Text

Monthly Operating Repts for Oct 1981
	ML20042A567
Person / Time
Site:	Quad Cities
Issue date:	11/02/1981
From:	Weinfurter E; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20042A554	List: ML20042A553; ML20042A567;
References
	NUDOCS 8203230564
	Download: ML20042A567 (22)
	v • d • e

-

h QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 HONTHLY PERFORMANCE REPORT OCTOBER 1981 ..

COMMONWEALTH EDISON COMPANY .-

AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 I,

t

- a ggRADOCKO3230564 811102 - -

p 05000254 PDR

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 Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossa ry

~

t 9

l l

1 l

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 jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling W'ater 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 to license numbers DPR-29 and DPR-30, issued October 1, 1971, and 3 March 21, 1972, respectively, 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, 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 Robert Tubbs, telephone number 309-654-2241, extensions 127 and 174.

C t:

e

II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One October 1-8: The Unit began the reporting period holding maximum attainable load. On October 4, load was dropped to 500 MWe for four - - - -

hours to run weekly Turbine tests and change control rod pattern.

Load was increased at 5 MWe/ hour, to 803 MWe on October 6.

October 9-17: At 0030, load was dropped to 700 MWe to take the "B" Condensate Pump off and place in STANDBY. Load was picked up at 75 MWe/ hour for one hour, and at 5 MWe/ hour to maximum attainable load.

On October 11, load was dropped for one and one-hal f hours to run weekly Turbine tests; load was increased at 50 MWe/ hour for one hour and 5 MWe/ hour to 801 MWe.

October 18-21: Load was dropped to 700 MWe to run weekly Turbine tests for one and one-hal f hours. Load was increased to maximum attainable load by 1030, October 18. ,

October 22-24: At 1409, control rod F-9 scrammed to full in position when scram channel B was tripped. Load dropped to 780 MWe when the rod went in. At 1437, the rod was moved to the full out position .

under the direction of the Nuclear Engineer. A load of 805 MWe was achieved by 1945 Load was held October 23 and 24 at 810 MWe. .2 October 25-29: On October 25, load was dropped to 600 MWe to run special tests on control rod F-9 to find out why it scrammed on October 22, and to run weekly Turbine tests. At 0900, we started to increase load at 50 MWe/ hour for one hour, 25 MWe/ hour for one hour, and 5 MWe/ hour until October 26 when at 0900 a load of 810 MWe was reached.

October 30-31: At 1945, the Main Steam Line High Radiation Alarm was received in the Control Room. Load was dropped at 100 MWe/ hour to 600 MWe. The problem appeared to occur when Condensate Make-up water was added in the system. The weekly Turbine tests were run, and the Unit started to pick up load at 50 MWe/ hour from one hour and 5 MWe/ hour through the end of this reporting period.

B. Unit Two October 1-31 : The End of Cycle Five Refueling Outage is still in progress.

, T, l'

W

III. PLANT OR PROCEDURE CIIANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Speci ficat ions There were no amendments to Facility License or Technical Specifications for the reporting period.

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 and Experiments rcquiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment 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.

y L

1 b

I d L- J P W i i' t .

1

, UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON NUMBER ACTION TAKEN TO NUMCER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13958 ID RHR Service Water The pump was The pump was still Replaced the rotating Booster Pump Out- indicating high operable. elenent and performed board Bearing vibration, quarterly flow test.

Ql2437 1-1734B "B" Main The input relays The monitor was Replaced input reed Steam Line Monitor were malfunc- spiking downscale. relays and calibrated.

tioning. Other monitors were Verified proper operation.

ope rab l e.

Ql3843 LPRM 16-49C Loose connection LPRM gave erroneous Found loose connections in cable connec- reading inputs to in connector J41. Repaired tor. computer. and works o.k.

Calibrated LPRM.

Q15358 81-18/03L HPCI Turbine A loose Jam nut Motos speed changer Checked linkage measure-Speed Control was found in the did not respond to ment; tightened Jam nuts mechanical switch movement in and visually inspected linkage. Control Room. Also, remaining linkage.

Turbine turning gear would not disengage with Turbine at 1500 rpm. HPCI System was .. .

declared inoperable and outage surveillances were initiated.

Q15374 Scram Solenoid Solenoid coil The control rod inserts Replaced coil on 117 ,

1-305-117 on the valve on a Channel "B" trip. valve; rebuilt valve CRD 22-35 failed. It failed in the safe and tightened loose ,

, direction. fittings. "

d a

'~

ft .

i UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON NUMBER ACTION TAKEN TO NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Ql4801 Unit 1 250 VDC Cell "15" on the The cell was not installed cell number Cell "15" Battery 250 VDC bank has leaking. It was 32 in number 15 position.

Bank a cracked casing. still operable.

Q14799 Unit 1 250 VDC The cell had a Electrolyte was Replaced the cell.

Battery Cell 50 cracked cas ing. leaking from the cell.

The cell was still ope rab l e .

Q08478 Unit 1 250 VDC The cell was Cell voltage dropped Replaced the cell.

Battery Cell 118 worn out. below manufacturer's specifications during the battery discharge test.

Q14960 Unit 250 VDC Battery cell is The cell was still Replaced the cell.

Battery Cell 119 cracked, but not operable.

leaking.

e O

l <! y o' F I i i e UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENi s5 PETIT 10N Q15148 Reactor Building The solenoid The damper was closed Installed new solen' aid Vent Isolation valve was in its safe position. valve and tested.

Inlet Damper sticking.

2-5741B Q09405 IRM 18 A loose pin was IRM 18 is erratic and The loose pin in the found in the spikes high. connector was re-connector soldered.

between the detector and cable.

Q14822 81-18/03L "A" Outboard The Kalrez 0- The check valve failed Disassembled valve.

(H) Feedwater Check ring had the local leak rate Replaced 0-ring and Valve 2-220- deteriorated. test. The inboard pressure seal ring per 62A valve was good. package. ,

Q15121 2B inlet The solenoid The damper was closed installed new coil in isolation valve was in the safe position, solenoid valve.

Damper Reactor sticking.

Vent Ql4444 81-18/03L HPCI Steam The valve disc The check valve failed Removed old valve and (B) Exhaust Check and seat were the local leak rate installed new valve.

Valve not seating test.

properly.

QO2363 2Al 24/48V Cell voltage The cell internals Replaced Cell number 5; Ba t te ry was 1.56 volts were degraded. The voltage reading 2.18V 2-8325 following battery battery was still discharge test. operable.

l ' W , e f

I UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q02830 Unit 2 250 VDC The cell's _The battery was still Replaced cells 26 and 73 Battery 2-8350 voltage was operable.

lower than manu f ac t u re r's specifications.

6 O

l l

e f

_ __ _m_ __ J

4 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 t 3 I* reportable occurrence reporting requirements as set forth in se Li - : 6.6.B.I. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licenste Event Report i+ umber Date Title of Occurrence 81-17/03L 10-09-81 Channel "A" Fuel Pool Monitor Downscale Trip 81-18/03L 10-23-81 HPCI Inoperable 81-19/03L 10-23-81 Suppression Pool High level 81-20/03L 10-24-81 'laive Leak Detection Temperature Recorder Malfunction .

UNIT TWO 81-20/03L 9-28-81 Local Leak Rate Test Failures 81-21/03L 10-06-81 Unsatisfactory Fire Stops 4

e e

. t I

1 1

V. DATA TABULATIONS 1

,The following data tabulations are presented in this report:

1 A. Operating Data Report i

i B. Average Daily Unit Power Level 1

C. Unit Shutdowns and Power Reductions 4

4 i

o I

~

j 1

i 3

i l

k I

I i

l p1

. OPERATING DATA REPORT DOCF.ET NO. 50-[154 UNIT nr{E LATE 0ctober 2 1901

.. . COMPLETED BYErich We in f ori e r

_ . _ ~

TELEPHONE 309-654-2.24iX194 OPERATINC STATUC 0000 100181

't Repor1ing period:2400 103101 Gross hours in reporting pcriod: 745

2. Current 1v authorized power level (MWt): 2511 Max. Depend capacity (MWe -Ne:t) 76Y4 Design elec trical rating (Mue-Net): 789

3. Power level to which rest ric te d (if any )(MWe-Ne t ) : NA

4. Reasons for restriction (if any):

This Month Yr.to Date Cumulotive

3. Number of hours reactor was critical 745.0 7046.6 67752.9

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

~

. Hours generator on line 745.0 6916.8 64800.6

_ ,,,i aours. 0.0 0.0 909.2 i e w, .c :1 '766829 15717427

.t ,

131959515 s

. _ . .;>. _... I.

' . . . - .%. > - . n.

~

c. .,a -. . - , . ... ,~.

., qa . 4.t g gn ,.

,*s _

-. "'t i -

,,. ,. _.. (

- ,.yl i t - +t

.. .i i _ .... 1

12. Rcottor service factor 'i '.

13. Retctor uvallobtlity factor 100.0 9 6 . /, .3 . .7

14. Ur.' - --

fut:or ,.

100.0 9 4 . B. 78.0

15. Unit oucilability factor a ll 04.0 79.1 m6. Unit coaccity factor (Usina MDC) 94.9 '? LE.0 1" 'J n i : conoci19 2 0ctor (Usina Des.Muc) 92.5 32.0 60.5 lu. Unit forced outage rate 0.0 2.4 ? ?

19 Shutdowns schedulcd over next i nonths (Type,Dctc,ond Dorotion of each) r

20. If i:hutdown at end o f report period, estimated date of stcr*uo NA tihe GC ely be it.cr then 769.e . 6 ring pences of high c tient ter;erotre he te tie tNr-a. cerformn:e of the sprcy con 1. -- -

GP c:: /4 f 1 p C D(0 /, s LPURT DOCKEi NO. '0-2f.5 UT'll 't !!O DATE0cTober 2 $991 cot 1PLETED DYErich !cinf ur t er TELEP HONE 3 r.o-6 54 -2'; 41 X i '/ 4

. _ _ ~

OPERATING STATUS 0000 100181

1. %p or ting period:2in0 103101 Gross hours in reporting period: 745

2. Cur ren t ly authorized power level (MWt). 2511 Max. Depend cupacity (liUr-Ne 1 ) : 769* Design electrical rotino (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons, for restriction (if any):

This Month Yr,to Date Cumulotive

3. Number of hours reactor was critical 0.0 5881.0 6 ~.', 1 3 . 0

6. Reuctor reserve shutdown hours 0,0 Od 2985.8

7. Hours generator on line 0.0 5854.1 62535. 3 U, Unit reserve uhutdown hours. -

0.0 0.0 7n2.9 7

7. Gross chernal energy g e n e r a t e d ( h s' .s 0 12558041 127758449

/" ,

50. Grosn elcctrical energy aenero ed(MWH) , a948242 40669793

i. i . Net electrical energy aenerated(MWHi -1986 3737323 30094275

12. Reactor service factor 0.0 00.6 78.0

13. Reactor ovallobility factor 0.0 80.6 02,4

14. Unit service factor _

0.0 80.2 75,6

15. Unit avoilobility factor 0.0 80.2 76.5

16. Unit capacity factor (Using MDC) .3 66,6 60,3

17. Unit conocity factor (Usina Des.MWe) .3 64.0 58.0

10. Unit forced outane rate 0.0 .9 D.4

19. Shutdowns ucheduled over next 6 nonths (Type,Date,and Dur a t i on of each):

20. If uhutdown,at end of report period,estinated date of startup 12-29-81 (i IThe XX rw be Iwer th n 769 t.'e durin; terieds of hich ceicnt terperature he te the iterr21 performanct si the spray cencl. 9

g u

F1 P M n f '** f"*7 P'9 Td n n M F3 m T'~! (~~ C

,rz

(*3 ,

APPENDlX D QTP 300-S13 50-265 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

March 1978 UNIT NAME Quad-Cities Unit Two .,

COMPLETED BY Robert Tubbs DATE November 2, 1981 309-654-224i, REPORT MONTH OCTOBER 1981 TELEPHONE ext. 174 m 5 -

m = Et x 5 Ee 8 @; $ LICENSEE pg gg Co' DURATION $

@ b;

EVENT *8 g:8 NO. DATE (HOURS) y! $ $ REPORT NO.

3 8 CORRECTIVE ACTIONS / COMMENTS l R 81-17 810907 S 745 0 C 4 RC FUELXX Continuation of End of Cycle Five Refueling Outage 8 -4 1

4 (final)

a W n F1

,f ug I""9 }"I F*'l i". M f* 9 b"*! F~'1 M M M f"~1 77 * ' '

I f~ T

(',

APPENDIX D QTP 300-S1?

UNIT SilVTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. 50-254 March 1978 UNIT NAME Quad-Cities Unit On COMPLETED BY Robert Tubbs November 2, 1981 309-654-2241, DATE REPORT MONTil OCTOBER 1981 TELEPHONE ext. 174 A $ s m z Eb .

t

=

e 8 g6 LICENSEE gg gg C u-DURATION $

ic $ " EVENT *o g:o NO. DATE (HOURS) y5g REPORT NO.

8 CORRECTIVE ACTIONS /C0h..ENTS R

81-26 811004 S 00 B 5 RB CONROD Load reduction to perform Turbine tests and perform special rod maneuvers.

81-27 811025 S 0.0 B 5 RB CONROD Load reduction to perform Turbine tests and perform special test on control rod F-9 81-28 811030 F 0.0 B 5 CD INSTRU Load reduction to investigate Main' Steam Line High Radiation Alarm.

~

1 (finai) m _

(WPEi1DJX It AVERME DAILY UfJll POWER LEVEL DOC'r:E T NG. '60-269 ljNIT T WD_

DATE0c_tober _2 1901 00t1PLETED BYErich 1.le i n f o r_t e r. -

TELEPHONE 309-654-2241X$94 tia mi ll. O c t c b e.r 1981 DAY AVERAGE DAILS 'UWER LEVEL DAY AVERAGE DAILY POWER LEVEL

( h We - N e i. ) (MWe-Net)

1. --4 ,0 17. -2.9 P. - 2. __0

10. -2.8

'. -2.1 19. -2.8

4. -2,2 20. -3.3

5. -2.2 21. -- 2 . A

6. -2.2 22. -2.9

.i

". -2 2 23. -3.5 0, -- 2 . 1 24. -4.0

' . -2.7 25. -3.0

10. _ -2.8 26. -2.9

11. -2.8 27. -2.8 i?. -2.8 28. -2.3

13. -2.8 29. -2.1

i. 4 . -2.9 30. -1.0

$E. -2.8 3$. 0.0

.1 0 . - 2 .__8 I N ST R lJCT I ONS On this f cr. , list the c;erage dcily unit powe- level in M'.'e-Net for ecch hy in the repcrting monti,C;rpute to the rec est whole meccwott, Initt fig: ts lill be used to plot a creth f r ec:h re;crtina nanth. Note thol wher P.czimum depertble ccpccity is there ect te itcasions 6 Set, the dcily ciere:e pcwer level exceeds the tsed flire iCC2 t the (or net the electratti ratinglevel restricted pwer cf'the enit,In stch cases lthe cut ;ge dcily snit pewir c'utput sheet should be line). 8,'

f actr,cted ts explc,r tie'c;;c ent cncedt ( ,

APPENDIX 14 AVE R AGl" D AILY Ui1IT POWER Ll~ VEL DOCKET NO. 5 0- P54 UNIT O tJE D AT E0r t_ nb e r 2 1901 C0iFLETED BYEr ich Weinf or te r . _ _ ~

TELEP140NE309-654-2241Xi?4 i10N ili October $981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) ( M W e - ile t )

l. 709.4 17, 756,i

2. 748.4 10, 749.1

3. 752,3 19. 766,B

4. __

5n0.5 20, 740,5

'5 . 594.8 21. 755.4 6, 723.1 22. 762,1 .

7. 749,7 23. 747,0

3. 754.0 24. 757.9

9. 740.1 25. 669.3

'0.

.. 75P 1 26. 754.7

11. __ 715,6 27. 758,0 1?. 753,6 28. 755.0

13. 752,9 29. 755.5

14. 750.2 30. 731.0 15, 757.5 31. 647,0

16. "39.O INSTRllCT I ONS On this fctn, list the averc;e daily unit power loel in F'Je-Net fer exh day in the reporting nanth.Corpute to the r.ecrest whole reccwatt.

These figeres stil be used to plot a grcch for each rescrting nenth. Note that when nnimum depedble cc:xity is cf the Unit,there sw te c::csicrs when tre d:ily evere:e power level ocucs the g tsed fer tte r.ettestricted electracci retir; level line).In such cases the ever:;e daily unit power dutput sheet sh:uld te scwer 100%

ic:tr tetliretc(cr o thkain p tr,e c::crent cnon:lv ,

a 9

VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior

~

fommitments to the commission: l

-~-

A. MAIN STEAM RELIEF VALVE OPERATIONS Relief valve operations duriag 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 DESCRIPTION UNIT DATE ACTUATED ACTUATIONS CONDITIONS OF EVENTS 2 9-7-81 2-203-3E Did Not Open RX PRESS Surveillance

, (See LER 980 T.S. 4.5.D.1.b 81-17/03L)

B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There were no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

(

L

VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a Janua~ry 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 Information",

dated January 18, 1978.

d

. (*

L 1

QTP 300-532 Revision 1 QUAD-C! TIES REFUELING March 1978

-(- -

INFORMATION REQUEST l l

1. Un i_t :

2 Reload: 5 Cycle: 6

2. Scheduled date for next refueling shutdown: 8-30-81 (Shutdown EOCSI ~~-

3 Scheduled date for restart following refueling: 12-20-81 (Startuo BOC6)

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: No, Plan 10CFR50.59 Reloads for future cycles of Quad Cities Unit 2. The review will be conducted by early August, 1981.

5 Scheduled date(s) for submitting proposed licensing action and supporting in forma tion: Early August, 1981 for 10CFR50.59 related changes es90 days prior to shutdown.

6. Important licensing consideratior.3 associated with refueling, e.g., new or

'different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

~~

New Fuel Design: 1. Barrier Fuel

2. Control Cell Core _

-C 7 The .iumber of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 672

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: 1460

b. Planned increase in IIcensed storage: None 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September, 1984 (End of batch discharge capability) e[

( -:- 4PPROVED APR 2 01973 CD. C:. C). S. R.

QTP 300-532 Revision 1

~

QUAD-CITIES REFUELING Harch 1978

-(-

lHFORMATION REQUEST

1. Unit: 1 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: 9-12-82 (Shutdown EOC6T ""

3 Scheduled date for restart following refueling: 12-5-82 (Startup BOC7)

4. VIII refueling or resumption of operation thereaf ter require a technical specification change or other IIcense amendment: No, Plan 10CFR50.59 reloads for future cycles of Quad Cities Unit 1. The review will be conducted in August, 1982.

5 Scheduled date(s) for submitting proposed licensing action and supporting in forma tion: August, 1982 for 10CFR50 59 related changes ev 90 days prior to shutdown.

d

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

'different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: .

New fuel designs:

2 7 The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 820

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

a. Licensed storage capacity for spent fuel: 1460

b. Planned increase in licensed storage: None 9 The projected date of the last refueling that can be discharged to the spent, fuel pool assuming the present licensed capacity: September, 1985 8 (end of batch discharge capability) t (O, .'PPROV_Dc A

~

l APR 2 01978 Q.C.C.S.R.

I

r _

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 -

Boiling Water Reactor CRD -

Control Rod Drive EHC -