ML19343A126

Forwards Monthly Operating Repts for Aug 1980

ML19343A126
Person / Time
Site:	Quad Cities
Issue date:	09/02/1980
From:	Kalivianakis N COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
Shared Package
ML19343A127	List: ML19343A126
References
NJK-80-299, NUDOCS 8009160272
Download: ML19343A126 (1)

Text

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0 Commonwealth Edison C;as C.t es Nuc ear P0wer Station e2710 206 Avenue N0rth C:r::va, inino s 61242 Teepnene 309/654-2241 NJK-80-299 i

September 2, 1980 Di rector, Of fice of Management Information and Program Control Directorate of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

Enclosed for your information is the Monthly Performance Report covering the operation of quad-Cities Nuclear Power Station, Units One and Two, during the month of August 1980.

'/e ry t ruly yours,

COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

,/$'/' 'f 'l'#/.9.M(3,'(I

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',4G N. J. Kal ivianaki s Station Superintendent bb Enclosure OCT S

l 8009160 2 %

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1 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1980 COMMONWEALTH EDISON COMPANY AND 10WA-ILLIN015 GAS S ELECTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 LICENSE NOS. DPR-29 and DPR-30 S009160 2 7[

I l

TABLE OF CONTENTS l

1.

Introduction 11.

Summary of Operating Experience

)

A.

Unit One B.

Unit Two 151.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance i

j A.

Amendments to Facility License or Technical Specifications i

B.

Facility or Proceduie Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Event Reports i

j V.

Data Tabulations VI.

Unique Reporting Requirements i

A.

Main Steam Relief Valve Operations I

B.

Control Rod Drive Scram Timing Data Vll. Refueling information Vill. Glossary l

l.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 Mwe net, located in Cordova, Illinois.

The Station is jointly owned by Commonweal th Edison Company and towa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.

The Architect / Engineer was Sargent & Lundy, Inc. and the primary construction contractor was United 4

Engineers & Constructors.

The condenser cooling method is a closed-cycle spray canal, and the Mississippi River is the condenser cooling water source.

The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, raspectively, pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor criticalities for Units 1 and 2 respectively were October 18, 1971 ar.d April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit 1 and March 10, 1972 for Unit 2.

This report was compiled by Becky Brown and Bob Tubbs, telephone number 309-654-2241, extensions 245 and 174.

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SUMMARY

OF CPERATING EXPERIENCE I

j A.

Unit one August 1-9: Unit One began the reporting period holding a load of 496 MWe and held an average load of 485 MWe over this nine day period.

August 10: Load was reduced 100 MWe/ hour at 0500 at 400 MWe to time MSIVs and reverse condenser flow. At 0615 load was increased at a rate of 50 MWe/ hour; at 0730 the rate was reduced to 25 MWe/ hour and at 0830 load was held at 475 MWe.

August 11-16: Unit One held an average load of 473 MWe over this six I

day period.

August 17: At 0300 load was reduced per Load Dispatcher's request at 100 MWe/ hour to 400 MWe.

At 0730 load was increased to 466 MWe at 50 MWe/ hour.

i August 18: At 0400 load was reduced per Load Dispatcher's request at 100 MWe/ hour to 400 MWe.

At 044f load was increased to 470 MWe at 70 MWe/ hour.

August 19-29:

During this eleven day period an average load of 453 MWe was held.

August 30: At 0600 loat was reduced to 265 MWe to secure a reactor recirculation pump.

At 2l00 load was reduced 75 MWe/ hour to prepare for shutdown of the plant.

August 31: At 0003 the main generator was manually tripped off line in preparation for shutdown for cycle five refueling. The reactor was manually scrammed at 0323 due to a electromatic relief valve failing to reset following testing. The mode switch was placed in shutdown at 0905 ending the reporting period for Unit One in cycle five refueling.

B.

Unit Two August 1-2: Unit Two began the reporting period at a load of 709 MWe and held it for this two day period.

August 3: At 0001, load was reduced at 100 MWe/ hour to 400 MWe to perform weekly turbine tests and to reverse condenser flow. At 0730 load was increased at 50 MWe/ hour until 1130 when the rate was decreased to 8 MWe/ hour until a load of 600 MWe was achieved at 1720.

i August 4-5: Load was increased 5 MWe/ hour until 1300 when load was held at 665 MWe due to high condenser backpressure. The load in-crease was resumed at 2330 until a load of 700 MWe was reached and held at 0730 on August 5 August 6-12: During this seven day period power was held at an average load of 697 MWe.

l August 13: At 0300 load was reduced 100 MWe in one hour at the Load Dispatcher's request.

Load was increased at 0455 at a rate of 50 MWe/ hour, decreasing :o 25 MWe/ hour at 0555 and to 8 MWe/ hour at 0655 until a load of 700 MWe was achieved at 1015 August 14:

Load was reduced at 0250 to 600 MWe per Load Dispatcher's request at 100 MWe/ hour. At 0510 load was increased at a rate of 50 MWe/ hour for one hour, 25 MWe/ hour for one hour, then 8 MWe/ hour until a load of 700 MWe was achieved at 1015 August 15-16: Over this two day period an average load of 749 MWe was held. At 2345 on August 16 load was reduced at 100 MWe/ hour.

August 17-19: The weekly turbine tests were performed at 0150.

At 0310 when a load of 400 MWe was achieved, HPCI and RCIC.nonthly tests were performed. At 0730 load was increased at the following rates and times; 0730-50 MWe/ hour, 1130-8 MWe/ hour, 1200-50 MWe/ hour, 1300-25 MWe/ hour and 1400-8 MWe/ hour to achieve a load of 693 MWe at 1500.

At 1640 on August 17 load was decreased at 30 MWe/ hour for the Nuclear Engineer until 1700. A rate of increase of 5 MWe/ hour was set and held until 0730 August 18 when a load of 736 MWe was held.

At 2330 load was increased again at a rate of 5 MWe/ hour until a load of 750 was held at 0230 cn August 19 August 20-23: During this four day period an average load of 742 MWe was held.

August 24:

Load was reduced to 700 MWe at 100 MWe/ hour to perform weekly turbine tests.

Load was increased at 0145 at 20 MWe/ hour for one hour then at 5 MWe/ hour until a load of 745 MWe was achieved at 0745 August 25-28: During this four day period load was held at an average of 746 MWe.

August 29-30: During August 29 a load.

74i MWe was held until 2220 when load was reduced to 340 MWe due.

r:

fa(iure of 2A recirculation pump MG set 4KV meter transforme. i.

'O cn August 30, the MG set rate of 50 MWe/ hour to a was restarted and load was incre j

load of 500 MWe at 1700.

August 31: At 0810 load was increased at a rate of 5 MWe/ hour ending the reporting period with a load of 587 MWe.

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111.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specification On August 6, 1980, the NRC issued Amendment 57 to DPR-29 and Amendment 52 to DPR-30 for Quad-Cities Station, Units 1 and 2.

These amendments authorize changes to the Environmental Technical 0

Specifications, Appendix B, so that the 2 F per hour temperature change limit does not apply during changes in the mode of condenser cooling. Administrative changes have been made to the Station's envi ronmental moni toring reporting requi rements to bring this section into conformance with current practices and organizational structure.

B.

Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes requiring NRC approval.

C.

Tests and Experiments Requiring NRC Aporoval There were no tests or experiments performed during the reporting period.

D.

Corrective Maintenance of Safety Related Eauipment The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period. The headings indicated in this summary include Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

U?!!T _grat_ ltAi!!TQA!!CL SU? '",nY Ct t!L L n_LULYS r. EH L Liu U.R.

LER OF 01 ACT10h l' IluMEER flul'.BE R COMP 0tlEtlT ltAL FUt!CT I C:1 SAI E OPEP/.T10:1 I>f: EVE!!T f'

.,10:1 QO1273 RilR Valve (1-The torque switch The thermal tripped Replaced torque switch 1001-186A) was bad.

everytime we tried and stroked the valve to open valve.

three times.

q07103 Torus Level T ransmi t te r Indication does not Re-zerced transmitter Indicator I-needed re-agree with control and levels agreed.

1602-3 zeroed.

indication.

Q07129 IIPCI Turning Bolt was Turning gear would Cut off excess bolt that Gear 1-2303 obstructing gauge not engage on first extended from drain

lever, attempt.

casing. Test turning gear.

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UillT TWO__ MAlllTE!'AtlCE SU:1!'.ARY CAUSE i',ESut IS 5 LFI-EL.15 U. P..

LER OF Off ACT10:1 T:

o flullBET.

flUtiBLR C0 iP0tlElli MAL FUllCT 10:1 St.TE OPERAT! Oil PREVEllT

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G' 406755 Unit 2 D.G.

'B' The air compressor The air compressor was The air compressor was Air Compressor was worn.

blowing out oil, rept t and the new compres,or was tested.

3524-79

'E' Electromatic Unknown.

The valve was giving a The valve was replaced.

Relief Valve (RV-high temperature alarm.

2-203-3E) 406942

'C' Steam Line The monitor was The monitor was The monitor was calibrated Rad Monitor out of calibration.

reading low.

and tested.

(2-1734C) q07370 RCIC Inlet ticchanical steam Valve leaks and is Cut disc to 160 less than isolation cut on disc seat; putting steam into machined seat.

Stroked Valve MO cuts on seat were suppression chamber.

valve three times.

1301-61 severe.

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IV.

LICENSEE EVENT REPORTS The following is a tabular summary of all license event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 80-18/03L 8-5-80 Main Chimney Off Gas Sample Pump Tripped 80-19/03L 8-18-80 RCIC Flow Controller was left in MANUAL 80-20/03L 8-31-80 Electromatic Relief Valve 1-203-38 failed to close UNIT TWO 80-18/0ll 8-29-80 Unit 2 HPCI MGV would not come off of the High Speed Stop l

80-19/03L 8-29-80 2A Reactor Recirc Pump 4KV Meter Trans-former failure 80-20/03L 8-28-80 Valve 2-1601-57 N2 Inlet to Drywell &

Torus would iot close i

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i V.

DATA TABULATIONS The following data tabulations are presented in this report.

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions S

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OPERATING DATA REPORT s

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___.__ _ UNIT ONE

-- Sectember 2. 1o80 DATE s

COMPLETED BY R. Tubbs

-.-.__-. T EL E P H O N E 309-654-2241. ext._176.__

OPERATING STATUS

-._ _ _ 0 0 0 0 -. 0 8 0 18 0____

1.

Reporting period:2400 083180 Gross hours in reporting period:

744

2. Currently au t h or i z ed -. p o wer leveLlMWt) L2511-Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 3.-. Power level t o. wh ich. r e s t r ic t e d Li f _an y M MWe-Ne t) L N A - - ____

4.

Reasons for restriction (if any):

This Month Yr.to Date Cumulative

5. Number of hours recc. tor _was_ critical._. -

723.4._.

5725.1__

60439.2 _

6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 720.1 5623.1 57664.0 8._ unit r e ser ve shu t d own. h o ur s.---

0. 0_ _

0. 0 __ _

.909.2_.

9.

Gross thernal energy generated (MUH) 1077710 11394718 115938699

10. Gross electrical energy generated (MWH) 329718 3662730 37285784

11. Ne t - e le c t r ical-. a ner g / - g ene r a t ed ( MWH). ---.-

291109--

3385639--._ 34801145--

12. Reactor service factor 97.2 97.8 83.0

13. Reactor ovallobility fcctor 97.2 97.8 87.7

14. Unit. service fcctor 9 6. 8. _- _

.- 96.0 _-

79. 2 _.

15. Unit avoilobility factor 96.8 96.0 80.4

16. Unit capacity factor (Using Des.MWe) 50.h 75.2 62.1

17. Unit-copocity factor (Using MDC-)

.49.6--.---

73.3-60.6---

13. Unit forced outage rote 0.0 3.6 7.0

'9.

Shutdowns scheduled over next 6 months (Type,Date,ond Duration of each):

20. If shutdown et. end.ot report. p e r i o d, e s t inc t e d. d c t e_. o f-_ s t ar t u p. _ _J,,l,.-22-8 0_ _ _

tihe MC sy be Icwer then 769 MWe daring periods of high emblant tesperature due to the therul performance of the sprop ccnal.

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OPERATING DATA REPORT 9

DOCKET NO.

50-265 k

9

_.. _ _ _. _ _ _ _ _. _.. _ _.. _ _ _.. __ _ _. UNIT TWO Q

DATE September 2, 1980 COMPLETED BY R. Tubbs TELEPHONE 309-654-2241, ext._176 _

OPERATING STATUS

_ _ _ _._.0000_080180 _ _ _ ___ _.-_ _ _

-. ~ -

1. Reporting period:2400 083180 Gross hours in reporting period:

744

2. Currently authorized power _ level (MWt): _2511-Max. Depend. capacity (MWe-Net)i 769* Design elec teical roting (MWe-Net): 789 3.

P owe r -.le v e l..t o which _r e s tr ict ed lif any ).(MWe--Ne t )..LN A - ___ _ ---

4.

Reasons for re s tr ic t i on (if any):

This Month Yr.to Date Cunulative 5.

N u nb e r - o f h o u r s - r e cc-t o r - wa s c r i-t i c al___ - _ 74 4 0 -____3061. 5_ - 5619 0,4 -

6. Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 744.0 2942,0 53733.8

8. Unit reserve shutdown houns-_--- __._____

0. 0 _ _. -

.0.0-__.

702.9 _

9.

Gross thermal caergy generated (MWH) 1660264 6455054 109471163

10. Gross electrical energy generated (MWH) 512083 2017686 34880736

11. Net electrical energy generated (MWH)------

488388__

1880976 _.__,32623501.--___

12. Reactor service factor 100.0 52.3 78.1

13. Reactor ovallobility factor 100.0 52.3 82.3 14 _ Unit.. service factor ___

100.0-50.2 _

7 4. 7 _ _.-

15. Unit ovallobility factor 100.0 50.2 75.7

16. Unit capacity factor (Using Des.MWe) 85.4 41.8 59.0 17 -. Un i t. cap aci t y_ f ac t o r. lusin g. MDC)._ _ _.._.

83.2 _

4 0. 7_.

57.5._

18. Unit forced outage rate 0.0 7.0 9.1 1

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):

20. If shutdown..ct end o f r ep or t. p er i od, e st inc t e d da t e -o f.. s t n t up____[_A_,;

• The sX ny te lower than 769 MWe during periods of high ambiant te=perstvre due

?s the therul perforpince :( the sprov canal.

APPENDIX B

\\v AVERAGE DAILY UNIT POWER LEVEL 4

9 DOCKET NO.

50-254 9

UNIT ONE g

._ D ATE __ Sep tembe r 2, 1980 ____._

COMPLETED BY R. Tubbs MONTH Auaust 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) _

_ _(MWe-Net) _._ _.

1.

438.9 17, 399.8 2.

432.1 18, 410.9 3.

434.5

.__19.

404.7 4.

436.3 20.

402.0 5.

425.1 21.

407.2 6.

429.9

. _ _ 2 2.__

400.5 7.

426.4 23, 394.5 8.

423.6 24.

396.0 9.

414.6 25.

396.7 10.

413.9 26, 390.8 12.

417.6

.28, 386.5

1. 3.

413,8 29, 385.0 14, 418.8 30.

235.7

.15,

408.2 31.

-35.0 16.

415.0 INSTRUCTIONS On this firm, list the average daily snit power level in MWe-Net for each day in the reporting month Compute to the nearest whole aegawatt.

These figures will be ssed to plot o grech for-each reporting manth. Note that when sciimon dependele cepecity is -

used for the net elettrical rating of the snit there may be occasions when the daily overage power level exceecs the 1988 line (or the restricted power level line),In such cases,the avtr:ge hily snit power evtpot sheet should be instnoted ta explain the apparent anoncly

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO

@9

_.._ DATE September 2, 1980 _. _

COMPLETEli BY P. Tubbs MONTH Avaust 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

'"We-NetL i.

673.9 17.

550.7 2.

671.7 18, 698,i 3.

518,1

_19._

704.2 4.

620.4 20.

699.3 5.

649.2 21, 712.0 6.

659.8

_______._____.22.

709.0 7.

658.2 23, 696.6 8.

659.2 24.

706.5 9.

654.7

_ 25.

709.5 10.

666.9 26, 707.4

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

ii.

666.3 27.

708.6 12.

670.2

_28.._

707.5 13, 650.7 29.

686.2 14.

665.6 30.

379.0 15.

686.1 31.

496.6 16, 707.4 On this fern, list the average daily unit power level in PVe-Net for ecch day in the reporting month.Co=pute to the nearest whole negawatt.

These figures will be used te pitt a graph for t'ich reporting month. Nste that when matinum dependable capacitt is-used for the net electrical roting of the sait there may be occasions when the daily average power level exceeds the 1001 line (or the restricted power level line).,In such cases,the average daily unit power outpst sheet should be t

l festnoted to explain the apparent onomaly

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APPEllDIX D QTP 300-S13 UtilT SilVTDOWilS AtlD POWER REDUCTIO!ls Revision 5 50-254 tiarch 1978 DOCKET t10.

COMPLETED DY R. C. Tubbs UtilT tlAtiE Quad-Cities Unit __One DATE September 1, 1980 REPORT '40!1Til AUGUST 1980 TELEPl10tlE 309-654-2241,

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12 800830 S

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tlA flA flA flA Load reduction due to securing of reactor feed pump 13 800831 F

20.6 A

1 80-20/03L 302 VALVEX Reactor scranmed (rather than shutdown), for cycle tiva refueling outage, due to failure of an electro-matic relief valve to reset af ter testing w

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VI.

UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on pric.r commitments to the commission:

A.

MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

VALVES NO. & TYPE PLANT UNIT DATE ACTUATED ACTUATIONS CONDITIONS DESCRIPTION OF EVENTS Rx Press 1

8-3'-80 1-302-3A 1 Manual 930 Surveillance T.S.

1-302-jB 1 Manual 930 4.5.D.'i.b.

(1-302-3B

!-302-3C 1 Manual 170 actuated but would not 1-302-3D 1 Manual 170 close.

Rx was manually 1-302-3E 1 Manual 170 scrammed.

Valves 1-302-3C, D, E were actuated after the scram).

B.

CONTROL ROD DRIVE Sr, RAM TIMING DATA FOR UNITS ONE AND TWQ The basis for reparting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.I. and 4.3.C.2.

The table on the following page is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.

i 1

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 &2 CONTROL R0D DRIVES, FROM l-1-80 TO 12-31-80 AVERAGE TIME IN SECONDS AT %

Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION NUMBER 5

20 50 90 Technical Specification 3.3.C.I &

.DATE OF RODS 0.375 0.900 2.00

3. 5 7 sec.

3. 3.C.2 ( Averaae Scram insertion Time) 8-30 66 0.28 0.65 1.42 2.51 G-9 3.03 Seq B Hot Scram Timing Unit 1 informational prior to outage i

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REFUELING INFORMATION I

The following information about future reloads at quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) f rom D. E.

O'Brien to C. Reed, et. al., titled "Dresden, Quad-Cities, and Zion Station - NRC request for refueling information dated January 18, 1978.

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F.evision 1 QUAD-CITIES REFUEll!!G March 19 N 1!!FORMATlC" TiEOUEST

(

1.

Unit:

1 Reload:

5

_ cycle:

6 2.

Scheduled date for next refueling shutdewn:

8_31y8n (sn,w,..n (gc;;

i 3

Scheduled date for restart folicwing refueling:

12-7-80(Startun ECC67 4.

Uill refueling o'r resumptien of operation thereaf ter require a techaical 4

specificaticn change er other license amendment:

No, Plan lOOFR50.59 'reloed:

for future cIcles of Quad Citics Unit 1.

The revieu will be conducted in June, 1980.

l scheduled date(s) for submitting preposed licensing action and supporting 5

i nf orma tion:

June, 1980 for 10CFR50.59 related changes a 90 days prior bo chutdown.

S.

Important licensing considerations associated with refueling, e.g., new or i

'different fuel desigh or supplier, unreviewed design or performance dnalysis methods, signi ficant changes in fuel design, new operating procedures:

"cu fuel designs:

Retrofit 6:-:8 f6el 2.63 U/c% (^ 224)

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The aumber of fuel assemblies.

!! umber of assemblies in core:

724 a.

b.

I umber of assemblies in spent fuel pool:

596 C.

The Jesent licensed spent foal poal stcrcge c2paci ty and the c ite of ar.y l

i n.. c a :- e in licensed storage a pacity that has been requested or i s planncd in numner o.

vue,, a m m.2.ics:

1 3 Licensed storage capaci ty for ' spent fue1:

1h60 a.

s.

h.

Planned increase 12 IIcensed storage:

I!One s

S.

The projected date of the last refueling that can be discharger to :be.,y y

n c,, g. - ; ~,,g m

.a

- m 4

f *s i#N'

$., V 9

}

~ *

• v D

n <

M u,. e...

a s

m.

J WD V

,_m_

QTP 333-532

.e.ev i s i on 1 (UAD-C IT I ES RIE JEU NG "crch 1973

.n... :. c..c -

p. ;. O,o.

I v.,,

r r.

o n.

u. v. >.

~

e 1.

Unit:

2 P,e load :

4 Cycle:

_5 2.

Scheduled date for ne.n refueling shutdo..in:

11-4'79 (Shutic.in EC:

3 Scheduled dat.e for restart folic. ing refueling:

1-17-80 (St'trtun RC.CE 4.

Uill refueling or resumptica of operatica ther2after require c technical

~

specification change or othar license amendment: lic, Plan 1CC.".R50.59 Relcad.

for future cycles of C.nd Cities Unit 2.

The revleu will be conductu by early September, 1979 5

scheduled date(s) for submitting prcposed licensing cctica and supporting information: Early. August, 1979 for ICCFR50 59 related chans;es a 90 days prior to shutdown, 9

o.

Important l.icensing consid2rctions associated w.t,a re:uel.ing, e.g., new or i

' di f ferent fuel design or supplier, unreviewed design or performance cnclysis cethods, significant changes in fuel design, new cperating proccdures:

l

'!ew Fuel resign:

Retrofit &:8 fuel (120'!

al nat. U at bundle top and bottca b

c., i o,.,,,.,

.. u a v =,

.,c,a:

v.

u _..

}-

c neu en"1chment d.'.0 tr:.but ic n d)

v. #

A,,,.4..n_u

- e a

9 r.. ' n.' ' 4 n~ C_s*

'u' m.

Pc.-

^v..>.G

C ' H, _ Oo "m'.',

v ~., '_ e ~,-

'"h 4 -

.C ' ~' a _'

A_^ " 4 e,..

a a_c m

~

I and Dresden Unit 2 C cla 7.

f 7

The number of fuel assemblies.

a.

Number of assemblies in core:

7 2 't t

t b.

Number of assemblies in spent fuel pcol:

492 yhe present l i c e n s e t. spent fuel paci storage ccpacit/ ana. tne size u:. c.y o

v.

incr.'ase in licensed stcrap conceit / that has 'een requestec or is irr,ed in numoer o.-

.ces a n em.a... = :,.

t.

a.

Licensed storage capacity for spent fuci:

1h @

I b.

Planned increase in licensed storage:

7:cg 9

The projected date of the last refueling that can be discharcE to the r

• ' 1 ~

[ ~i,

0

Vill.

GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

Control Rod Drive System CRD SBLC Standby Liquid Contrei System MSIV Main Steam isolation Valve RHRS Residual Heat Removal System PCic Reactor Core Isolation Cooling System

. 'PC I High Pressure Coolant injection System 3RM Source Range Monitor IRM Intermediate Range Monitor LP RM Local Power Range "onitor APRM Average Power Range Monitor TIP Traveling incore Probe RBCCW Reactor Building Closed Cooling Water System TBCCW Turbine Building Closed Cooling Water System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System HEPA High-Efficiency Particulate Filter RPS Reactor Protection System IPCLRT Integrated Primary Containment Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS RBM Rod Block Monitor i

BWR Bciling Water Reactor In-Service inspection ISI MPC Maximum Permissible Concentration PCI Primary Containment isolation SDC Shutdown Cooling Mode of RHRS LLRT Local Leak Rate Testing Maximum Average Planar Linear Heat Generation Rate MAPLHGR R0 Reportable Occurrence DW Drywell RX Reactor EHC Electro-Hydraulic Control System MCPR Minimum Critical Power Ratio PCl0MR Preconditioning Interim Operating Management Recommencations LER Licensee Event Report ANSI American National Standards Institute NIOSH National Institute for Occupational Safety and Health ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring

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