ML20116J930

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Monthly Operating Repts for Oct 1992 for Lasalle County Nuclear Power Station,Units 1 & 2
ML20116J930
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 10/31/1992
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9211160457
Download: ML20116J930 (25)
v • d • e


Text

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5- Commonwe:lth Edison LaSalle County Nuclear Station 2601 N. 21st. Rd.

Marseilles, Illinois 61341 Telephone 815/357 6761 November 9, 1992 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station Pl-137 Hashington, D.C. 20555 ATIN: Document Control Desk i

Gentlemen: 1 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for October 1992.

Very truly yours,

( ffh b G. J. Diederich b.

Station Manager LaSalle County Station GJD/HJC/djf

-Enclosure xc: A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center D. R. Eggett, NED P. D. Doverspike, GE Resident T. J. Kovach, Manager of Nuclear Licensing T. A. Rieck, Nuclear Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor H. P. Pietryga, QA/NS Off Site Review Station File 160091 o .

I 9211160457 921031 i i I ZCADTS/5 PDR ADOCK 05000373 l I 1 R PDR ), N -] g _ ~j

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LaSALLE NUCLEAR POWER STATION UNIT 1 HONTHLY PERFORRANCE REPORT OCTOBER 1992 CO M

  • HEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. FT-11 ZCADTS/5

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i TABLE OF CONTENTS-

-(UNIT 1)

I. INTRODUCTION R

II. REPORT A. SUW4ARY OF OPERATIWG EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL-SPECIFICATIONS C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS 3

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit-Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS
1. Main Steam Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major. Changes to Radioactive Maste Treatment System
5. Indications of Failed Fuel Elements f

e ZCADTS/5

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4 I. INTRODUCTION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Comonwealth Edison Company and located near Marsellies, Illinois. Each unit is a Boiling Hater Reactor with a designed net e'ictrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Comonwealth Edison Company.

Unit One was issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761, extension 2427.

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. II.' MONTHLY REPORT.;

- A. - SlM ERY OF OPERATING EXPERIENCE-_(Unit
1)' .;

~

1

-Q3y. Ileg - Event 1- - 0000 Reactor critical,= Generator on-line at 800 Hve.- "

(Unit-in coastdown). .

0050. Reduced power level to 750 Mwe due tol system load, f 0420 Increased power level to 800 Mwe.

2 1000 Reducing power at 150 Mwe per hour for upcoming- l refuel outage.

1200 Downshifted Reactor Recirculation pumps, power. level '

at 370 Mwe.

2000 Power level at 163 Mwe.

2206 Power level at 80 Mwe. ,

3 0031 Generator offline, refueling outage (LIR05) began.

0645 Reactor subtritical.

31 2400- Reactor subcritical, Generator offline, refuel outage (L1R05) in progress. '

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. .. . -. - - =

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B .~ : AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION.

(None.)=

C. ~ MAJOR CORRECTIVE MAINTENANrE TO SAFETY-RELATED- EQUIPMENTE(including; SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE, EVENT REPORTS (Unit 1)

LER Number Dite Description 92-010-00 10/09/92 During performance l of -a Division . I' Alternate Rod- Insertion relay logic test,=  ;

with the at,Je switch in - refuel', _ an inadvertant scram was - received on -low charging water pressure.

92-011-00 10/15/92 Technical- Specifica lion requirements for '

the posting and t 7 trol of a High-High; radiation area were not maintained.

E. DATA TABULATIONS (Unit 1)

1. Operating Data Report (See Table 2) '
2. Average Daily Unit Power Level (See Table 3)
3. Unit Shutdowns and Significant Power Reductions-(See Table 4) w k

ZCADTS/5

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C. TABLE 1 (Unit 1)

MAJOR CORRECTIVE MAT *4TENANCE TO I SAFETY-RELATED LWITHENT HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF HALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L16097 Switchgear 136X X-Relay. None. Replace X-relay.

IAP21E L16210 'A' Diesel Generator Transformer 74 relay. Soakback pump will not continue Replace transformer Soakback Pump AC to run. and 74 relay.

L18121 Source Range honitor Pre-reg >1ator. Setpoints erratic excessive Replace pre-regulator.

'B' relay chatter.

L18125 Average Power Range Power supply and fuse. Erratic readings. Replaced 2CV power supply Honitor APRH 'B' and fuse.

L18148 Intermediate Range Inoperable inhibit switch. Monitor failed downscale. Replaced inhibit switch.

Monitor IRH 'A' L18266 Main Steam Line Rad FEH to anuneter card. None. Replace assneter card.

Monitor 1D18-K6100 (No SOR Failures this month.)

.ZCADTS/5+

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-TADLE -

.E.1-OPERATING DATA: REPORT-

" DOCKET NO.LO50-373.-

UNIT LASALLE ONE- -

DATE November 9, 1992 CQlPLETED BY.M.J.CIALKOWSKI:

OPERATING STATUS- . TELEPHONE ( 815) . 357- 67 61 -

l '. REPORTING PERIODS October 1992- ,

GPOSS HOURS IN REPORTING PERIOD: -745 72'. - - CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323.

MAX DEPENDADLE CAPACITY 'MWe. Net): 1,036 DESIGN ELECTRICAL RATING (MWe. Net): 1,078

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A

,4. REASON FOR RESTRICTION (IF ANY):  ;

THIS MONTH YEAR TO DATE CUMUUTIVE  :

. ... ... . .. . ... .. ......v..s.. J

-5. REACTOR CRIIICAL TIME (HOURS) .54<8 6,568.3 53,924.8-0.0 0.0 1,641.2 64 l REACTOR RESERVE SHUTDOWN TIME (HOURS) 7 GENERATOR ON.LINE TIME (HOURS) 48.5 6.529.3 52,907.6 B.. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0

9. THERMAL ENERGY GENERATED (MWHt) 94,066- 19,903,179 '155,060,158 10.' ELECTRICAL ENERGY GENERATED (MWHe. Gross) 30,784 6,702,577- 151,792,349 7
11. ELECTRICAL ENERGY GENERATED (MWHe. Net) 21,520 6,469,278 49,664,423-112. REACTOR SERVICE FACTOR (%) 7.4 89.7 69.6=
13. REACTOR AV;.ILABILITY FACTOR (%) 7.4 89.7 71.7;

-14. UNIT SERVICE FACTOR (%)

-6.5 89.2 G8.3: ci 15i UNIT AVAII!BILITY FAC1]R. (%) ~ 6.5: 89.2 68/3.

T16.- UNIT CAPACITY FACTOR (USING MDC) (%) 2 . 8 -- 85.3- 61.9'-

~17.' UNIT CAPACITY FACTOR (USING DESIGN MWe) 2.7 82.0: 59.5 f18._ UNIT PORCED OUTAGE FACTOR.(%)- 0.0- 1.4 '6.9

-19. ' SHUTDOWNS SCHEDULED OVER THE. NEXT 6 MONTHS (TYPE,- DATE, AND DURATION OF EACH):

h-

20. --I? GHUTDOWN AT END OF REPORT PERIOD, ESTIMATED:DhTE-OF STARIUP:-

-, ,m - . . . . . m . ,e ~. , . - ,

b.T . -

fr .. TABLE-3 ~'

,90Y I$2 - AVERAGE DAILY UNIT-POWER LEVEL (MWe-Not) .

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DOCKET NO. 050-373. .;

jf UNIT LASALLE ONE:

?  : DATE November :-9,_--- 1992 l-;

COMPLE7ED BY M.J. CIALKOWSKI- ,

I .TELEPilON E ' ( 815 )-3 07 -67 61 t

REPORT PERIOD October 1992 'l DAY POWER DAY POWER 'i 1 769 17 -12 +

2 455 18 -11 -

_ 3 -11 19 -11 4 -12 20 .11

~

5 -12 21 -11 T

6 -12 22 -11 7 -12 23 -11 8 -12 24 -11 9 -11 25 -11 10 -11 26 -11' 31 -12 _27, -11' 12L -11 28 -11'-

13 -11 129- -11

.14 -11 30 '-11 l-l 15 -11 31- -11 l.

[ 16 -12 c.

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TABLE 4 E.3 UNIT SHUTD0HNS AND P0HER REDUCTIONS > 207. -

(Unit 1) -

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOHN ACTIONS /COM4ENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if

. NUMBER (YYM4DD) S: SCHEDULED (HOURS) REASON REDUCING IV)MER applicable) 4 921003 S 696.5 C 1 Refuel outage (L1R05)

SIM4ARY OF OPERATION:

The unit entered a scheduled refueling outage on 10/03/92. Scheduled return to service is 01/08/93.

ZCADTS/5 a ______m.m - .

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'4 F. UNIQUE REPORTING REQUIREMENTS.(Unit l1);

1. _ Safety / Relief valve operations

-(None.)

2. ECCS System Outages

.(See Table 5)

3. Changes _ to_-the Off-Site Dose Calculation Manual'

.(None.)_

4. Major changes to Radioactive Maste-Treatment Systems.

(None.)

5. Indications of Failed Fuel Elements.

(None.)

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j ZCADTS/5 1 x o

(Unit 1)

Table 5 ,

F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.

OUTAGE NO. EOUIPHERI PURPOSE 0653 1E22-S001 General diesel generator maintenance.

1061 1E22-F031 Install flushing spool for refuel outage.

1063 IE22-S001 Diesel generator and . manual injection stop valve relay- logic testing.

1083 1E22-SYSTEM Boundry out of service for high 1108 pressure core spray condensate 1126 suction piping modification.

1084 1E22-SYSTEM High pressure core spray boundry out of service for L1R05.

1109 1E22-F019 Administrative control.

1110 1E22-F038 Administrative control.

1209 1E12-F3310 Check valve inspections.

1E12-F331C 1253 IE12-F0688 Valve repack.

1259 1E22-S001 Battery replacement.

1260 1446 1A RHR System Operation of shutdown cooling mode.

1452 1B RHR System Operation of shutdown cooling mode.

1453 1E12-F063C Fill suppression pool.

1467 1489 1499 1E12-B0018 Administrative control.

1507 IE12-F087A Administrative control.

1511 1E12 -F068B Administrative control.

1520 1E12-F0928 Administrative control.

1E12-F0908 1E12-F092C l 1526 1E22-F003 Change limit switches, valve

repack.

L ZCADTS/5+

e-v LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT OCTOBER 1992 C06NONHEALTH EDISON COMPANY NRC DXKET NO. 050-374 LICENSE NO. NPF-18 l

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TABLE OF CONTENTS 4 (Uni t-- 2)

1. INTRODUCTION .

i II. REPORT I A. SUMARY OF OPERATING EXPERIENCE I B. AMENDMENTS TO FACILITY LICENSE OR TEDINICAL SPECIFICATIONS -

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT-D. LICENSEE EVENT REPORTS E. DATA TABULATIONS  ;

1. Operating Data-Report ~

1-2.- Average Daily Unit Power Leve.

3. Unit Shutdowns and-Power Reductions F. UNIQUE-REPORTING REQUIREMENTS
1. Safety / Relief Valve Operations
2. ECCS System Outages 3.- Off-Site Dose Calculation Manual Changes _
4. Major Changes to-Radioactive Maste Treatment System '
5. Indications of Failed Fuel _ Elements ZCADTS/7 - ,

A I. INTRODUCTION (Unit 2)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, I:11nois. Each unit is a Bolling Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Couonwealth Edison Company.

Unit Two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on Match 10, 198* and commercial power operation was commenced on October 19, 1984.

This report was compiled by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.

ZeADTS/7

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II. MC*iTHLY REPORT

A.- SlMMRY- 2F OPERATING EXPERIENCE (Unit 2)' .

Day _ Iljhg _ Event' React'or critical, Generator on-line at-1110 Mwe.-

~

1 0000 T

0030 Reduced power level to 945 Mwe due to system load.:

1000 Increased power leve. +01120 Mwa.

2 0300 Reduced power level to 1000 Mwe-due to system load.

0800 Increased power level to 1120 Mwe.

4 0230 Reduced power level to 1000 Mwe due to system . load.

1200 Increased p3wer leval to 1120 Mwe.

2330 Reduced power level to 845 Mwe due to system load.

5 1000 Increased power level to 1120 Mwe.

6 0030 Reduced power level to 850 Mwe due to systein load. -!

0900 Increased power level to 1120 Mwe.

2330 Reduced power level to 810 Mwe due to system load.

7 5200 Increased powe- level to 1125 Mwe.

9 0230 Reduced power level to 995 Mwe due to system load.

Increased power leve' to 1130 Mwe.

1000 10 0300 Reduced power level to 990 Mwe due to system ioad.

1000 Increased power -level _to 1130_'Mwe.

11 0130 Reduced power level to 850 be due to-system load.-

12 1800 . Increased power level ta'1130 Mwe.

13 0000 Rrv . ' nower level to 1000 Mwe due to system load.

1000 Ihaeased power level to'1130 Mwe.

14- 0100 Reduced power _ level to 840 Mwe due.to system load.

L L 1000 -Increased power level to 1130 Mwe.

15 1700 . Reduced power level to 880 Mwe, placed theI'B'- .

Turbine Driven Reactor Feed Pump out of' service

~ ~

, for maintenance.-

L 16- 0600 Increased power level to'1026 Mwe.

l L ZCADTS/7 ,

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II. MONTHLY REPORT 1

. A.

  • SU M ARY OF OPERATING EXPERIENCE (Unit 2) (CONTINUED)

QAy llM Event 1700 Reduced power level to 900 Mwe for maintenance on the l

'B' Turbine Driven Reactor feed Pump.  !

i 17 0600 Increased power level to 1020 Mwe. I 1100 Reduced power level to 900 Mwe due to system load.

2200 Increased power level to 1130 he. l 21 0300 Reduced power level to 1000 Mwe due to system load.

1000 Increased power level to 1135 Mwe.

23 0130 Reduced power level to 990 Mwe due to systes load.

1150 Increased power level to 1130 Mwe.

24 0400 Reduced power level to 895 Mwe due to system load.

1100 Increased power level to 1130 Mwe..

25 0130 Reduced power level to 990 Mwe due to system load.

0430 Reduced power level to 890 Mwe due to system load.

1100 Increased power level to 1130 Mwe.

2P30 Reduced power level to 1000 Mwe due to system load.

26 0130 Reduced power level to 850 Mwe due to system load.

1000 Increased powe, level to 1130 Mwe.-

27 0200 Reduced power level to 1060 Mwe due to system load.

1000 Increased power level to 1130 Mwe..

30 0200 Reduced power level to 1000 Mwe due to-system load.

1100 Increased power level to 1130 Mwe.

1 31 0200 Reduced power level to 875 Mwe due to system load.

2400 Reactor critical,- Generator on-line at 1130 Mwe.-

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B. AMENDMENTS 10 THE FACILITY LICENSE OR TECHNICAL SPECIFICATION (None.) i C. MAJOR Q)RRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPflENT (including .

SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2)

LER.Mumtter DAtt Description 92-014-00 10/28/92 Improper performance of a local leak rate test of a primary containment isolation i valve (2G33-F040). i 92-015-00 10/29/92 Isolation of the Reactor Water Cleanup system due to a high differential- flow signal.  ;

E. DATA TABULATIONS (Unit 2) l 3

1. Operating Data Report.  ;

(See Table 2)

2. Average Daily Unit Power Level. ,

(See Table 3)

3. Unit Shutdowns and Significant Power Reductions.

(See Table 4) i

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C. - TABLE 1 (Unit 2)

MAJOR CORRECTIVE MAINTENANCE TO

, SAFETY-RELATED EQUIPMENT NORK REQUEST RESULTS AND EFFECTS ,

IRAGER COMPONENT- CAUSE OF MALFUNCTION ON SAFE PUutT OPERATION C9RRECTIVE ACTION l .L18379' Low Pressure Core SOR outside its reject Redundant systems available. Install new switch.

Spray Min-Flow Static- limit..

~

.O-Ring Switch.(SOR)

, -(See'

attached SOR failure report.)

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SQRJip_Sif1TflLfMWREJATAlllEET Equipment Piece Nu.ber 2121-HQQi__ Model Number: 101:AS:1202:NX MIIKQ Serial Numbert JL9-2 -3 87 7 App 11eation: Minimunt.Ilow_ByPAEllillRrtatinL EltaEMLg_Swltch >

Date and Time of Disc,very: 10/13/02 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> Reactor Mode: LCRuni Power Levels 10m .

Calibration Tolerance s _1L.Q _22.tl "WC 1 Hominal Setpoint 2L.D "WC Action Limits: < _21t3 or >_2L 1 "WC Reject Limits: < _2L.4 or >_2514 "WC Technical Specitication Limits: 1 1 12 "WC ,

As Found Setpoint .l5t5 "WC Date and Time of Return to Service AQLlDZ22 153Q hours Model Number of Replacement Switch 101 AS B292:HK:J1TTXQ Serial Number of Replacemant Switch: 22-5-7812 DVR Number: 1-2-92-074 Cause s Switch _wan lound_o.nt_qLcalibratien._Apparnat_cAuse_.ia_unkanwn.

Alh019 ngh_1 nYS atig ation_1 E_in_plo9 LB114 Corrective Action: Zhe switch yng_rgplaced.

. _ . , . _. . .__ ._m...- _ _ _ _ _ . _ . _ . _ . - . . _ _ _ . .. _ . . _ . _ , _ . . _ _ . _.. __ .

. 1 a TABLE 2 '

l E.1 OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LASALLE TWO  !

DATE November 9, .1992 ,

COMPLETED BY M.J.CIALKOWSKI  ;

OPERATING STA'11]S TELEPMIE (815) 357-6761  :

s I. REPORTING PERIOD: October 1992 t

- GROSS llOURS Ill. REPORTIllG PERIOD: 745

2. CURRENTLY AUTilORIZED POWER. LEVEL (MWt): 3,323 MAX DEPENDADLE CAPACITY (MWe-Net): 1,036 1 DESIGN ELECTRICAL RATING (MWe. Net): 1,078 f

-3. POWER LEVEL TO WHICil RESTRICTED (IT ANY) (MWe-Not)t li/A i

4 REASOff FOR RESTRICTION (IF ANY):

THIS MO!!TH YEAR TO DATE CUMULATIVE

b. REACTOR CRITICAL TIME (llOURS) 745.0 4,641.1 49,576.9
6. REACTOR RESERVE S!!UTDOWN TIME (HOURS) 0.0 0.0 1,716.9
7. GENERATOR ON-LINE TIME (llOURS) 745.0 4,454.8 48,659.4
8.

UNIT RESERVE SHUTDOWN TIME (llOURS) 0.0 0.0 0.0

9. TllEltMAL ENERGY GENERATED (MWilt) 2,362,500 13,343,630 145',500,029
10. ELECTRICAL ENERGY GENERATED (MWHe. Gross) 800,492 4,505,298 48.395,048_-

s II. ELECTRICAL ENERGY GENERATED (MWHe-Net) 776,892 4,317,398 46,448,902 i I

12. REACTOR SERVICE FACTOR (%) 100.0 63.4 -70.4
13. REACTOR AVAILABILITY FACTOR (%)

100.0 _63.4 72.8 i

69.1-

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14.' UNIT SERVICE FACTOR (%)

100.0 60.97 r

15. UNIT AVAILIDILITY TACTOR- (%) -100.0 .60,9 69.1 ,

l'6. UNIT CAPACITY TACTOR (USING MDc) _ (%) 100.7 56.9 :63.6; 17.-UNIT. CAPACITY FACTOR (USING DESIGN MWe) 96.7 .54.7 '61.1 +

M .-UNIT FORCED OUTAGE FACTOR (%) 10.0: '9.6'. 12.8.

19. ' S!!UTDOWNS SCIIEDULED OVER THE NEXT 6 = MONTHS (TYPE, DATE, AND DURATION OF~EACH): ,

.i F 20./ IF S!!UTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: . N'/ A-R ,

'Y-Th*-*vW-1t a Av,*.e+ vees ='t d W w a'W *N P'1er-v y,w # yr Ym -'=W't+y '=y- 7 g *? "T +P'i *-"'*'-"

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TADLE 3

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"Ef/k. E.2, AVERACE DAILY UtdIT POWER LEVEL (HWe.Ilet ) j '

DOCKET 110.-050-373

UtlIT LASALLE 'lHO

, DATE 11ovember-9,' 1992 COMPLETED DY M.J. CIALKOWSK!

TELEPliotit (815)-357 6761 .i I

1 l

j REPORT PERIOD: October 1992 )

i.? v POPER DAY POWER

.. ... .. ...... . .--...... . ..-~.--- ,

-l 1 1,033 17 980  ;

2 1,002 18 1,096 3 1,073 19 1,098 4 1,027 20 1,090 5 1,008 21 1,002 6 1,006 22 1,090 7 1,004 23 1,004 0 1,092 24 1,058 9 1,074 25 1,079 10 1,077 26 1,043 11 833 27 1,084 12 1,010 28 1,097 13 1,059 29 1,068 i- 14 -1,041 10 1,066 l-15 1,018 31 1,028 16- 923 H

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rM' TABLE 4. -

. E.3 - UNIT SHUTDOWNS AND POWER REDUCTIONS >20%

(UNIT 2)

  • b l

CoRREcrIvE METBoD or YEARLY: TYPE SHUTTING DOWN ACTIOWS/C0000ENTS SEQUENTIAL DATE' F: FORCED DURATION THE REACTOR OR (LER/DTE # if EtBIBER (YDeeD) S: SCHEDULED (HOURS) REASON REDUCIWG PONG apolicable) i 8 921011 r 0.0 H 4 Power reduction due to systein.

load.

1 4

. ., a SuseurY OF OPERATION: '

The unit remained on line 'at high power throughout the month. . Several minor power reductions were required due'to system load and maintenance activities.

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i l-k ZCADTS/7-

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

. F. UNIQUE REPORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Operations (None.)
2. ECCS System Outages (See Table 5.) i i
3. Changes to the Off-Site Dose Calculation Manual.

(None.)

4. MajorchangestoRadioactiveWasteTreatmentSystems.

(None.)

5. Inoications of failed fuel Elements.

(None.)

ZCADTS/7

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(Unit 2)

Table 5 f.2 ECCS Systes Outages-Note: The year and unit data has been removed from the cutage number.

DUTAGE NO.- [ QUIET![KI PURPOSE 2133 2DG08C8 Control switch replacement.

2161 2E21-C001 Administrative control.

2168 2DG01K Lubrication.

2179 2E22-5001 Lubrication and inspection.

2180 ZCADTS/7

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