ML20246B037

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jul 1989 for LaSalle County Nuclear Power Station
ML20246B037
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 07/31/1989
From: Diederich G, Thunstedt J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 8908230225
Download: ML20246B037 (24)
v • d • e


Text

~

E'O,;.n Ls- .

V .y :.,

g*E,

) ..,,,,L4 - ..

v~r -

M~ ,jr; c 'Ng . CommonweaMh' Edison <

m 9e '. ? s..!/sf F. bSallaCountyNuclearStation

' ;! *' 1 Rur:I Routa #1, Box 220

, ,-( .-. "' Marseilles, Illinois 61341 L g'

c . ..

Telephone 815/357-6761 August 7, 1989 L

j.'[ ..

Director of. Nuclear Reactor Regulation

"

  • United States Nuclear Regulatory Commission.

Mail Station P1-137 l

o.,

Washington, D'.C. 20555 N:

'ATTH: . Document Control Desk Gentlemen:

Enclosed for your.information is the monthly performance report covering LaSalle. County Nuclear Power Station for July, 1989.

x I (

Very truly yours, V

G.'J. Diederich hrStationManager LaSalle County Station tthl%

JP JWT/jdp:

F

. Enclosure ac t . A. B. Davis, NRC, Region III NRC' Reside'nt. Inspector LaSalle Ill. Dept. " of Nuclear Safety P..Shemansks., NRR Project Manager

-D. P.'Galle, CECO l D. L. Farrar, CECO-INPO Records Center L. 'J. Anastasia, AIP ' Coordinator, Nuclear Services J. E. Kuskey,;GE Resident. ,

T. J. Kovach, Manager of Nuclear Licensing j W. F. Naughton, Nuclear Fuel Services Manager ,j C. F. Dillon, Senior Financial Coordinator, LaSalle {

.  ? Terry Novotney,> INFO Coordinator, LaSalle Station j T. A.' Hammerich, Regulatory Assurance Supervisor J..W. Gieseker, Technical Staff Supervisor Centrol File j i

890823o225 39o733

{DR ADOCK 05000373

~ZCADTS1 ((2.,

L

'lI

m, . . _ - . _ - - _

, *' . :?'

'+ ,.. . -

LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY' PERFORMANCE REPORT JULY 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll ZCADTS l.

b_

. :'-

  • T.

"ABLE OF CONTENTS I. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CilANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications
2. Changes to procedures which are described in the Safety Analysis Report
3. Tests and Experiments not covered in the Safety Analysis Report
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety-Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions E. 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 Waste Treatment System
5. Indications of Failed Fuel Elements ZCADTS

.=m_____..._.__ _ _ _ i

- 1 1

1. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Bolling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste 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 cont'ractor was  ;

Commonwealth-Edison Company.

Unit One was issued operating Ilcense number NTF-11 on April 17, 1982.

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

This report was compiled by John W. Thunstedt, telephone number (815)357-6761, extension 2463.

.ZCADTS j o _ - _ _ . _ _ _ _ _ _ _ _ _ _ .

~ ~ ~

FTI.-

T

'II. MONTHLY REPORT l.-

A. '

SUMMARY

CT OPERATING EXPERIENCE pny Ilmg Event 1 000C Reactor critical, generator on-line, full power (Note Almost daily, power reductions were performed due to system load conditions or to improve main condenser vacuum which resulted from high cooling lake temperature; these reductions greater than 20% are reported in Section II.D.3. The following items summarize other conditions).

6 0000 Reduced power to 2884 NWT for TIP set.

7 1200 Returned to full power.

14 0300 Reduced power to 2983 MWT due to a blown diaphram on rod 26.39 drive system.

1200 Returned to full power.

! 15 0200 Reduced load to 2080 MWT due to scram-time testing and rod pattern adjustment.

2000 Returned to full power.

17 1400 Reduced load to 2601 MWT due to hydrogen leak on main generator.

18 1100 Returned to full power.

19 0000 Reduced load to 3130 MWT for CRD exercising.

28 0500 Reduced load to 3200 MWT due to Xenon transient.

31 0300 Reduced load to 2580 MWT due to hydrogen venting.

1300 Returned to full power.

2400 Reactor critical, generator on-line, full power.

ZCADTS

_u.______ _ _ _ _ l

J~

,1<-

. L B '. . [ PLANT [OR' PROCEDURE CHANGES, TESTS, EXPERIMENTS AND-SAFETY RELATED. I q...

-j -4 -

. MAINTENANCE.

', 2 ~

1. Amendments to'the Facility License or Technical Specification.

h 1

] a.  : Suppression Pool Temperature Limit Change to.105 degrees-F.

~. b . . . Amend Tech Spec's so that: the' 3.25 surveillance extension

~

-does not apply to refuel outage interval' surveillance.

i

t. ci ~MAPLHGR limit curve revisions.

\ ~_

2. .

Changes to procedures which are described in the Safety Analysis Report.

I (None),

l

3. Tests and~ Experiments not described in the Safety Analysis Report.

-(None)

4. Major corrective maintenance to Safety-Related Equipment.

(None)

5. Completed Safety-Related Modifications.

.(See Table 1)

' ZCADTS - I L_=___ -_ __ ._ _ - _ _

'h y

~

.B.5 TABLE 1 COMPLETED SAFETY-RELATED MODIFICATIONS MODIFICATION NUMBER DESCRIPTION ,

M01.1'-8 8-015 ' Human Factors to implement corrective action in response to HED 343. The Off Gas system holdup line drain valves were incorrect as it shows them in series, when they are actually in parallel.

,r ZCADTS

g _. . _ _ _ . . _ _

.- , .. ., 0,1

'# .. - ~

C. - LICENSEE EVENT REPORTS -

1

.e

(;

I' LER Number Rate Description None D. DATA TABULATIONS

1. Operating Data Report (attached)
2. Average Daily Unit Power Level (attached)
3. Unit Shutdowns and Power Reductions (attached)

.I t

l I.

ZCADTS j

m__ 4

w.c , .,.

W ', , ,

4

. D.i DPERATING DATA REPORT DOCKET NO. 950-373 UNIT LASALLE ONE DATE August 10,1989 COMPLETED BY J.W. THUNSTEDT TELEPHONE (B15)-357-6761 OPC'ATING' R STATUS

1. REPORTING PERIDD:

. JULY 1989. GROSS HOURS IN REPORTING PERIOD: 744

E.CURRENTLYAUTH0P,1ZEDPOWERLEVEL(MWt): 3,323 . MAX DEPEND CAPACITY (MWe-Net): 't,036 DESIGN ELECTPICAL RATING (MWe-Net). 1,078 -

3c: POWER LEVEL TO WHICH RESTKICTED (If ANY) (MWe-Net): (None) 4.: REASONS TCR RESTRICTION (IF ANY): (N/A)

REPORTING PERIOD DATA THIS HONTJ YEAR-TD-DATE CUMULATIVE

5. TIGE REACTOR CRITICAL'(HOURS!

744.0 5,013.3 31,032.6

~ 6. TICE REACTOR RESERVE SHUTDOWN (HOURS). 0.0 0.0 1,641.2

!7. TIGE GENERATOR DN-LINE (H0dRS) 744.0 5,003.1 '30,317.6

8. ' TIME GENERATOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 1.0
9. THERMAL ENERGY GENERATED (MWHt-Gross) 2,271,504 15,693,742 B4,472,320
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 745,C24 5,306,933 27,952,687'
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) '718,208 5,114,673 26,690,202
12. REACTOR SERVICE FACTOR (%) 100.0 98.6 63.4

.13. REACIDR AVAILABILITY FACTOR (%) 100.0 98.6 66.8

14. SERVICE FACTOR (%) . 100.0 98.4 62.0 i
15. MAILABILITY FACTDR (%)- . 100.0 98.4 62.0

'16.CAPACITYFACTOR(USINGMDC)(Is 93.2 97.1 52.6

17. CAPACITY FACTOR (USING DESIGN MWe) (%) 89.5 93.3 50.6
18. FORCED DUTAGE FACTOR (1) 0.0 1.6 10.5

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

l l Refueling 9-16-89 12 Weeks 1 L 20.-IF SHUTDOWN AT END DF REPORT FERIOD, ESTIMATED DATE OF STARTUP:

l (N/A)

L 4

pl-( i

_1__.___.___________..____..._ _ _ . _ _ _ _ . _ _ _ _ _ _ _ __ . . _ . _ _ . _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ .

.. e i , I *;

f I k . 6, I* -.

~' ' '

DOCKET NO. 950-373 UNIT LASALLE ONE D.2 . AVERAGE' DAILY UNIT POWER LEVEL OtWe-Net) DATE August 10,1989 as C0liPLETED BY J.W. THUNSTEDT TELEPHONE (815)-357-6761 s ,

1 k REPORIPERIDD: JULY 1989

. DAY: POWER- IAY . POWER-

D
1. . 984 17 - 866 ,

2 1,005 .18 . 991

'3. 961 19 1,044 4' 941 20 1,025

'5 942 -21 1,007 6- 299 22 i,634 7 931 23 974 8 940 24 1,010

9. 974 25 930 10 - 999 26 - 965 11 - 990 ' 27 1,022 12 962- 28 - 1,027

_13 956 29 872 14 - 1,010 '. 30 896

-15 820 31 996 16 954

.3 l

l '..

p 1

h L

c. . _ _ -_ _ _-__ _ -__ --- __ _ _

5 S7 1 T r r r r t r r r r r r 0 a . Y8 N e e e e s e e e e e e e e

- LtB( E h h h h e h h h h h h h h

. s - M c c c c t c c c c c c c c OE uDE M t t t t t t t t t t t t NM GEN EO a a a a e a a a a a a a a A uTO VC p p p p m p p p p p p p p TNAEH I / s s s s i s s s s s s s s E LP TS i i i i t i i i i i i i i KTEPE CN D D D D - D D D D D D D D CI TML EO m ONAOE RI d d d d a d d d d d d d d DUDCT RT a a a a r a a a a a a a a OC o o o o c o o o o o o o o CA L L L L S L L L L L L L .

L

% RR 0 NOE 2 W W FORO

> ODOP T

S DGCG N ONAN S S S S S S S S S S S S S O HI EI I TTRC T ET U C 9 MUED U 8 HHE D 9 STR E 1 R

R Y E L W U O J P N

O D H S N T A F F F F B F F F F F F F F A N E O R S M N

W T O R D O T P U E H R S N O)

T I S I TR 0 0 0 0 0 0 0 0 0 0 0 0 0 N AU U RO 0 0 0 0 0 0 0 0 0 0 0 0 0 UH D(

3 D

D E

L DU ED CE ERH POC YFS T : :

FS S S 5 S S 5 5 S 5 S S S S E

T A 1 3 4 3 5 5 6 7 1 3 5 9 1 D 1 1 1 1 1 2 2 2 2 3 L

A I

T YNR LEE RUB 2 3 4 5 6 7 8 9 0 1 2 3 4 AQM 2 2 2 2 2 2 2 2 3 3 3 3 3 EEU YSN I

4

_j E." UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief _ valve operations k

VALVES NO & TYPE PLANT DESCRIPTION i

. DATE , AC211ATED .ACTUATIQH CONDITION OF EVENT (None) ,

(

1

2. ECCS System Outages l QQTAGER EOUIPMEllI PURPOSE

.lUnit_Q) 0-205-89 ODG01P Lubricate Coupling

- 1ENIT 1) 1-406-89 1B D/G Replace 1E22-F377A 1-407-89 1B D/G Replace PS-1E22-N514 1-408-89 HPCS Water-leg Pump Lubricate Coupling 1-411-89 1B D/G Motor-driven Replace head-gasket Air-Compressor 1-413-89 1E12-F312A Inspect torque switch (RH) 1-427-89 1E51-C004 Inspect motor (RI) 1-428-89 1E51-C005 Inspect motor (RI) 1-429-89 1E51-F008 Replace 1E51-F008 (RI) 1-430-89 RCIC Lubrication 1-431-89 RCIC Lubricate coupling ZCADTS I

'C

  • ~ '

QU'[hGE NO. EOUIPMENT PJlRPOSE 1.

l- UNIT 1 (CONTINUED) 1 1-434-89 1E22-F342 (Administrative)

(HP) 1-437-89 1E22-C302A Repair head gasket (1B D/G "A" l air compressor) .I I

'1-439-89 1E22-C302A Repair head gasket and relief valve (IB D/G "A" air compressor) 1-460-89 1E12-F052B Perform EQ inspection (RH) 1-461-89 IE12-r052B Repair Limitorque operator (Ell i 1-463-89 1E12-F047B Remove support (RH) 1-465-89 1E12-C003 Lubrication (RH) 1-466-89 1E12-C003 Replace oil (RH) 1-47'.-89 1A RHR Service Perform EQ inspection Water Pump

3. Off-Site Dose Calculation Manual (None)
4. Major changes to Radioactive Waste Treatment Systems.

(Hone)

5. Indications of Failed Fuel Elements.

(Hone)

)

ZCADTS I

,: +: .

fs .

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT JULY, 1989 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS

TABLE OF CONTENTS l

i

1. INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications
2. Changes to procedures which are described in the Safety Analysis Report.
3. Tests and Experiments not covered in the Safety Analysis Report.
4. Corrective Maintenance of Safety-Related Equipment
5. Completed Safety Related Modifications C. LICENSEE EVENT REPORTS D. DATA TABULATIONS
1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
1. Safety / Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System
5. Indications of Failed Fuel Elements l

T ZCADTS7 I-f-

  • 'e I INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. . Waste 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 Commonwealth Edison Company.

Unit Two was issued operating license number NPT-18 on December 16, 1983. Initial cr3ticality was achieved on March 10, 1984~and commercial  !

power operation was commenced on June 19, 1984.

This report was compiled by John W. Thunstedt, telephone number (815)357-6761 extension 2463.

l l

l l

l l

ZCADTS7

N' Ni *I '

II. MONTHLY REPORT A,

SUMMARY

OF OPERATING EXPERIENCE

. DAY ILWE EXRpt 1 0000 Reactor critical, generator on-line, 2854 MWT due to System load conditions.

(Note: Almost daily, power reductions were performed due to system load conditions or to improve main condenser vacuum which resultad from high cooling lake temperature; these reductions greater than 20% are reported in Section II.D.3. The following items summarize other conditions).

3 0900 Returned to full power.

6 0400 Reduced load to 2648 MWT for rod-set.

1200 Returned to full power.

13 0100 Reduced load to 2930 MWT for CRD exercising.

1200 Returned to full power.

20 0300 Reduced load to 2773 MWT to adjust rod-line.

1300 Returned to full power.

21 0900 Reduced loed to 3141 MWT due to test on "A" Reactor Feed Water Pump.

1300 Returned to full power.

23 1900 Reduced load to 2572 MWT due to repairs on "B" Reactor Feed Water Fump.

25 0100 Reduced load to 1766 MWT for Deep Shallow.

27 0600 Returned to full power.

2200 Reduced load to 2888 MWT due to CRD exercising.

28 1100 Returned to full power.

31 2400 Reactor critical, generator on-line, full power.

ICADTS

d:i #

es! Eai a:

g Q A.S  ;- B. PLANT. OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

MAINTENANCE.-

hpll :.= :iFL f EO > ,  : 1~. -Amendments to the Facility License or Technical Specification.

?N a._ .. Suppression Pool Temperature Limit Change'to 105 degrees F.

,, . h ?

' b .~ Amend TechLSpec's'so that the 3.25 surveillance extension

- does not apply,to refuel outage interval surveillance.

g; ic. MAPLHGR limit curve revisions.

2. . _ChangesLto procedures which are described'in the Safety.

> Analysis" Report..

(None)~

. Tests and Experiments not' described in the Safety Analysis

?3.

, Report.

(None)

4. . Major. corrective maintenance'to Safety-Related Egulpment.

,, (See. Table ~1)

p
5. Completed Safety-Related Modifications.

(None) i

{s 3

(,

~ZCADTS a

,',d-_.

o e 3 n .

E r g a y

, F V t n s . a I n u R nt O l T o l C ir S e C c p F pa T r E p ,

R d d . d d - d s d R e ee e e r et e O c t g c ce t c c C a sa a at s a a l uk l l n ut l p jn p pu jn p e di e e o d o e R Al R R c A c R .

N O d SI i TT . d . .

CA e e e ER g s g g FE a t a t a FP t c t n t EO l a l a t l o t o l a o DT v n v o e v NN o o s O AA t c t c t T L u u t u SP p m p r o p E T T t a t o n t C LE u r , u t u NN UF o ce o c . d ,

o A E SA ss ay i y N M ES c o c et dl c E IP R i pl i ri r i 1 T U N t uc t v ee t O a k a hi vp a E N I Q r r

ct ao r

r gt l o ar r

r L A E E B n E i c H a V p E 3 M D A

T E E T V A I

T LE N 4 C R O E - I f n B R Y T d oi R r e O T C 3

E N a F s s g C F U o e gt a R A F b s n nc t O S L o i p

i a . l .

oy J A l o t t r A M o l t no V a r l eot l M F t m e s ca h e O n r R u r gr o a C f toe i E c S cS p H n S r g eT o w U d e d n r yo A e g e i r& e td C l n l k o v l t i u i a cCl uu a l a e nS a ah F P F L I T v F s

)

B 0 6 r 4 r 2 r e 1 e C0 e g K g I F g T r r C - I r N I a y I a e R2 I a E I h a I h l 1 I h N

O I C l e

I C d n

oE t 2 vy

.C P vy R vy u (

M i r i r B9 X i r O D e m D e 8 H e D e C t a t l 2 v t 2 t r 2 t eF Rl 2 t

- a c - a uY H a - a UB S UB FL RV UB T

S E

U Q

E

_ R R 6 4 5 1 6 8 E 7 3 0 1 5 5 KB 2 2 3 4 6 5 RM 1 1 1 9 8 8

1 9

_ OU 9 9 9 8 WN L L L L L L t ll l!

l

.g .;

C. . LICENSEE EVENT REPORTS LER Numb 1E DAtt. Description 89-010-00 07/15/89 HPCS Inoperable due to inoperable Division III battery charger D. DATA TABULATIONS

1. Operating Data Report (Attached)
2. Average Daily Unit Power Level (Attached) 3.. Unit Shutdowns and Power Reductions (Attached)

ZCADTS7

,y.. ,.

y, , ,, t.

/4 '

l' D.1 OPERATING DATA REPORT DOCEET NO. e50-374 Le-UNIT LASALLE TWO

- DATE August to,1989 COMPLETED BY J.W.THUNSTEDT.

TELEPHONE (B15)-357-6761 l ' L DPERATE:G STATUS l?

JULY 1989 GROSS HOURS IN REPDRTING PERIOD: 744

}:.1.'REPORTINGPERIOD:

l : 7, CURRENTLY AUTHORIZED POWER LEVEL (fiWt): 3,323 MAX. DEPEND CAPACITY (MWe-Net): 1,036 DESIrN ELECTRICAL RATING (Mee-Net) 1,078 l

. Y

' 3. ' POWER LEVEL TO WHICH PISTRICTED (If ANP (MWe-Net): (None)'

l

' 4. REASONS EUR RESTRICTION (IF ANY): (N/A).

REPORTING PERIOD DATA THIS MONTH YEAR-TD-DATE CUMULATIVE

,. 5.. TIGE REACTOR CRITICAL (HOURS) 744.0 4,173.1 27,651.1

. 6. TIME REAC TOR RESERVE SHUTDOWN (HOURS) 0.0 0.0 1,716.9

'l' 7.. TIME GENERATOR DN-LINE (HOURS) 744.0 4,121.5 27,212.5

~

8. TIME GENERATOR RESERVE SHUTDOWN -(HOURS). 0.0 0.0 0.0
9. I TRMAL ENERGY GENERATED (MWHt-Gross)' 2,327,736 12.582,744 78,522,352
10. ELECTRICAL ENERGY GENERATED (MWHe-Gross). 744,507 4,128,727 25,832,065 3
11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 716,429 3,979,424 24,718,674
12. REACTOR SERVICE FACTOR (%) 100.0 B2.0 66.0
13. REACTOR AVAILABILITY FACTOR (%) 100.0 E2.0 70.0 114. SERVICE FACTOR (!) 100.0 91.0 64.9 .

I 15.AVAIuBILITYFACTOR(%) 100.0 81.0 64.9

16. CAPACITY FACTOR (USING MDC) t%) 92.9 75.5 56.9 )

l

'17. CAPACITY FACTDR (USING DESIGN MWe) (%) 89.3 72.6 54.7 -

I

18. FDRCED OUTAGE FACTOR (%) 0.0 0.2 14.8
19. SHUTDDWNS SCHEDULED DVER TPE NEXT 6 MONTHS (TYPE, DATE, AND DURATION Of EACH):

(None)

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

(N/A)

, in :a . . . .

tp-a

~'

DOCKET NO. 050-374 UNIT LASALLE TWO D.2 AVERAGE DAILY UNIT POWER LEVEL (HWe-NeO DATE August 10, 1989 COMPLETED BY J.W. THUNSTEDT

' TELEPHONE (015)-357-6761 REPORT PERIODr JULY 1989

. DAY POWER DAY POWER

.i 877 17 972 2 . B99 iB - 984 l

3 '971 .19 994 4 959 29 1,006 5 951 21 1,040 1

6 918 22 1,039 1 ~' 7  ? 907 23 905 l-8 929 24 B91 L

.9 -947 25 805 10'- 974. 26 964-l:

11 . 973 - 27- 1,008 l.

l l-12 -973 '28 -992 l

13 955 29 1,002 L-14 979 30 1,600 J 15 975 31 1,065

- l

16 976 l '.

1 L

L .

L l 1 i l' l l

l, c_-

E a M M w.

M o t EO " l d VC B l e1 I / . " a TS h o

w9 n6 t6 s7 CN EO t

e s

'r i .

S T8 u - RI - ap p 4 9 h7 RT d pm e 7 e1T5 OC o e u e 3 l 3 CA R R P D

- l , .)

0 a0J5 5S1 1 0 a Y8

.LtB(s '

OE uDE NM GEN A uTO TNAEH RR E LP NOE KTEPE W W CI TML FORO ONAOE ODOP DUDCT T

% DGCG 0 0 NAN 2 1r I EI 5 S S

> TI RC ET U S MUED N HHE O STR I

T C 9 U 8 D 9 E 1 R

, E R Y D E L O W U C O J P N B B B O

D  : S N H A A T E R

S N N O W M O T D R T O U P H E S R N O)

T I S 0 0 0 I TR N AU 0 0 0 U RO UH D(

3 D

D E

L DU ED CE

_ E RH POC YF S T : :

FS S S S

_ E T

A 6 3 5 D 2 2 A

_ I

_ T YNR LEE RUB AQM 7 8 9 EEU 1 1 1 YSN

- l' l l

  • c L ., .

.*# +- E .

.'. . UNIQUE REPORTING REQUIREMENTS a . ,-

1. Safety / Relief Valve Operations VALVES NO & TIPE PLANT DESCRIPTION DATE ACTUATED ACIUAnORS CONDITION OF EVENT (None)
2. ECCS System Outages QQTAGE N L EOUIPMEET . PURPOSE 2-668-89 2DG01F Inspect cooling-water strainer.

2-681-89 2E51-C005 Inspect motor.

(RI) 2-682 '2E51-C004 Inspect motor.

(RI) 2-683-89 2E51-C002 Replace oil.

(RI) 2-694 2B D/G Calibrate 2E22-R533.

3. Off-Site Dose Calculation Manual (None)
4. Major changes to Radioactive Waste Treatment Systems.

(None)

5. Indications of Failed Fuel Elements.

(None) ,

l ZCADTS L_ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ . ____ _ _ _ - _ _ _ _ _ _ _ _ _ . -

Retrieved from "https://kanterella.com/w/index.php?title=ML20246B037&oldid=3165534"