ML20195G638

Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With

ML20195G638
Person / Time
Site:	Dresden
Issue date:	05/31/1999
From:	Butterfield S, Heffley J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-02, GL-97-2, JMHLTR:#99-0070, JMHLTR:#99-70, NUDOCS 9906160127
Download: ML20195G638 (10)

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, .. Commonwcalth likson Osmpany Dresden Generating Station

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6500 North Dirsden Road Morris. IL N) ISO Tel Hl5-912 2920 Comed  !

June 10,1999 JMHLTR: #99-0070 U.S. Nuclear Regulatory Commission Attention: Document Control Desk j Washington, DC 20555 Dresden Nuclear Power Station Units 1,2, and 3 Facility Operating License Nos. DPR-2, DPR-19, and DPR-25 Docket Nos.50-010. 50-237. and 50-249

Subject:

Monthly Operating Data Report for May 1999 Enclosed is the Dresden Nuclear Power Station Monthly Operating Summary Report for May 1999.

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, and Generic 7 Letter 97-02. I Should you have any questions concerning this letter, please contact Dale Ambler, J Regulatory Manager at (815) 942-2920.

Respectfully,

[

J. M.He e .

. ce Vice Presi ent Dresden Nuclear ower Station

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Attachment cc: Regional Administrator- Region lil NRC Senior Resident inspector - Dresden Nuclear Power Station UDI, Inc. - Washington, DC 9906160127 990531 PDR ADOCK 05000010 R PDR y A Unkom Comp.my

ATTACIIMENT MONTIILY NRC

SUMMARY

OF OPERATING EXPERIENCE, PER REGULATORY GUIDE 1.16 FOR DRESDEN NUCLEAR POWER STATION COMMONWEALTII EDISON COMPANY FOR MAY 1999 UNIT DOCKET LICENSE 1 050-010 DPR-2 2 050-237 DPR-19 3 050-249 DPR-25 1

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TABLE OF CONTENTS 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 Repon - Dresden Unit 2 3.2 Operating Data Repon - Dresden Unit 3 3.3 Unit 2 Shutdowns  ;

3.4 Unit 3 Shutdowns 4.0 Unique Reporting Requirements l l

4.1 Main Steam Relief and/or Safety Valve Operations - Unit 2 and Unit 3 '

4.2 Technical SpeciDcation Amendments L

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I 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 si being decommissioned 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 August 11,1970 and October 30,1971 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.

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR MAY 1999 2.1 UNIT 2 MONTIILY OPERATING EXPERIENCE

SUMMARY

Unit 2 operated throughout the period at full power except for short periods for maintenance and surveillances. ,

1 1 2.2 UNIT 3 MONTHLY OPERATING EXPERIENCE

SUMMARY

Unit 3 operated throughout the period at full power except for short periods for maintenance and surveillances. l l

On May 3,1999, a Technical Specification action which requir-d plant shutdown was l taken due to an apparent failure of the pressure safety function of the Target Rock safety relief valve. Dresden requested enforcement discretion which was granted by the )

l NRC. This enabled Unit 3 to remain at full power. Additionally, an Exigent Technical Specification Amendment was requested to address the issue.

l On May 22,1999, at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> Unit 3 reduced power for single loop operation in ]

order to perform maintenance on the 3A Reactor Recirc Pump Motor Generator. At

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1802 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.85661e-4 months <br /> on May 23 Unit 3 was restored to full power. j i

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3.0 OPERATING DATA STATISTICS 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 DATE June 4,1999 f COMPLETED BY Sherry Butterfield i TFLEPHONE _

(815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: May 1999

2. CURRENTLY AUTHORIZED POWER LEVEL (MWth): 2,527 1

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.

I FEFGIBGR!RCDDilIA RGEEHR 1H8mE(MifR10DEE CmuAmE 2 If1RSJN HEMD 74 3,C 252,479 E TnelupCBR acTpL 74 3,62] 186,241 7 TDE 14pCERIW!ERE 55EX391 (Hauts) Q < C 0  !

2 Tea (merem 0+LTee Otars) 74 3,62] 177,898 h TDC (BWWERIWl!BtWE SEEOfi Ok1*s) 0 C 4 1C 'DEEML DRM steNGED GMft Gross) 1,872,325 9,071,674 376,9 % ,73S 1 ism.uwLmew(unused teEHa(kras) EQiQ 2,964 M 120,596,681 l

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=- ==_4 RWW GREI55D $4Who Nut) 574e1 2,841,875 114,154,908 1.1143CIR !EWEE WCER (%) 100.0c 100.0'$ 73.81 9 143CER MA3pmTyry BCER (%) 100.05, 100.0^ 73.81 7 ~GtWWER !ERWKE BCER (%) 100.0; 100.0' 70.51 12 GtEE8tKR MAIDarnriv BCER (%) 100.0Y 100.0" 70.5Y 17 (NBCZN WCER (UnirgMD142) (%) 100.0S 101.9 58.61 12 CNBCEN BCER (UlsirqIERNat) (%) 97.2Y 98.8S 56.95 15 RKID CU192 BCER (%) 0 O .05 12.21

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m 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE I

DOCKET No. 050-249 l

DATE June 4,1999 COMPLETED BY Sherry Butterfield TFI.FPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: May 1999

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 restriction

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

l FEPCRmGPERG)MTA mm msum vernomu a5RAME 5 I(ES R1 HRED 744 3,623 241,799 8 TDE NJCKR CRITEX. 744 2,956 173.151 7 TDE NJCER NRRVE S{RDON4 OtArs) 0 0 0 8 TDE GNINGtR Q4-LDE Okars) 744 2.908 165 489 9 TDE GMWGER PE!ENE SEMDON Otars) 0 0 1 10 1HReL BeJu GMRNIED $4Ht ames) 1,837,248 7097898 350.350,323 11 nacutroL maar aussano osann W 593,056 2,312.535 112.2g9 12 EIECIIGX INEIM GMHOED 0+1EHa Net) 570.281 2.220,467 106 561,975 13 IWCER 3RVEE DC1tR (%) 100.0 % 81.6 % 73 4%

14 IUCER MAEAEILT1Y DCitR (%) 100 0% 81 6 % 73 4 % ,

15 GMDFW!tR SENE2 PMitR (%) 100.0 % 80 3% 70 0% i 18 GNHGIF M&IIABIETIY DCER (4) 100 0 % 80 3% 70 0% I 17 CNBCI1Y DCER (Using MD Nut) (%) 99 3 % 79 4 % 579%

18 CNacrIY DCER (Using GR Nut) (%) {

96.5% 77.2% 56 3% j 19 RR:ED CIMME DCIIR (%) 0% 24% 12 4% l j

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3.3 UNIT 2 SHUTDOWNS REPORT MONTH OF MAY 1999 i NO DATE TYPE DURATION REASON METHOD CORRECrlVE (1) (HOURS)* (2) OF AGONS /

SHUTilNO COMMENTS DOWN REACTOR (3)

Year-to-date forced outage hours = 0 Cumulative forced outage hours = 24691 TABLE KEY (1) (3)

F: Forced Method:

S: Scheduled 1. Manual

2. Manual Scram (2) Reason: 3. Automatic Scram A Equipment Failure (Explain) 4. Other (Explain)

B Maintenance or Test 5. Load Reduction C Refueling D Regulatory Restriction E Operator Training & Licensing l Exam F Administrative G Operational Error  !

H Other (Explain) l l

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3.4 UNIT 3 SHUTDOWNS REPORT MONTH MAY 1999 l NO DATE TYPE (1) DURATION REASON (2) METHOD OF CORRECTIVE (liOURS)* SHUTTING ACTIONS /

DOWN COMMENTS REACTOR j (3) i l

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Year-to-date forced outage hours = 70 Cumulative forced outage hours = 24,761 l TABLE KEY (1) (3)

F: Forced Method:

S: Scheduled 1. Manual

2. Manual Scram i (2) 3. Automatic Scram I Reason: 4. Other (Explain)

A Equipment Failure (Explain) 5. Imad Reduction B Maintenance or Test C Refueling D Regulatory Restriction E- Operator Training & Licensing Exam F Administrative G Operational Ermr H Other (Explain) 8 8

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t 4.0 UNIQUE REPORTING REQUIREMENTS N6ne 4.1 MAIN STEAM RELIEF AND/OR SAFETY VALVE OPERATIONS -

UNIT 2 - NONE l

l UNIT 3 - NONE l

4.2 TECHNICAL SPECIFICATION AMENDMENTS l None l

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