Electric Boiling l Water Reactors, each licensed at 2527 megawatts i 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 October.1996, was compiled by Gary A.

l Abrell of Dresden Regulatory Assurance Staff, telephone number (815) 942-2920, extension 3749.

3 Li\8360\B301\ MISC \96\96110801.GA

. , _ . . . . . . . _ , - . . - _ _ . - . . ~ . . . . ~ . _ _ . . . . _ _ . _ _ . - . . _ m._. _ _ .

i s

i j .

j 2.0 SUte4ARY OF OPERATING EXPERIENCE FOR October 1996 i

4 2.1 UNIT 2 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 2 was on system at the beginning of the

period near full power.

At'1300 on 9 October 1996 load was dropped to 350 MWE to perform the 10% closure test on the 1A Main.

Steam Isolation Valve (MSIV). During a previous test, it had fully closed. The unit returned to i full power at 1000 on 10 October 1996 following a satisfactory test.

At 0132 on 19 October 1996 load was reduced to 300 MWE to perform maintenance activity on the I. following equipment:

1A Main Steam Isolation Valve 10% closure

, 2A Reactor Feed Pump Vent Fan

. Circulating Water Flow reversing valve 1

Off Gas System

} Recirc Motor Generator speed control 1

Leaks into Dry Well Equipment Drain Sump i l

. Power was returned to 788 MWE at 1800 on 22 1 October 1996.

j At 1000 on 27 October 1996 a load reduction began to perform routine surveillance activities. Full power was resumed at 1800 on.27 October 1996.

4 j' The-Unit is currently derated 2% because of

! feedwater flow element uncertainty. This derating j may be reduced based on the results of startup

{ testing. j 1

4 h

4 I

i i

5 4

i L:\8360\B301\ MISC \96\96110801 GA

s.

2.0 SUt@lARY OF OPERATING EXPERIENCE FOR October 1996 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 3 began the~ period about 85% power in coast down. The unit is derated an estimated 30 MWE because.three control blades are inserted  !

surrounding the leaking fuel bundle.  :

AT 1800 on 26 October 1996, the 3B reactor recirculation pump tripped with indications of an electrical problem. At 0150 on 27 October 1996 j operations commenced a load drop in preparation for a shutdown. At 0201 the plant was manually scrammed to-complete the shutdown.

The 3B reactor recirculating pump motor was found to be grounded. Repairs are in progress.

i 5

5 Lt\8360\9301\ MISC \96\96110801.GA

3.0 OPERATING DATA STATISTICS 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 DATE November 3,1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: October 1996

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) : 2477 MWth (approximately 778.1 MWe Net)

4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.1 of this report.

l PARAMETER THIS MONTH I YEAR TO DATE CUMULATIVE l 5 HOURS IN PERIOD 745 7,32C 229,872 6 TIME REACTOR CRITICAL 745 2,566 165,698 7 TIME REACTOR RESERVE SHUTDOWN (Hours) 0.0 0 0 8 TIME GENERATOR ON-LINE (Hours) 745.0 2,267 157,551 9 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0.0 0 1 10 THERMAL ENERGY GENERATED (MWHt Gross) 1,739,084 4,006,282 328,543,350 11 ELECTRICAL ENERGY GENERATED (MWEHe Gross 555,201 1,245,780 104,873,784 12 ELECTRICAL ENERGY GENERATED (MWEHe Net) 530,653 1,147,205 99,116,914 13 REACTOR SERVICE FACTOR (%) 100.0% 35.1% 72.1%

14 REACTOR AVAILABILITY FACTOR (%) 100.0% 35.1% 72.1%

15 GENERATOR SERVICE FACTOR (%) 100.0% 31.0% 68.5%

16 GENERATOR AVAILABLILITY FACTOR (%) 100.0% 31.0% 68.5%

17 CAPACITY FACTOR (Using MCD Net) (%) 92.3% 20.3% 55.9%

18 CAPACITY FACTOR (Usinc DER Net) (%) 89.7% 19.7% 54.3%

19 FORCED OUTAGE FACTOR (%) 0% 50.2% 12.7%

20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: NONE

21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 6

L:\8360\9301\ MISC \96\96110801.GA

_- _ . - . --- - - . - - .-. -- --- . . . . - . .- - . ~ . - - - -

i

3.0 OPERATING DATA STATISTICS i

! 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No. 050-249 j DATE- November 3,1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS

, 1. REPORTING PERIOD: October 1996 E 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 restrict' ion

4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.2 of this report.

REPORTING PERIOD DATA PARAMETER THIS MONTH YEAR TO DATE CUMULATIVE 5 HOURS IN PERIOD 745 7,320 219,192 6 TIME REACTOR CRITICAL- 628 4,358 155,857 7 TIME REACTOR RESERVE SHUTDOWN (Hours) 0.0 0 0 8 TIME GENERATOR ON-LINE (Hours) 628.0 4,273 148,524 9 TIME GENERATOR RESERVE SHUTDOWN (Hours) 0.0 0 C 10 THERMAL ENERGY GENERATED (MWHt Gross) 1,241,977 9,508,S40 310,212,477 11 ELECTRICAL ENERGY GENERATED (MWEHe Gross 401,324 3,096,338 99,273,141 12 ELECTRICAL ENERGY GENERATED (MWEHe Net) 382,216 2,953,236 94,094,213 13 REACTOR SERVICE FACTOR (%) 84.3% 59.5% 71.1%

14 REACTOR AVAILABILITY FACTOR (%) 84.3% 59.5% 71.1%

15 GENERATOR SERVICE FACTOR (%) 84.3% 58.4% 67.8%

16 GENERATOR AVAILABLILITY FACTOR (%) 84.3% 58.4% 67.8%

17 CAPACITY FACTOR (Usino MCD Net) (%) 66.5% 52.3% 55.6%

18 'APACITY FACTOR (Usinc DER Net) (%) 64.6% 50.8% 54.1%

19 FORCED OUTAGE FACTOR (%) 15.7% 41.6% 13.7%

20. SHUTDOWNS SCHEDULED OVER THE NEXT 6 MONTHS: 1 March 1997.

21. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF  :

STARTUP: NO FIRM DATE AVAILABLE AT THIS TIME.

7 L:\B360\8301\ MISC \96596110801.ra u - - .

3.3 AVERAGE DAILY UNIT 2 POWER LEVEL l l

1 DOCKET No. 050-237 UNIT Dresden 2 DATE November 3,1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 MONTH: October-96 DRESDEN 2 j DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) 1 695 18 750 2 751 19 376 3 755 20 468 4 756 21 502 5 761 22 712 6 758 23 751 7 754 24 752 8 749 25 749 9 612 26 745 10 706 27 728 11 752 28 743 12 753 29 740 13 758 30 766 14 753 31 773 i 15 750 l 16 746 l 17 747 (Note: negative Values represent station loads) 8 Li\8360\0301\ Misc \96\96110001.GA

1 f

I

- l i

i I

3.4 AVERAGE DAILY UNIT 3 POWER LEVEL ,

1 1

DOCKET No. 050-249 UNIT Dresden 3 DATE November 3, 1996 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920  !

l l

MONTH: October-96 i DRESDEN 3 ,

DAY AVERAGE DAILY NET DAY AVERAGE DAILY NET POWER LEVEL (MWe) POWER LEVEL (MWe) !

1 616 18 604 2 658 19 605 3 648 20 603 4 644 21 594 5 643 22 591 6 637 23 590 7 632 24 592 8 634 25 590 9 633 26 496

, 10 630 27 17

11 626 28 -8 i 12 625 29 -8 13 620 30 -8 14 614 31 -8 15 609 16 605 17 603 l

(Note: Negative values represent station loads) i 1

1 9

L \8 360\9 301\ MISC \96\96110801,GA A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

. . -. - -- --.. .. . . - . . - _.~. . . . . . . . _ - .- ... . . ..

l i

l

\'

j 3.5 UNIT 2 SHUTDOWNS AND POWER REDUCTIONS l REPORT MONTH OF October 1996

[ NO DATE TYPE DURATION REASON METHOD LICENSEE SYSTEM COMPO- CORREC-j (1) (HOURS)* (2) OF EVENT CODE (4) NENT TIVE SHUTTING REPORT # CODE ACTIONS /

DOWN (5) COM- l REACTOR MENTS '

(3)  ;

4 961005 S 0 B 5 N/A N/A N/A 2.1 ,

j 5 961019 s O B 5 N/A N/A N/A 2.1 j 6 961027 s O B 5 N/A N/A N/A 2.1 Year-to-date forced outage hours = 2,281

] Cumulative forced outage hours = 22,935 TABLE KEY:

(1) (3)

F: Forced Method: l 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.

10 Li\8360\9301\ MISC \96\96110901.GA u

l l

3.6 ' UNIT 3 SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH October 1996 l

NO DATE TYPE (1) DURATION REASON (2) METHOD OF LICENSEE SYSTEM COMPONENT CORREC-(HOURS)* SHUTTING EVENT CODE CODE (5) TIVE DCWN PIPORT # (4) ACTIONS /

REACTOR COMMENTS l (3)  !

4 961028 F 117 A 1 N/A AD MO 2.2 I

l Year-to-date forced outage hours = 3,046 Cumulative forced outage hours = 23,612 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.

11 L:\8360\8301\ MISC \96\96110801.GA C -

l 0

I i

g e t 4.0 UNIQUE REPORTING REQUIREMENTS 1

4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS -

UNIT 2 AND UNIT 3 l

None 1 l

l 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 ELEh3NT 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 October 1996.

None 12 Lt\9360\8301\ MISC \96\96110801 GA

-