Text

Monthly Operating Repts for Apr 1982
	ML20051R183
Person / Time
Site:	Quad Cities
Issue date:	05/03/1982
From:	Weinfurter E; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20051R115	List: ML20051R070; ML20051R183;
References
	NUDOCS 8205170440
	Download: ML20051R183 (20)
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m QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT APRIL 1982 COMIONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS CAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 82 0 517 o 4'Yo

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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,. Experheents, 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

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VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information 1-VIII. Clossary 4

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I. INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling

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Water Reactors, each with a Maximum Dependable Capacity of 769 MWe r.et located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Cae & Electric Com pa 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 to license numbers DPR-29 and DPR-30, issued October 1,1971, and 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.

Canmercial generation of power began on February 18, 1973 for Unit 1 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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11.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE April 1-16: The unit started the month in the coastdown mode of operation at a maximum attainable load of 730 MWe. On April 3, at 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , load was reduced to 700 MWe to perform weekly Turbine tests. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months , load was increased 25 MWe/ hour to 727 MWe.

April 17-18: On April 17, at 1310 hours0.0152 days 0.364 hours 0.00217 weeks 4.98455e-4 months , the Reactor scrammed on low condenser vacuum af ter a valve on the Condensate Demineralizer System.

failed open. The valve was repaired and Reactor startup commenced.

At 1953 hours0.0226 days 0.543 hours 0.00323 weeks 7.431165e-4 months the Reactor was made critical, and the unit was placed on-line at 120 MWe by 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months . At 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months , on April 18, the unit was at 400 MWe, increasing load in accordance with preconditioning limits to maximum obtainable load.

April 19-29: At 1133 hours0.0131 days 0.315 hours 0.00187 weeks 4.311065e-4 months , on April 19, the Reactor scrammed when a contractor, installing braces on an instrument rack, inadvertently hit the instrument rack with a hammer causing a spurious Group I Isolation signal. The Reactor was made critical at 1656 hours0.0192 days 0.46 hours 0.00274 weeks 6.30108e-4 months and the unit was on-line by 2013 hours0.0233 days 0.559 hours 0.00333 weeks 7.659465e-4 months . The unit was at 550 MWe, April 20, at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months . At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months , load was increased in accordance with pre-conditioning limits to 740 MWe. Xenon then was allowed to build in to bring load to 668 MWe.

April 30: At 0943 hours0.0109 days 0.262 hours 0.00156 weeks 3.588115e-4 months the Reactor scrammed on Reactor Low Water Level when tbc "B" Reactor Feed Pump Discharge Valve spuriously went closed, causing a partial loss of Feedwater flow. Recovery from the scram was normal and the Reactor was made critical at 1525 hours0.0177 days 0.424 hours 0.00252 weeks 5.802625e-4 months .

The unit was placed on-line at 1914 hours0.0222 days 0.532 hours 0.00316 weeks 7.28277e-4 months and increasing load at the end of the month.

B. UNIT TWO April 1-9: The unit started the month at a maximum attainable load of 800 MWe. On April 3, at 0000 hours0 days 0 hours 0 weeks 0 months , load was reduced to 700 MWe at a rate of 100 MWe/ hour to perform weekly Turbine tests. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months load was increased at 50 MWe/ hour to 755 MWe then at 5 MWe/ hour to 815 MWe.

April 10-17: On April 10 the unit reduced load to 600 MWe to perform weekly Turbine tests. At 0240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months , a load increase of 50 MWe/ hour was initiated up to 700 MWe, then 5 MWe/ hour to 815 MWe. At 2145 hours0.0248 days 0.596 hours 0.00355 weeks 8.161725e-4 months , on April 11, load was decreased to 600 MWe due to Condensate Deminera-lizer problems. Load was increased at 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months on April 12 until maximum obtainable load was achieved.

April 18-24: At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , on April 18, the unit load was decreased to 700 MWe to perform weekly Turbine tests. At.0330, load was increased at a rate of 50 MWe/ hour for one hour, then 5 MWe/ hour to 814 MWe.

Two Condensate Demineralizers were taken out of service at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months on April 18, and load was decreased to 600 MWe. On April 19, at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months , load was increased at 50 MWe/ hour for two hours then 5 MWe/ hour to 815 MWe.

April 25-30: On April 25, at 0000 hours0 days 0 hours 0 weeks 0 months , load was reduced to 700 MWe for weekly Turbine tests. At 0220 hours0.00255 days 0.0611 hours 3.637566e-4 weeks 8.371e-5 months load was increased 50 MWe/ hour to 750 MWe, then 5 MWe/ hour to 810 MWe; the maximum attainable load which was maintained through the end of the month.

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

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A. Amendments to Facility License or Technical Specification There were no Amendments to Facility License or Technical Specifications during 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 or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related r.alntenance 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.

4 UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q18488 1-1601-59 The control switch The valve would close The switch contacts Nitrogen contacts were dirty, when the control switch were cleaned.

Make up Valve was in the " NEUTRAL" position. Closed is the safe valve position.

Q18500 06-35 CRD The cylinder lining The control unit The Accumulator was Accumulator and 0-Rings were continuously alarms on replaced and checked worn. high water level. Scram for leaks.

capability not af fected.

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7 UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q16790 IRM 15 The range overlap When the IRM is on The range overlap was out of adjust- Range 6 with a down- was reset.

ment. scale ir.dication, it is still on scale on Range 7. RPS function not af fected.

Q16663 LPRM 24-35A The cable connector The LPRM read down- The connector was was faulty. scale. repl aced.

Q16667 LPRM 16-25A The cable connector The LPRM read down- The connector was was faulty. scale. replaced.

Q16666 LPRM 48-17A The cable connector The LPRM read down- The connector was was faulty, scale. replaced Qi6667 LPRM 16-09A The cable connector The LPRM reads up- The connector was was faul ty. scale. replaced.

Qi6668 LPRM 40-09A The cable connector The LPRM read down- The connector was was faul ty. scale. replaced.

Q18334 Radiation The monitor MSL rad monitor reads The monitor was Mon i to r - Ma i n calibration had about 30 higher than re-calibrated.

Steamline "C" drifted, other monitors. Monitor was operable.

Q18365 Drywell Vent The instrument air During surveillance The pressure switch was Valve to Reactor pressure sensing testing, the valve re-calibrated and valve Bldg Vent 2-1601- switch was out of failed to close on low closure was successfully 24 calibration. air pressure. Valve tested.

was operable.

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Q18366 Inboard' Air Purge The inst rument ai r During surveillance A new pressure switch was Supply Valve 2- pressure sensing testing the valve failed installed and valve 1601-21 swi tch was faul ty. to close on low air pres- closure was successfully sure. Valve was operable. tested.

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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 1 Specifications.

UNIT ONE 1

Licensee Event Report Number Date Title of Occurrence '

82-6/03L' 4-12-82 High.Drywell Pressure Switch Setpoint Drift (1-1001-89B) 82-7/03L 4-15-82 ID RHR Service Water Pump inoperable 3

8/03L 4-20 RCIC Stsam Line High Flow UNIT TWO 82-4/03L 2-24-82 RCIC High Differential Pressure Switch 2-1360-IB+ Setpoint Drift 82-5/03L 4-20-82 High Drywell -Pressure Switch Setpoint Drift t

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V. DATA TABUIATIONS The following data tabulation 4 are' presented in this report:

A. Operating Data Report 1 B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions 4

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OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATEMov 04 1982 COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 040182

1. Reporting period 2400 043082 Gross hours in reporting period: 719

2. Currently authorized power level (HWt): 2511 Mox. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789

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

4. Reasons f'or restriction (if any):

This Month Yr.to Date Cumulative'

5. Number of hours reactor was critical 701.2 2845.6 71944.7

6. Reactor reserve shutdown hours 0.0 0.0 3421.9 7.. Hours generator on line 690.5 2825.2 68956.7

8. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thernal energy generated (MWH) 1426135 6432653 141491012

10. Gross electrical energy generated (MWH) 464938 2104478 45633411

11. Net electrical energy generated (MWH) 425336 1946569 42530653

12. Reactor service factor 97.5 98.8 82.3

13. Reortor avo11ob111ty factor 97.5 98.8 86.2

14. Unit service factor 96.0 98.i 78.9

15. Unit ovellability factor 96.0 98.i 79.9

16. Unit copocity factor (Using MDC) 76.9 87.9 63.3

17. Unit capacity factor (Using Des.MWe) 75.0 85.7 61.7

18. Unit forced outage rate 4.0_ i.9 6.9

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

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

8Ihe ABC not he lwer then 7691%ie daring periods of high asient tenperatore due to the thernal perfernance of the sprey tonal.

OPERATING DATA REPORT

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DOCKET NO. 50-265 Y

UNIT TWO DATEHov 04 1982 COMPLETED BYErich' Weinfurter '

TELEPHONE 309-654-2241x192 _

OPERATING STATUS 0000 040182

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1. Reporting period 2400 043082 Gross hours in reporting periods -719

2. Currently authorized power level (HWt): 2511 Hux. Depend capacity (MWe iN'et)i 769* Design elec'trical rating (HWe-Net): '789 '

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

4. Reasons for restriction (if any):

t This Month Yr.to Date Cunulative

5. Number of bours reactor was critical 719.0 1918.7 66670.5

6. Reactor reserve shutdown hours 0.0 0.0 2985.0 l

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! 7. Hours generator on line 719.0 1798.8 64040.0 l 0. Unit . reserve shutdown hours. O.0 0.0 702.9 l

1766671 132032047

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9.. Gross thernal energy generated (MWH) 4144964'

10. Gross electrical energy generated (HWH) 573438 1339615 42045855' I

11. Net electrical energy generated (HWH) 548632 1271392 39395976 _

-12. Reactor service factor -

100.0 63.2 77.i-

13. Reactor ovo11obility factor 100.0 63.2. 80.5' 114._ Unit service factor 100.0 62.5 74.0 i .

'15 . Unit avo11obility factor -

100.0 62.5 74.9.

_16." Unit capacity'foctor (Using_HDC) 99.2. 57.4 59.2 17.__ Unit copacity factor'(Using Des.HWe) 96.7 .56.0 57.7 18.-Unit forced outage rate 0.0 37.5 9.6

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

20. If shutdown;ot end of report period,estinated date of startup __NA_________

SIhe litt ney k lower then M9181e dering perleds of high e41 eat tenperatore doe to the thersel perfernesce of the sprey cenel.

l APPENDIX B l AVERAGE DAILY UNIT POWER LEVEL l l

DOCKET NO. 50-254 UNIT ONE DATEMov 04 1982 COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241x192 MONTH Apr11 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

( MWe-Ne't ) (MWe-Net) ..

1. 657.3 17, 325.9 2.

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'660.5 18, 503.8

3. 655.0 19, 308.5

4. 664.3 20. 568.5

5. 638~3

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655.0 21.

6. 661.5 22. 609.0

7. 654.5 23. 609.9

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8. 650.5 602.B'

9. 647.7 25. 573.0 10, 643.5 26. 610.5

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11. 643.5 -

27.

'i2. 634.8 28. 595.8

'13, 632.3 29, 592.5

'L4. 632.3 30. ~ 261.~ i ~ ~

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15. 622.2 16, 618,8 INSTRUCTIONS ~

On this fwn, list the e,erege dolly seit peer level in Mue-Net for each der in the repwting unth Cegete to the neerest uhele negemett.

the ig w es vill be e to slet a f r each repeting math. Note that when monima dependable copecit, is ._

f r the net electr re11ag e t there new be occasions when the delly everage pwer level exceeds the 1 ne (w the restr d pwer 1 1 ).,In sich fases,the overage dolly enit twer detpet sheet should he

- eetnoted to explain the apperent onenelf

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APPENDIX B -

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEMay 04 1982 COMPLETED BYErich Weinfurter

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TELEP HONE 309 -654-2241x i92

,NONTH April 1982

. DAY AVERAGE DAILY POVER LEVEL DAY AVERAGE DAILY POWER LEVEL

, (HWe-Net) (MWe-Net)

1. 765.3 17, 782.2

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2 .' ' '766'.8 18. ~753.~8 3.- 750.5' 19, 691.0

4. 775.7 20. 778 i

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5. 776.~0 21. 7 7 5~ ' 2 ~ ~ ~ ^ ~ ~ ~

6. 783.8 22. 774.5 7 .- 778.8 23, 768.9 g

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780.8 - 24'.-

9. 771.8 -25. 694.6 _

to. 694.2

26. 788.6

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' i. i . 761.8~ ~27. ~~ 759.8'~~ .

12. 7 i i .' 5 28, 758 i __

L3. 773.5 29 .- 787.3 7 y..___ _

780.2'

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' 15 . - 772.2 _ _ _. _

L6. 775.3

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' INSTRUCTIONS

~ On this forn, list the seeregt deil enit t power level-in IWe-Net for each der in the reporting nenth. Compete to the neertst whole negemett.

Then figeres will be syd to slet a graph for each reperting nenth. Note that when sozinen dependeble cepecitt is ogej for the net electrical reitng of the sait there ney be occostens when the daily everage power level excetes the' ~~ ~ '+ ~~~~

1551 Une ter the restricted power level line),In soch cases,the everage daily snit power setpet sheet should be festnoted to esplein the apperent enemely

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APPENDIX D QTP 300-513 DOCKET NO. 050-254 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 March 1978 U, NIT NAME quad-Cities Unit On

. COMPLETED BY E Weinfurter DATE May 3, 1982 REPORT HONTH April 1982 TELEPHONE x 92 w 5 s w = Eb x 5 Ee 8 @ $ LICENSEE gg gg NO. DATE C '-

DURATION $

@{3* EVENT *8 g3 (HOURS) yIg REPORT NO. 8 CORRECTIVE ACTIONS / COMMENTS R

82-12 820403 S 0.0 B 5 HA ZZZZZZ Reduced load for weekly Turbine test

, 82-13 820417 F 10 33 A 3 HG VALVEX' Reactor scram on low condenser vacuum due to condensate demineralizer valve failure 82-14 820419 F 8.66 H 3 ZZ ZZZZZZ Reactor scram on high main steam line flow, when craf ts hit instrument rack with hammer causing spurious trip signal 32-15 820430 F 9.5 A 3 CH VALV0P Reactor scram on Reactor low water level caused by "3" Reactor feed pump discharge valve going closed l

(final) 9 9 --e- -._-_________

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APPENDIX D QTP 300-513 050-265 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

March 1978 UNIT NAME Quad-Cities Unit Tw -

COMPLETED BY E Veinfurter MaY 3' 1982 309-654-2241, DATE REPORT MONTil TELEPHONE APRIL 1982 ext. 192 m 8 -

m 2 eb t 5 Ee 8 g$ LICENSEE gg gg g DURATION $ g$" EVENT *o j= 3 u- "

NO. DATE (HOURS) y' 5 y REPORT NO.

8 CORRECTIVE ACTIONS / COMMENTS R

82-10 820403 S 0.0 B 5 HA ZZZZZZ Reduced load for weekly Turbine test 82-11 820410 S 0.0 B 5 HA ZZZZZi Reduced load for weekly Turbine test 82-12 820411 F 0.0 A 5 HG DEMINX Reduced load due to problems with a condensate demine ra l i ze r 82-13 820418 S 0.0 B 5 HA ZZ7ZZZ Reduced load for weekly Turbine test 82-14 820418 F 0.0 A 5 HG DEMINX Reduced load due to problems with a condensate demineralizer 82-15 820425 S 0.0 B 5 HA ZZZZZZ Reduced load for weekly Turbine test (final)

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VI. UNIQUE R120RTING REQUIREMENTS The following items are include.* I this report ')ased en prior caemitments to the commission:

A. MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Stean Relief Valve Operations for the reporting period, B. CONTROL ROD DRIVE SCRAM TNING DATA POR UNITS ONE AND TWO There was no Control Rod Drive Screa Timing Data for Units One and Two for the reporting period.

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VII. REFUELING INFORMATION -

The following'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 Infonnation",

dated January 18, 1978.

QTP 300-S32 e~,

I Rovision 1

. .- ! QUAD-CITIES REFUELING March 1978 b, ,

I INFORMATION REQUEST u~ 1. Unit: 1 Reload: 6 Cycle: 7

" 2. Scheduled date for next refueling shutdown: Sept 12, 1982 3 Scheduled date for restart following refueling: Dec 4, 1982

v-

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

P YES

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

{ . Information:

1. JULY 26, 1982 t*

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

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

,s b '

'ltiPLEl1ENTATION OF TH'E ODYN TRANSIENT ANALYSIS CODE AND RESULTS (fiCPR SCRAM TiltE DEPENDENCE)

I r-t n.

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7 The number of fuel assemblies.

!' a. Number of assemblies in core: 224 new/724 total 8- after the

b. Numbcr of assemblies in spent fuel pool: outage 1940 v.

~ 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 refuel;ng that can be discharged to the spent fuel pool assuming the present licensed capacity:

v LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/04 LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 A'PPROVED APR 2 01978

. Q. C. o. S. R.

, QTP 300-532

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' Revision 1

. QUAD-CITIES REFUELINr, March 1978 I

I,;j , INFORMATION REQUEST r,

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.s 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 -

r-

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

IF NO u

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

. Informa tion:

{

L NONE r*

j~ 6. Important IIcensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis 7, / methods, significant changes in fuel design, new operating procedures:

G b - NONE ie i l

n I

a.

7 The number of fuel assemblies.

[' a. Number of assemblies in core:

af ter the 192 new/724 total L.

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

L, 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 1

in number of fuel assemblies:

b* 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 licensed capacity:

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84 WPPROVED LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2.01978

., C).c:.c).55.FR.

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