ML20210H551: Difference between revisions

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| number = ML20210H551
| number = ML20210H551
| issue date = 07/31/1997
| issue date = 07/31/1997
| title = Monthly Operating Repts for July 1997 for DNPS IAW Rg 1.16 & GL 97-02
| title = Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02
| author name = Abrell G, Perry J
| author name = Abrell G, Perry J
| author affiliation = COMMONWEALTH EDISON CO.
| author affiliation = COMMONWEALTH EDISON CO.

Latest revision as of 15:36, 20 April 2023

Monthly Operating Repts for July 1997 for DNPS IAW RG 1.16 & GL 97-02
ML20210H551
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 07/31/1997
From: Abrell G, Jamila Perry
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.016, RTR-REGGD-1.016 GL-97-02, GL-97-2, JSPLTR-97-0146, JSPLTR-97-146, NUDOCS 9708140076
Download: ML20210H551 (11)


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,ti We in,11 (d)iW hl Hi % 941191tl August 6,1997 JSPLTR 97 0146 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

hionthly Operating Data Report for July 1997 Dresden Nuclear Power Station Commonwealth Edison Company Docket Nos. 50 010,50 237, and 50 249 Enclosed is the Dresden Nuclear Power Station hionthly Operating Summary Report for July 1997.

This information is supplied to your of!1ce as required by Technical Specification 6.9. A.5, in accordance with the instructions set forth in Regulatory Guide 1.16. and Generic Letter 97-02.

Sincerely, \ t 1

Luge'rty e,r-J. icphen 5iit d Vice Presid it /) h. ~r)l/Up j Dresden Station ,/

Enclosure cc: NRC Region lli Office Illinois Dept. of Nuclear Safety, State ofIllinois NRC Senior Resident inspector, Dresden Station UDI, Inc. . Washington, DC File /Nuliierical

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i HONTHLY HRC r

StAMARY OF OPERATING EXPERIENCE, i PER REGULATORY GUIDE 1.16 .

FOR i

DRESDEN NUCLEAR POWER STATION t

CO M ALTH EDISON COMPANY FOR JULY 1997 I

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UNIT DOCKET LICENSE 4

1 050-010 DPR-2 2 050-237 DFR-19 3 050-249 DPR-25 1

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d TABLE OF.CONTFNTS JULY 1997 NRC REPORT 1.0 Introduction 2.0 sunenary 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 Unit 2 Shutdowns 3.4 -Unit 3 Shutdowns 4.0 Unique Reporting Requirements

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

Unit 2 and Unit 3 2

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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  :

Plaines Rivers, in Grundy County, near Morris, Illinois.

Dresden Unit 1 is a General Electric Boiling Water Reactor with a design not electrical output rating of 200 megawatts electrical (MWe). The unit is 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 liccased at 2527 megawatts thermal. The gross outputs of Units 2 and 3 are 832 and 834 megawatts electrical, respectively, with design not 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.

This report for JULY 1997, was compiled by Gary A.

Abre11 of Dresden Pegulatory Assurance Staff, telephone number (815) 942-2920, extension 3749, 3

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2.0

SUMMARY

OF OPERATING EXPERIENCE FOR JULY 1997 l 2.1 UNIT 2 MONTMLY OPERATING EXPERIENCE

SUMMARY

Unit 2 began the period at full power and remained at that level except for minor load drops for surveillance or lake temperature limitations.

Unit 2 was manually scrammed at 0139 on July 28, 1997 during a reactor vessel level t.ransient which occurred during an attempt to change operating feed pumps. The reactor was taken critical at 0915 on July 31, 1997, and will be put on system August 1, 1997.

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2.0 SUl44ARY OF OPERATING EXPERIENCE FOR JULY 1997 2.2 UNIT 3 MONTiiLY OPERATING EXPERIENCE

SUMMARY

Unit 3 operated near full power throughout the period with minor load changes for surveillance and maintenance activity.

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3.0 OPERAT;NG DATA STATISTIC 8 3.1 OPERATING DATA REPORT - DRESDEN UNIT TWO DOCKET No. 050-237 DATE AUGUST 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: JULY 1997
2. CURRENTLY AUTilORIZED POWER LEVEL (MWth): 2,527 MAXIMUM DEPENDABLE CAPACITY (MWe NET): 772 DESIGN ELECTRICAL RATING (MWe Net): 794
3. POWER LEVEL TO WilICH RESTRICTED (MWe Net): No restrictions
4. REASONS FOR RESTRICTIONS (IF ANY): See Section 2.1 of this report.

REPORTINO PERIOD DATA PARAMET ER THis MONTH YEAk TO DATG CUMULATIVE iiOUP S IN PERIOD 744 6,527 237,863 T1ht RRACTOR CRITICAL 664 4,252 171,414 TIta REACTOR RESERVE SHUTDOWN (Hours) 0 0 0 TM GENERAMR C44*LINE (Hours) 650 4,160 163,181 TI)4 GENERATOR RESERVE SHUTD N (Hours) 0 0 1 THEMMAL ENERGE GENERATED DedHt. Gross) 1, t,14, 3 0 6 9,t23,037 341.326,938 81.BCTRICAL SHRhGY GRHEAATED (HwtNe Gross) $13,9b6 3,098,36( 108,996.300 ELECTRICAL ENERGY GENERATED (lefEHe Net) 490,300 2,960,6b6 103,062,38b REACTOR SERVICE FACTOR (t) 87.44 65.1% 72.14 REACTOR AVAILABILITY FACTOR (t) 89.3% 66.1% 72.11 GENERAMR SERVICE FACTOR (t) 87.4% 63.8% 68.61 GENERATOR AVAIIABLILITY FACTOR (t) 87.4% 63.8% 68.6%

CAFACITY FACTOR (Using ICD Net) (t) 85.4% $8.81 56.11 CAPACITY FACTOR (Usin(* DER Het) (t) 83.01 $7.1t $4.64 FORCED OUTAGE FACTOR (t) 12.64 18.11 13.04

20. Shutdowns scheduled over the next 6 months: none
21. If shutdown at end of raport period, estimated date startup: Unit is in startup and will be put on system August 1, 1997.

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3.0 OPERATING DATA STATISTICS 3.2 OPERATING DATA REPORT - DRESDEN UNIT THREE DOCKET No. 050-249 DATE AUGUST 4, 1997 COMPLETED BY G. A. ABRELL TELEPHONE (815) 942-2920 OPERATING STATUS

1. REPORTING PERIOD: JULY 1997
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): Seo Section 2.2 of this report.

REPORilNG PERIOD DAT A PARAMETER THIS MONTH YEAR To DATE CUMUL.ATIVE 5 HOURS IN PERICO 744 b,087 22b,743 6 Tits REAC1oM CRITICAL 744 2488 158,345 7 TIDs REACTOR RESERVE SHunx. net (Hours) 0.0 0 0 6 TD4 (BHEkAWR (24-LINE (Hours) 744 2,331 150,8bb 9 TDS GENERA 10A RE8ERVE SHV11XM4 (Hours) 0.0 0 0 10 1wtse4AL ENERaf GEurRATED (i+4t t c ros s ) 1,809,e34 4,373,412 314,heb,se9 11 ELECTRICAL BNERGY 08HERATED petEHe Otoss) b80,39b 1,400,926 100,674,067 t 'l ELECTRICAL ENERGY GENERA 17.D 04HEHe Net) 564,674 1,320,456 95,402,057 13 REAC10R SERVICE FAC'IOR (t) 100.0t 48.9% 70.1%

14 REACTOR AVAIIABILITY FACNR (t) 100.01 48.95 10.19 15 aENERATOR SERVICE FACTOR (t) 100.04 45.et 66.81 16 CENERA10R AVAIIARLILITY FAC1un (t) 100.09 4b.84 66.Pt 17 CAPACITt FACTOR (Usirv3 M:D Net) (t) 98.31 33.6% 54.7%

18 CAPACITY FACTOR (Usaru; DER Het) (t) 9b.tt 32.7t b3.29 14.61 19 FORCED OUTAGE FAC1DR (t) 0.09 24.79

20. Shutdowns scheduled over the next 6 months: None
21. If shutdown at end of report period, estimated date of startup: N/A 7 l mo nna ioisHiseslisties ei.ot.o. l l

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, . i 3.3 UNIT 2 SHUTDOWNS t REPORT MONTH OF JULY 1997 t

NO DATE TYPE DURATION REASON METHOD CORRECTIVE  !

(2) 0F ACTIONS /  !

(1) (HOURS)*

C0144ENTS SHUTTING -

DOWN E

REACTOR (3) ,i 6 970728 r 94 o 2 tra 97-010  :

i Year-to-date forced outage hours = 921 Cumulative forced outage hours = 24,327 -

TABLE KEY:  ;

e (1) (3) .

F Forced Method:

St Scheduled 1. Manual

2. Manual Scram '

( 2 ) .. 3. Automatic Scram Reason: I. , -Other (Explain) l A Equipment Failure (Explain) 5. Load Reduction

'B Maintenance or Test -

C Redueling D Regulatory Restriction E ' Operator-Training &

Licensing Exam F -Administrative >

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Year-to-date forced outage hours = 763 Cumulative forced outage hours = 25,839 TABLE KEY:

(1) (3)

F Forced Method:

St 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 C Refueling D Regulatory Restriction E Operator Training &

Licensing Exam F Administrative G Operational Error

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