Text

Monthly Operating Repts for May 1982
	ML20054F658
Person / Time
Site:	Quad Cities
Issue date:	06/04/1982
From:	Weinfurter E; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20054F655	List: ML20054F654; ML20054F658;
References
	NUDOCS 8206170195
	Download: ML20054F658 (23)
	v • d • e

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! QUAD-CITIES NUCLEAR POWER STATION J

UNITS 1 AND 2 i

MONTHLY PEREDRMANCE REPORT l

MAY 1982 i

COMMONWEALTH EDISON COMPANY AND l

IOWA-ILLINOIS CAS & ELECTRIC COMPANY .

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 e

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8206170195 820601 l PDR ADOCK 05000254 PDR

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TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant of Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Stean Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossa ry 1

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4 I. 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 joir.tly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Compa ny. The Nuclear Steam Supply Systems are General ' Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United 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 I to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively, pursuant to Docket dumbers 50-254 and 50-265. The date of initial reactor criticalities for Units 1 and 2 respectively were October 18, 1971, and April 26, 1972.

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

This report was compiled by Becky Brown and Erich Weinfurter, telephone number 309-654-2241, extensions 127 and 192.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE May 1-7: The unit completed load increases which were started on April 30. The load was increased at various rates to 703 MWe. The unit is continuing coastdown for End of Cycle Six Refueling Outage in September.

May 8-16: The Load Dispatcher requested a load drop to 535 MWe at 1:35 a.m. on May 8 due to low system demand. The unit started to increase load by 7: 10 a.m. to 645 MWe. At 2:35 a.m., on May 9, the Load Dispatcher requested the unit to reduce load due to low system de man d . The unit was at 435 MWe by 4:40 a.m. The unit then increased load to 640 MWe by 5 p.m., May 9 Hay 17:23: A leak in the low flow Feedwater valve drain line required the unit to be shut down on May 17 The Generator was off line at 5:12 p.m. and the Reactor scrammed at 7:30 p.m. due to an IRM Hi-Hi and MSIV closure signal. The drain line was repaired and the unit was put on line May 18 at 2:50 p.m. Load was increased normally to maximum attainable load.

May 24-31: The Load Dispatcher requested a load drop to 495 MWe due to low system demand. The unit was at 495 MWe at 3 a.m., May 24. Load was increased up to 595 MWe by 8 a.m. the same day. On May 27 the unit started to decrease load in preparation for a planned weekend outage to repair the slip rings on the Main Generator. The unit was manually scrammed at 12:50 a.m., May 28. The unit was returned to service at 1:38 p.m., May 31, and increased load to 550 MWe at the end of this month.

B. UNIT TWO May 1-4: The unit started the month decreasing load to perform weekly Turbine tests. Load was decreased to 600 MWe by 1:30 a.m., May 1.

After the test, load was increased to 808 MWe by 10 p.m., May 1.

May 5-8: On May 5, Condensate Demineralizer problems caused the unit to decrease load to 650 MWe for I hour. The unit was back up to full power by the end of the day. On May 7, Condensate Demineralizer problems again caused the unit to drop to 650 MWe for I hour while the problems were corrected. The unit was at 818 MWe by the end of the day.

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- May 9-13: On May 9, load was decreased to perform weekly Turbine tests. ,The unit was returned to maximum attainable load the same day.

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May 14-21: Starting at 4 p.m., on May 14, the unit decreased load to prepare for a planned weekend maintenance outage in order to repair main Condenser tube leaks. The unit was off line at 12:22 a.m. on '

May 15 and the Reactor was manually - scrammed at 'l':18 a.m. Following the outage, the unit was critical at 7:40 p.m. on May 16 and the Generator was synchronized at 7:40 a.m. on May 17 The unit increased load per preconditioning limitations to maximum attainable load.

May 22-29: On May 22, load was dropped to 500 MWe and then back up to 700 MWe to check vibration in the 2A Recirculation Motor-Generator Set. The unit was allowed to increase load to 807 MWe by 3 p.m.,

May 23 May 30-31: The unit dropped load to perform weekly Turbine tests at 2: 30 a.m. on May 30. Load was subsequently increased to 774 MWe.

The unit was being derated due to high vibration in the Recirculation Motor-Generator Set , thus preventing full power. The unit finished this month in this condition.

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

A. Amendments to Facility License or Technical Specifications There were no Amendnents to Facility License or Technical Specifications during the reporting period.

I, B. Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure Changes requiring NRC approval for the reporting period.

C. . Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment _

r 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 Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO -

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION ql8016 1B-1003 RHR Heat A wo,rn gasket was There were indications The gasket was replaced' Exchanger found between the of a small leak between and the system was floating head and the tube and shell sides checked satisfactorily floating tube sheet. of the heat exchanger, for leaks.

Ql8377 "B" Ma i n S t eam The monitor was out The monitor was .The moni tor was bench-Line Radiation of calibration. spiking downscale checked, calibrated, lion i to r quite frequently. and re-installed. -

ql8895 1-1001-43A The spring in the The valve motor was The spring was reset Shutdown Cooling torque switch was drawing 14.2 amp and and the internals were Suction Valve set too tight. should be 4 to 6 amps. cleaned. "I Q19341 IB Diesel The ai r compressor The compressor was The air compressor was Generator Air was faulty. inoperable. The 1A replaced with a re-Compressor compressor was still built compressor.

available.

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO -

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q19322 82-07/03L Electromatic Relief Thd control switch The relief valve failed The control switch Valve 2-203-3C connections were to open until the switch connections were loose. was jostled. tightened and the valve was re-tested.

Q16590 LPRM 16-09A The LPRM LPRM 16-09A reads high. The connector was

} connector was replaced and tested '

faulty. satisfactorily.

Ql9333 Recirculation The torque swi tch The valve would not The torque switch was Pump Discharge _ setting is not open and the circuit adjusted and the valve Valve 2 -202-5B properly adj usted. breaker thermals kept was stroked.

tripping.

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Q19404 Containment Spray A broken pin was The valve would close Installed a new torque Valve Indication found;in the but no closed switch.

2-1001-23A connecting gear of indication was received.

the torque switch.

] Ql9315 82-06/03L Drywell to Torus The vacuum breaker The valve.would not The counterweight was

] Vacuum Breaker counterweight was fully close during re positioned and all 1

2-1601-32C out of adjustment. testing. The Reactor- required testing was l was being shutdown at pe r fo rmed.

j the time.

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IV . LICENSEE EVENT REPORTS The following is a tabular summary of all licensee 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.1. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 82-09/03L 4-30-82 1C RHR Service Water

[ Pump inoperable to Repair / Repack 82-10/03L 5-19-82 1/2 Diesel Generator Cooling Water Pump Fa i lure UNIT TWO

, 82-06/03L 5-14-82 Drywell/ Torus Vacuum Breaker 2-1601-32C 82-07/03L 5-15-82 Relief Valve Failure to Open 203-3C

, 82-08/03L 5-15-82 Monitor inoperable; 2-203-3A, B, C P

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V. DATA ' TABUIATIONS 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

. _ OPERATING DATA REPORT -. . __ _ _ __ _ _ _ - . _ . _ _

DOCKET NO. 50-254 DATEJune 04 1982 ._

COMPLETED BYErich Weinfurter

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_0PERATING STATUS .

0000 050182

1. Reporting period 2400-053182' Gross hours-in reporting period 744-

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2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): '789 .

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3. Power level t o which restricted (if any)(MIde -Net): 'NA'

4. Reasons for restriction (if any) . _

This Month Yr.to Date Cumulative

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5. Number of hours reactor was critical 658' 8 '~ ~~350s~4~ ~7260f 5-

6. Reactor reserve shutdown hours _

0.0 0.0 3421.9 _

7. Hours generator on line 636.7_ 3461.9 69593.5

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8. Unit reserve shutdown hours. 0 . 0_ ' '0' . 0~ V0f."2 ~

9. Gross thernal' energy generated (MWH) 1183014 7615667_ _ 142674026 _

10. Gross electrical energy generated (MWH) 383744 2488222 46017155

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11. Het electrical energy generated (MWH) 347371 '2293940~ '42878024

12. Reactir service factor 88.5. 96.7 82.4

13. Reactor availability factor 88.5 96.'7_ 86.2

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14. Unit service factor 85.6 95.6 78.9

15. Unit availability factor 85.6 95.6_ 8 0 '. 0 _ _

16. Unit capacity factor (Using MDC) 60.7 82.3 63.3_

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17. Unit capacity factor (Using Des.MWe) 59.2 80.2 61.6 LO. Unit forced outage rate 3.3 2.1 6.9

19. Shutdowns scheduled over next 6 nonths (Type,Date ,ond Durotion of each ) :

20. If shutdown at end of report period,estinated date of startup __N,A__________ i 1

tihe MC not be lower than 7691%ie dering perleds of high onblent temperature det to the thernal perfernance of the sprop canal.

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OPERATING ' DATA REPORT .

DOCKET NO. 50-265

' UNIT- -

TWO -- - -

DATEJune 04 1982

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COMPLETED BYErich We1nfurter

- - TELEP HONE 309-654-2241 x 192- --

OPERATING STATUS

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i. Reporting period:2400 053182 Gross hours in ~ reporting periodi ~ 744 _

2. Current ly-outhor ized -p ower level ---(MWt ) 12 2511' Hox . Depend capacit y - - - - = - - -

(HWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to-which restricted (if-any)(MWe-Net)siNA--- - - - - - " - - -

4. Reasons for restriction (if any):

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This Month Yr.to Date Cumulative

-5.-Number of-hours reactor was-critical - - 701.6 - - - 252M- --- - 6737 2.1-

6. Reactor reserve. shutdown hours 0.0 0.0 2985.8

7. Hours generator.on line. 688'.7 2487.5- 6b28.7

8. Unit reserve-shutdown hours.- -

20.0 - 0 .~ 0 - - "- 7 0 2 . 9_

9. Gross thernal energy generated (MWH) . 1653583 5798547 133685630

10. Gross electrical energy generated (MWH) 533392 1873007 42579247 ii. Net-electrico1~ energy generated (MWH)- -509468- - 1780860 - 39905444 94.3 69.6 77.2

12. Reactor service factor

13. Reactor availability factor 94.3 69.6 80 7 92.6 -

68.7- -

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-14. Unit service factor 92.6 68.7_ 75.0

15. Unit avo11obility factor 89.0- 63.9 59.5

16. Unit capacity factor (Using HDC) 62.3 -58.0-

17. Unit capacity factor (Using Des.HWe) 86.8 0.0 30.3 9.5

10. Unit forced outage rote

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

20. If shutdown at end of report period,estinated date o f s t a r t u p _,,,. _N_A_ _ _ _ _ _ _ _ _

The MDC not be lwer then 769 mie dering periods of high onblent tenperatore det 1: the thernal perfernece of the sprey canal.

APPENDIX B

+ _ _ __ AVER AGE DAILY -. UNIT POWER.. LEVEL - ___ _ _ __

_ _ _ . . . _ _ _ _ DOCKET. -NO . ' 50-254 __

UNIT .ONE

. . _ COMPLETED _BYErich Weinfurter.. _ i TELEPHONE 309-654-2241xi92 DAY: AVER. AGE DAILY POWER LEVEL. __ DAY __ AVER AGE DAILYLPOWER LEVEL ..__

(MWe-Net) (MWe-Net) i, 576,3 _ _ _ _ _ _ 17. .. 335.4 _ _ ,

2. 586,3 -

18, 159.8

3. 588.0 19. ~594.1-

4. 579.2 _ .20. 543,1 _ _ _;

5, 584.9 21. 541.2

6. 584.0 22, 547.5

7. 582.0 .23 , . 538.3 _.

8. 554,5 24. 529.4

9. 543,7 25, 536,5 10, 574,7 26. 532,8 _.

ii. 564,8 27, 433.3

12. 565,5 28. -29,6

13. 558.5 29.. -26,5 14, 554.1 30. -28,1

15. 561.0 31, 155,5 l

16 . . 554.0 i

INSTRUCTIONS On this forn, list the average daily unit power level in 1%Ie-Net for each day in the reporting nenth.Conpete to the nearest whole negewett.

These figures will be used to plot a graph for each reporting nenth. Note that when narinen dependable capacity is used for the net electrical rating of the snit there may be occasions when the daily average power level exceeds the I illIline (or the restricted power level line).,In such cases,the average daily snit power evtput sheet sheeld be i festnoted to esplein the apperent onensly l

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APPENDIX B AVERAGE DAILY -UNIT POWER LEVEL' DOCKET NO.

50-265 UNIT TWO

.._:DATEJune- 0 4 -- 1982 - -- --

COMPLETED BYErich'Weinfurter-

' TELEPHONE 309-654-2241xi92 HONTH. Nov 1982 - - -- - - - -

DAY AVERAGE DAILY POWER LEVEL DAY' AVERAGE DAILY POWER LEVEL

( MWe-Ne t )- -

-- (MWe-Ne t ) - --- ---- --

1. 720.2' 17, 271.7

2. 763.1 10. 610.0

3. 775.6 19.- -756.2 - - -

4, 764.8 20, 757.9

5. 753.0 21. 766.3 6, 776.4 22. -

769.9 - -

7. 749.2 23, 752.0 H. 772.8 24. 761.4

9. 700.9 -25. 768.8 --

10, 768.7 26. 769.7 ii. 770.3 27, 765.3

12. 777.5 -28.- 775.1

13. 776.4 29, 776.7 14, 598.6 30. 714.h

15. -10.7 31. 764.0- - - -

16. -8.3 INSTRUCTIONS On this fern, list the overage daily unit power level in Mlle-Net for each day in the reperting nenth Compete to the nearest whole negawatt.

' Thew figures will be end to plot a graph for each reportina nonth. Note that when notinen dependable copecity is osed for the net electrical rating of the salt there ncy be Iccostens when the denly everage power level exceeds the 1881 line (or the restricted power level line)[In such cases,the overage daily unit power evtpst sheet shield be festnoted to explain the opperent anonely

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APPENDIX D QTP 300-S13 i UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. 050-254 March 1978

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i l UNIT NAME Quad-Cities Unit One COMPLETED BY E Weinfurter June 7, 1982 309-654-2241 -

DATE REPORT MONTH May 1982 TELEPHONE ext. 192 A $ s Ee LICENSEE b gg g ,

j 4 u-DURATION $

@3 EVENT *8 g:8

NO. DATE (HOURS) y5y REPORT NO. 8 CORRECTIVE ACTIONS / COMMENTS R

82-16 820508 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-17 820509 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-18 820517 F 21.6 A 3 CH PIPEXX Unit shutdown to repair crack in Feedwater low flow v'alve drain line 82-19 820524 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-2'O 820527 S 85.6 A 2 EB GENERA Unit shutdown to repair Gen,erator slip rings

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APPENDIX D QTP 300-513 i 050-765 UNIT SHUTDOWNS AND POWER P. EDUCTIONS Revision 5 DOCKET NO.

March 1978 !

l UNIT NAME Quad-Cities Unit Two COMPLETED BY E Weinfurter i

June 7, 1982 309-654-2241 ;

DATE REPORT HONTH MAY 1982 TELEPHONE ext. 192 i w $ H Ee m LICENSEE hg g Cou- DURATION $

p3 EVENT y8 m

g-8 j NO. DATE (HOURS) y! 5 g REPORT NO. g CORRECTIVE ACTIONS / COMMENTS R

82-16 820501 S 00 B 5 HA TURBIN Reduced load for weekly Turbine tests an'd to perform a modification test on Generator 82-17 820505 F 0.0 A 5 HG DEMINX Reduced load due to problems with a Condensate Demineralizer 1

82-18 820507 F 0.0 A 5 HG DE til NX Reduced load due to problems with a Condensate Deminsralizer 82-19 820509 S 0.0 B 5 HA TURBIN Reduced load for weekly Turbine tests

82-a0 820515 5 55.3 B 2 Hd HTEXCH Unit. shutdown.to repair tube leaks in the Main l

Condenser ,

82-21 820522 S 0.0 B 5 CB GENERA Reduced load to check vibration of the 2A Motor-Generator Set in the Recirculation System 82-22 820530 S 0.0 B 5 HA TURBIN Reducdd 1,oad for weekly Turbine tests

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s VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior 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 infornetion as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

VALVES NO. S. TYPE PLANT DESCRIPTION UNIT DATE ACTUATED ACTUATIONS CONDITIONS OF EVENTS 2 5-15-82 2-203-3A 1 Manual RX PRESS Surveillance 2-203-3B 1 Hanual 920 T.S. 4.5.D.I.b 2-203-3C 1 Hanual 2-203-3D 1 Manual 2-203-3E 1 Manual I 5-17-82 1-203-3C 1 Hanual RX PRESS Post Mainte-810 nance (replaced

pilot solenoid valve) 1 5-28-82 1-203-3A 1 Manual RX PRESS Surveillance 1-203-3B 1 Manual 950 T.S. 4.5.D.I.b

, 1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E I Manual B. CONTROL R00 DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO l

The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table 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.

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL R0D DRIVES, FROM l-1-82 TO 12-31-82 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

Insertion DESCRIPTION NUMBER S 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 (Average Scram insertion Time) 5-14 88 0.30 0.44 1.43 2.53 2.89 Uni t 2 Sequence "A" llot (11-9) 5-27 89 0.28 0.63 1.36 2 39 2.86 Unit i Sequence "A" & G-3 (26-11)

(K-7) Hot 5-30 1 0.25 0.49 0.99 1.74 1.74 Unit 1 Cold Scram Time Rod F-6 (F-6) (22-23) Replaced 5-31 1 0.33 0.72 1.57 2 74 2.74 Unit 1 Ilot Scram Time Rod F-6 (F-6) (22-23)

l VII. REFUELING INFORMATION The f ollowing information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al. , titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Inf ormation",

dated January 18, 1978.

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QTP'300-S32 n

Revision 1

-, QUAD-CITIES REFUELING March 1978 d

, INFORMATION REQUEST .

a~~ 1. Unit: 1 Reload: 6 Cycle: 7 r'

2. Scheduled date for next refueling shutdown: Sept 12, 1982 b :

3 Scheduled date for restart following refueling: Dec 4, 1982 -

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

9 YES lw r

5 Scheduled date(s) for submitting proposed licensing action and supporting

. Information:

- ' JULY 26, 1982

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

' different fuel design or supplier, unreviewed design or performance analysis

, f, methods, significant changes in fuel design, new operating procedures:

k 'lliPLEt1ENTATION OF TH'E ODYN TRANSIENT ANALYSIS CODE AND RESULTS (itCPR SCRAM TlHE DEPENDENCE) --

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s e 7 The number of fuel assemblies.

l a a. Number of assemblies in core:

after the 224 new/724 total

b. Number of assemblies in spent fuel pool: outage 1940 r,

8. The present licensed spent fuel pool storage capacity and the size of any' increase in licensed storage capacity that has been requested or is planned

, in number of fuel assemblies:

F a. Licensed storage capacity for spent fuel: 2920 1

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b. Planned increase in licensed storage: 4636 new/7556 total e

9 The projected date of the last refue. ling that can be discharged to the E

spent fuel pool assuming the present Ilcensed capacity:

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/34 XV p> ps Ft () \f EE [>

er LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2 01978

l. (D.c:.C).53.Ft.

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f .. QTP 300-S32 f- ,

. Revision 1

-, QUAD-CITIES REFUELING March 1978

, { INFORMATION REQUEST b~' 1. Unit: 2 Reload: 6 Cycle: 7

" 2. Scheduled date for next refueling shutdown: Feb 27,1983

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3 Scheduled date for restart following refueling: April 23, 1983 -

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{ 4. Will refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment:

1 9 N0 d

l S. Scheduled date(s) for submitting proposed IIcensing . action and supporting

" . Information:

NONE

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

,, ' different fuel design or suppiler, unreviewed design or performance analysis

/ methods, significant changes in fuel design, new operating procedures:

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b 7 The number of fuel assemblies. -

a. Number of assemblies in core: 192 new/724 total after the

b. Number of assemblies in spent fuel pool: outage 2132 7

/- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 2920

b. Planned increase in licensed storage: 4636 new/7556 total 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity:

i l-V LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84 LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 WPPROVED

! h- APR 2.01978

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

ACAD/ CAM -

Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor ATWS -

Anticipated Transient Without Scram BWR -