ML20237A029

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Nov 1987
ML20237A029
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 11/30/1987
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0036R-0031R, 0043R-0031R, 36R-31R, 43R-31R, NUDOCS 8712140205
Download: ML20237A029 (31)
v • d • e


Text

- _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _

9 1

l 1

1 l

l l

1 LASALLE NUCLEAR POWER STATION l UNIT 1 i

MONTHLY PERFORMANCE REPORT NOVEMBER 1987 COMMONWEALTH EDISON COMPANY J NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll l l

l l

l l

8712140205 871130 PDR ADOCK 05000373 R DCD ggg DOCUMENT ID 0043r/0031r gj

/I 1

l

_ . _ . _ __. _ _ _ i

e

1. INTRODUCTION 4

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, i'

Unit one was issued operating license number NPP-ll on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power j operation was commenced on January 1, 1984. J This report was compiled by James P. Peters, telephone number (815)357-6761, extension 325.

4 ,

i 1

l l

IXX'UMENT ID 0043r/0031r

l

, TABLE OF CONTENTS s-

1. INTRODUCTION 1

II. MONTHLY REPORT FOR UNIT ONE l

l A. Summary of Operating Experience j

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

1. Amendments to Facility License or Technical Specifications j 2. Facility or Procedure Changes Requiring NRC Approval l 3. Tests and Experiments Requiring NRC Approval
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 l 5. Indications of Failed Fuel Elements DOCUMENT ID 0043r/0031r

i l

11. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE o

NOVEMBER l-30 j

November 1, 0001 hrs. The unit entered November with the Reactor I critical and on-line at 77% Power (850 MWe).

November 10, 2330 hrs. Commenced Reactor Power reduction to 49%

(550 MWe) for Control Rod manipulation.

November 11, 0210 hrs. Reactor Power decreased to 55% (620 MWe) for ,

Control Rod manipulation. 1 November 11, 0420 hrs. Completed Control Rod manipulations and started ramping up at 100 MWe/hr.

-\

November 13, 0001 hrs. Reactor Power increased to 92% (1030 MWe).

November 30, 2400 hrs. Reactor and Generator on line and holding at  !

90% (1005 MWe).

\

b DOCUMENT ID 0043r/0031r

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

1. Amendments to Facility License or Technical Specification.

4 There were no Facility License of Technical Specification changes during this reporting period.

2. Facility or Procedure changes requiring NRC approval.

There were no Facility or Procedural changes requiring NRC approval during this reporting period.

l

3. Tests and Experiments requiring NRC approval.

l l

There were no tests or experiments requiring NRC approval during '

l this reporting period.

l l 4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a Summary of l safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this summary include:

Work Request number, Component Name, cause of Malfunction, Results I and Effects on Safe Operation, and Corrective Action.

l S. Completed Safety Related Modifications.

( The following Table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.

t l

l l

l l

l l

l I

l DOCUMENT ID 0043r/0031r

pr r e nb ge n l np E eo h ou nn t n

o v

i n

eo pr V rt w c il i r m mp I a e n n su o r r e T d u n i id nt r e e p a C nt p pn ee f s t o dl E ac d a sr . l R a e . d d . d d d d s di R t l t e ed dd e e e e ee et O l r l i c ce enc c c c t h t C i e au a an h ai a . a a sc se up t c l l a s v l p pm l l ut uv b m sr p pe urr p p ji jl ea ni e el l i e ea e e d w d a Rd IC R R c Fas Rl R R A s Av o

g o n t N i n O d e s SI - n h d TT e .

e w a CA d e r o ER c t n n l FE s n o o n FP i a s i i . u EO . v i t t n y t d a . ae d DT e l h a n c p cp n NN t t r g o i m m i o a AA B a oe i t i s d o e d L Y r np l o t p no T nl s SP 2 e o n a i iR il d T 1 p d r w c r i u a FT LE H o l p o . s i t el H l f o ON UF V u l 1 d e d l o a l E SA O t oe f e o n s b r s us EM ES o wt z d i . u at u di r CP R rn a mi d o rn os e NI N e yv eg r l r i eo i m se l .

AU O ps ai t r e ea r pc rr wv l h NQ EE me ao l t ec se yn p

a vw ep u

p o

nn ua pl ol h a i c hu 1

T Dd R a S e P Lu S Ii SA S v Cm

_ E ND

_ L I E B AT

- A MA t T L u

_ EE N o

_ VR O s

_ I I c s TY T e i a CT C r n s t f w EE N o i e p p o

_ RF U t l n o i r RA F a . i r t e OS L u g r l l r t u b

- C A t n a e o s o m .

M c i e g n t at A s G n a o l h h n F n i p m a c .

ce O r e n s n t t m e y s o n t o i i n gt E p m

a i n

e s

n o

v r

m r

we sm ns i u S l d U a e e i r e e t nj A D R h P y f p

s t t s ed pa C c t i u d d n d r d m d d mj m

. a a i a i aa a a i d af B B P B D Bl B B L a D o B

5 7 6 r y 3 1 . e a

r 0 - d d t

_ l o M C n r e1 o

r e t pC aV I l 3 r e R c m- l i - c t 0 e

_ T p e eR v1 nY 2 e uF l N m AX t TT L0 oX H R O - l

_ 1 E a F4 eA I 0 mO 2 1 i

_ #N D I 4 D5 P kN m A1 .1 k4 h

_ O I 0 2 /r n- Ar C0 p0 nC C TP B CC a1 Se a1 o OM m6 aI A

_ I M Y VV i C d T4 Ct LC eR T PC NO 2 - nV I r C Vc - T - e V1 UC 1 " Y o- - o Cl e t R 2 Cv 0 E BS mY Vc L - t sI R1 Ll P

- V OF mX I e BT "B e oA HE B a "A

" I V

O " 0 AO DR SL " D Pl R1 Sv T

S E

U Q

- E R 9 3 8 8 8 5 5 0 5 1

_ 7 1 7 8 0 5 6 1 8 5

- K 2 1 1 1 2 2 2 3 3 5 R 5 6 3 3 3 3 3 3 3 3 O 5 5 7 7 7 7 7 7 7 7 V L L L L L L L L L L

- l

3I "\,' ,

s TABLE 2 '( '

COMPLETED SAFETY RELATED MODIFICATIONS -; .r .

, ~f

e. .I

\

MODIFICATION NUMBER: A brief synopsis of incorporated modification objectives '

'j with fjnal_d<eign resolution. Also, state reviewed or unreviewed safecy questions. ,

,. t, UNIT ONE ,

i There were no Safety Related modifications civnpleted'<,rJ,. Unit i for the period of November 1 to November 30, 1987. l t

s

\

1

,\-

F .

i i t

r t

t

/

s j DOCUMENT ID 0043r/0031r

--m__ __m_________ _ _ _ _

3) 7 m .  ! a r 'l .)

I lg_ , , D 1# . >

"# i * (

-/ :s LICENSEE EVENT -) PORTS' '

g/.J N ,

if p i

The titlowing is a tabg br summaryynf all licensee event reports for .

- l

, r f tem .Powed Station, Unit a e, logged during the reporting LaSalle,y\ \ '

l period, Nbecmber,.1, 1987 through November 30, 1987. This information is  !

, ' ' sb

, I Ie, ,, s ,

e i s. i provided pursuant' 'co Lt 3 repercable occurrence reporting requiroents as '

l

[ . / ,: t

, s - ,,

c), . set forth in 10( < 59. *f s .

  • 1

\g f L ensee Event Retort p mber J Date Title of Occurrence

l' ) ,

\

87-034-00 '

'" s .'I

  • 10/17/87 spurious Auto start of "h" VC Ammonia Detectori '

8

', \

i 87/-035-00 , ( . )Mh!87 Ammonia Detect.or actuatici.

, / ,, g-iu 87-036-00 ' .< 11/14/87 "A"AmspiiaDbtectorfailure.

/

\ -

)

)

5 k \ .c

[i-

,) ,

s ,', 1 n r

i

+

'1, e

k .

>)

> n l/, '

/  ; s

.. t

( ,

I i ,  ![

Y , .

(

l' ' / ,

I f

t

/

g i

e t

DOCUMENT ID 0043r/0031r

iI D. DATA TABULATIONS i n this report:

The following data ,tchulatic>ns are presentedf

1. Operating Data Report
2. Average Daily Unit power t.evel
3. Unit Shutdowns and Power Reductions 1

i i

1 ..

DOCUttENT ID 0043r/003]r

1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE December 10,t_i987 COMPLETED BY J. P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PCR10D: November, 1987 GEOSS HOURS IN REPORTING PER10D:_720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):,1078

'3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 990

4. REASONS FOR RESTRICTION (IP ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 720 4939.1 13865.0' l
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0 .
7. HOURS GENERATOR ON LINE 720 4800.4 13602.4 3
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 i
9. GROSS THERMAL ENERGY GENERATED (MWHe) 2096952 3022476 38630656
10. GROSS ELEC. ENERGY GENERATED (MWHe) 705801 3712080 12766060
11. . NET ELEC. ENERGY GENERATED (MWHe) 680565 3534817 12103342
12. REACTOR SERVICE FACTOR 100% 61.6% 40.4%
13. REACTOR AVAILABILITY FACTOR. 100% 61.6% 45.2%  !
14. UNIT SERVICE FACTOR 100% 59.9% 39.6%
15. UNIT AVAILABILITY, FACTOR 100% 59.9% 39.6%
16. UNIT CAPACITY FACTOR (USING MDC) 91.2% 42.6% 34.0% i
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) _ 87.7% 40.9% 32.7%
18. UNIT FORCED OUTAGE RATE 0.0% 10.7% 18.7%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATB, AND DURATION OF EACH)

The units Second Refueling outage is scheduled for March, 1988, and will last 12 weeks.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 1

l djb '

t i

DOCUMENT ID 0043r/0031r L

2. i\VERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373

. UNIT: LASALLE ONE DATE: December 10, 1987 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: NOVEMBER, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 882 17. 984
2. 934 18. 949 3 922 19. 984  ;

.j 4 ,: 963 20. 979 ,_

5. 962 21, 979
6. 953 22. 975 {
7. 964 23. 929
8. 901 24. 929
9. 913 25. 929
10. 954 26, 932
11. 756 27. 928 I
12. 935 28. 923
13. 999 29. 974 l

( '

14. 999 30. 963
15. 995 31. N/A
16. 963 l

l k 1 (

l ,

k i,

l l DOCUMENT ID 0043r/0031r l

l l

_ - l .) E t os crn 0 arJ5 M 5S e 1 M at o 0 abY8 EO eni

.L emB( VC R ot I/ C a

_ OE cDE TS d l

_ NMeEN CN eou ADTO EO pt p p

_ TN EI I RI i E LP RT oen KTEPE OC r ua CI TML CA Dd m CNAOE DUDCT RR NOE W W FORO ODOP T

DGCG ONAN S I I I EI 4 N TTRC O ET U I MUED T I I

I I E C STR U

D 7 E 8 R 9 1

R E ,

W R O E P B M

D E N V N A O O N S S A N E 1 1

W l i R O T D N T O U M H

S T R

T O I P N)

N E OS U R I R TU AO  !

. R! 1 3 U( .

D 2 D

E L

DU ED CE l S

ERl POC YFS T ::

FS 7

8

/

1 E 1 T /

A 1 D 1 O

N 8

1..

l E. UNIQUE REPORTING REQUIREMENTS l

l 1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting.

period.

1 l l l.

l l ,

l l

l i

I l

l l

1 4

i DOCUMENT ID 0043r/0031r

2. ECCS Systems Outages The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 0-306-87 "0" D/G Air Compressor Repair head valve.

0-311-87 "0" D/G Clean fuel oil strainer.

0-314-87 "0" D/G Air Compressor Inspect breaker.

1-1104-87 "C" RHR Pump Motor Replace Ammeter 1-1107-87 RCIC Turbine Repair Drain Connection on Inboard bearing.

1-1126-87 "B" D/G Change Oil Filter.

1-1127-87 "B" D/G Clean Fuel oil strainer and repair leaks.

1-1131-87 "A" D/G "A" D/G Water Temperature Switch.

1-1132-87 "A" D/G "A" D/G Filters.

1-1133-87 "A" D/G Clean Puel Oil Strainer.

1-1138-87 1E22-F010 HPCS Test to CY (Limitorque Inspection).

1-1139-87 RCIC Repair seal water union.

1-1140-87 lE12-F049B Inspect Motor Operator.

1-1141-87 HPCS Line Break Isolation.

1-1149-87 lE12-F006A LES-EQ-ll2 1-1150-87 IDG035 LES-EQ-112.

i l

I l

l DOCUMENT ID 0043r/0031r 1

w_________

, 3. Off-Site Dose Calculation Manual There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatment Systems, j

.There were no changes to the Radioactive Waste Treatment Systems during this reporting period.

5. Indications of Failed Fuel Elements There were no indications of Failed Fuel ElemePts during this reporting period.

l k

i l

I l

l DOCUMENT ID 0043r/0031r i

_ - - - i

Y 1

l l .

I 1

1 LASALLE NUCLEAR POWER STATION 1

UNIT 2 MONTHLY PERFORMANCE REPORT l NOVEMBER, 1987 ,

1 COMMONWEALTH EDISON COMPANY l

NRC DOCKET NO. 050-374

/

l l

l l

1 DOCUMENT ID 0036r/0031r

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 Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Vaste 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.

l Unit two was issued operating license number NPP-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on June 19, 1984.

( This report was compiled by James P. Peters, telephone number I (815)357-6761 extension 325.

l 1

l l

l l

l l

r DOCUMENT ID 0036r/0031r l

l

. TABLE OF. CONTENTS

1. INTRODUCTION.

II. MONT3LY REPORT FOR UNIT TWO 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. Facility or Procedure Changes hequiring NRC Approval
3. Tests and Experiments Requiring NRC Approval
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 3 System
5. Indications of Failed Fuel Elements DOCUMENT ID 0036r/0031r

_.____ ____ . R

. 11. MONTHLY REPORT FOR UN1T TWO B.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO l NOVEMBER l-30 l November 1, 0001 hrs. The Unit entered November with the Reactor critical and on-line at 93% Power (1043 MWe).

November 5, 0115 hrs. Reactor Power decreased to 68% (765 MWe) due to Feedwater transient caused by "A" TDRFP Trip l and RR runback.

l l November 5, 0200 hrs. Commenced Reactor Power increase to 81% (915 l MWe) limited to Feedwater flow (MDRFP).

l November 9, 2300 hrs. Commenced Reactor Power reduction of 100 MWe/hr l for Control Rod manipulations.

l l November 10, 0145 hrs. Reactor Power decreased to 67% (750 MWe).

November 10, 0335 hrs. Commenced Reactor Power increase at 100 MWe/hr.

November 11, 1140 hrs. Reactor Power increased to 96% (1080 M'de) .

l l November 30, 2400 hrs. Reactor and Generator on-line and ramping up to 90% (1000 MWe).

l l

l l

l l

l l

l l

l l

l l

uOCUMeNT 10 0036r/0031r l

B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

. MAINTENANCE.

. 1. Amendments to Facility license or Technical Specification.

There were no Facility License of Technical Specification changes during this reporting period.

2. Facility or Procedure changes requiring NRC approval.

There were no Facility or Procedure change requiring NRC approval during this reporting period.

3. Tests and Experiments requiring NRC approval.

There were no Tests or Experiments requiring NRC approval during l this reporting period.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

I

5. Completed Safety Related Modifications.

The following table (Table 2) presents a list of completed f Modifications during this reporting period. Each entry will have a short synopsis explaining details involved with each modification.

l l

l l

l l

l DOCUMENT ID 0036r/0031r

o s w a .

ih n E . n r s m pc V w p i e es t h I e m w d pi di t T

C n

r

. u p

d n

o p

e an aw i t t a b s w E d e a . a h R et d r d r d c d e d R l l e d e e b ee er e O l i c ed c i d m ru c C af a nr a l a is a t l ao l a od as l sl p ec p c l a pe p ni e l e e e eo er e I o R Cr R R Rl Rp R e

r .

u d r m s n o r N s o t a O e p i l SI r s n a TT p e o CA r m d ER l . e FE i e t . t FP o c o d c EO n n a i l a r r .

DT a m s t e NN m r e a s t AA r o o e e m . a L o f d r r . r t r SP n r A d a h e T e n re l g p FT LE n P e e ez a i o ON UF a P l ti l E SA h d b l g s t EM ES t e a i r u w o CP R t "B r Fe o o n NI N r c " e n i l AU O e e p l e r f s NQ w f M o e u e 1 EE o f B n us p o o T L E R I Fi S N D E ND L I E e B AT r A MA h g s m u T L g n . t f s s EE N u i e n o i s VR O o d s e dn e I I r ni n t ea r TY T h i o o p

u yh p CT C t b n o ac EE N m re o RF U w l e o y h f m t y

RA F o av c c OS L l ni l t dd d r C A f r s r p i na et m M es e p w aol ti a l t e d u s au r F i nc r s n e l c h O o ix o no pn er p e c r oi ai ri a E h s e e i t t c i S c . ag r w t a g n d

~ U ur hn o ar nn ih A met ps i y P cb ei pc n C t ii kd t w ol mu r d dl on di o oi ua P c i

D B a na I c ri Bb aw B s l

B Tf r r -

g r o o a n e t t l r i r C t m c c o-o t e A l r e e s1 s aK d V i a t t I5 s l l r HA Fl e e E e u0 o 1 A D D w2 T r cG c m5 l o N p rD e o7 e ,

aA aB l h 2E m i2 RD oK ud i5 i5 Fc

  1. N o C p 3 R - F e n6 n6 t O C 0 8 t o1 o1 mi t P B Gm "F 6 l 1 Gc m- m- t w iM EC / u " R oD /i mC mC S sA nO V4 DP - r2 Dr AV AV B UC 0 MI t t - - Cn3 E l RS nM s " Y Y I o1 "B V

" O "A

" O i PC A2 oR CA "A e

" R AX

" O "B X

" O Ci0 Rt N T

S E

U Q

E R 6 2 1 9 8 5 5 6 6 9 1 7 7 4 6 4 K 3 8 1 1 2 4 4 6 R 4 2 3 3 3 3 3 3 O 6 7 7 7 7 7 7 7 W L L L L L L L L l I

., TABLE 2

, COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

UNIT TWO M-1-2-84-092: Snubber reduction on subsystem 211G62 per snubber reduction program.

There were no unreviewed safety questions.

i l

4 i

i l

l j

l i

l l

l l

DOCUMENT ID 0036r/0031r j

__ ._. _ - - _ _ _ - _ . -_-______-__0

1

.~

C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, November 1, through November 30, 1987. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CVR 50.73.

Licensee Event Report Number Date Title of Occurrence 87-018-00 10/17/87 Reactor Water Clean-up Isolation due to Personnel error.

87-019-00 10/21/87 RCIC Steam Flow Isolation Switch out of tolerance due to ruptured diaphram.

87-020-00 11/19/87 RClc steam Line High Flow switch failure.

l l

l DOCUMENT ID 0036r/0031r

,g, s j D. DATA TABULATIONS t

The following data tabulations are presented in this report:

1. Operating Data Report
2. Average paily Unit Power Level
3. Unit Shutdowns and Power Reductions t

i i

I l

DOCUMENT ID 0036r/0031r

. . - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ - . _ _ . 1

1.. OPERATING DATA REPORT

- DOCKET NO. 050-374

>. UNIT LaSalle Two DATE December 10, 1987 COMPLETED BY James P. Peters )

TELEPHONE-(815)357-6761 )

OPERATING STATUS l' 1. REPORTING PERIOD

  • November, 1987 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND. CAPACITY

~

(MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078

3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): None
4. REASONS FOR RESTRICTION'(IP ANY): None .

THIS MONTH YR TO DATE CUMULATIVE

.5 NUMBER OF HOURS REACTOR WAS CRITICAL 720 4037.34 16040.8

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0-0

. 29.83

7. HOURS GENERATOR ON LINE 720 3955.9 15727.1 1
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 2217456 12119328 45633592
10. GROSS ELEC. ENERGY GENERATED (MWH) 746833 4029073 21810645
11. NET.ELEC. ENERGY GENERATED (MWH) 720771 3850630 14390859
12. REACTOR SERVICE FACTOR 100% 50.4% 58.7% '
13. REACTOR AVAILABILITY FACTOR __,100% 50.4% 58.8%
14. -UNIT SERVICE FACTOR 100% 49.4% 57.5%
15. UNIT AVAILABILITY FACTOR 100% 49.4% 57.5%
16. UNIT CAPACITY FACTOR (USING MDC) 96.6% 46.4% 50.8%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 92.9% 44.6% 48.8%
18. UNIT PORCED OUTAGE RATE 0.0% 1.4% 21.4%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

.There are no shutdowns scheduled over the next 6 months.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP. N/A 1

l I

l I

l DOCUMENT ID 0036r/0031r

_ - - _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _

.. 2. AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO: 050-374 UNIT: LASALLE TWO v DATE: December 10, 1987 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: NOVEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 1004 17. 1044
2. 1007 18. 1045 3 1010 19. 1044
4. 1028 20. 1010
5. 849 21. 1046
6. 878 22. 1042
7. 880 23. 1046
8. 883 24. 1045
9. 882 25. 1042 10, 888 26. 1045 11, 1046 27. 1034
12. 1047 28, 1047
13. 1028 29. 1044 1
14. 1046 30, 932
15. 1045 31. N/A
16. 1045 _

l 4

l l

l I

l DOCUMENT ID 0036r/0031r l l

7 e1 P5 E a r 3l 3 M r "A

. - l r .) M T" R 0 aeJ5 EO ry R

5Sb 1 VC 0 amY8 I/ ebd n

TS

. L_ec B ( CN t

ad a OE eDE EO we NMDEN RI d sp A TO RT eui TN El i OC ear E LP CA F cT KTEPE CI TML ONAOE DUDCT RR NOE W W FORO ODOP T

DGCG 0 NAN S f I EI i

N TTRC 4 O ET U I MUED T

I I

l i E C STR U 7 D 8 E 9 1

R R

E r W e O b P m e

D v N o N A N O S A S A N E W

l i R O T D N T O U M I

I S T R

T O I P N)

N E OS U R I R TU AO I 5

. RI 8 3 U(

D 0 D

E L

DU ED CE ER I I F POC YFS T

FS

. 7 8

. /

E 5 T /

A 1 D 1

_ O N 3

g ' E.

UNIQUE REPORTING REQUIREMENTS I

l

1. Safety / Relief Valve Operations for Unit 'luo.

DATE VALVES NO & TYPE PLANT DESCRIPTION l '

ACTUATED ACTUATIONS CONDITION OF EVENT There were no Safety / Relief Valve operated for Unit #2 during this reporting i period.

i

?

l i

I l

l l

i DOCUMENT ID 0036r/0031r

2. ECCS Systems Outages

,a The following outages were taken on ECCS Systems during

, the reporting period.

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE f 2-1739-87 "B" D/G Clean and inspect strainers.

2-1741-87 "B" D/G Change filters.

2-1472-87 "B" Petter Diesel Replace lube oil and fuel filter.

2-1743-87 LPCS Lubricate water leg pump coupling.

l 2-1753-87 "A" D/G Replace oil circulation pump.

2-1759-87 2E51-F008 Comply with Technical Specification 3.3.2.

l 2-1761-87 RCIC Administrative Control -

2E31-N013BA Inoperable.

2-1767-87 2E31-N007AA/AB Prevent accidental RCIC 1 solation.

l 2-1768-87 2E51-F064/91 Comply with Technical Specification 3.3.2.

(

l l

l l

DOCUMENT ID 0036r/0031r

e <

3. Off-Site Dose calculation Manual (U-2)

. There were no changes to the ODCM during.this reporting period.

I *

( 4. Radioactive Waste Treatment Systems.

l There were no changes to the Radioactive Waste Treatment Systems l during this reporting period.

5. Indications of Failed Fuel Elements, off Gas Levels indicate one pinhole fuel element failure in the reactor. This does not represent a change since the la:;t reporting period.

There were no indications of Failed Fuel Elements during this ,

reporting period.

i i

l l

l DOCUMEU ID 0036r/0031r

-s' , ,

  • 4:.[C'hs; Ec i Cimm:nw3cith LaSalle County Nuclear Station

' Rural Route #1, Box 220 Edisin r ,\  %> Marseilles, Illinois 61341

\ Telephone 815/357-6761

.'/ \

December 10, 1987 Director, Office of Management Information and Program Control United States Nuclear Regulatory Cotanission Washington, D.C. 20555

' ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period November 1, 1987 through November 30, 1987. ,

, Very truly yours, G. J. Diederich W S ation Manager LaSalle County Station GJD/JPP/sjc Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety i P. Shemanski, NRR Project Manager i D. P. Galle, CECO D. L. Farrar,'C2Co INPO Records Center L..J. Anastasia, PIP Coordinator SNED M. A. Ortin, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle  !

Dennis Carlson/ Tech Staff Terry Novotney/INPO Coordinator, Tech Staff Central File DOCUMENT ID 0043r/0031r

(. J

Retrieved from "https://kanterella.com/w/index.php?title=ML20237A029&oldid=3117187"