U-601005, Monthly Operating Rept for Jul 1987

Monthly Operating Rept for Jul 1987

ML20237H569
Person / Time
Site:	Clinton
Issue date:	07/31/1987
From:	Spangenberg F ILLINOIS POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
U-601005, NUDOCS 8708170272
Download: ML20237H569 (6)

Text

. _ _ _ _ _ _ _ _ _

i >

, 's.

Page 1 of 5 Attachment to U-601005 i CHALLENGES TO MAIN STEAM SAFETY / RELIEF VALVES eL Month July 1987 NONE

)

l l

l i

d 1

0708170272 070731 , ;(.-

PDR ADOCK 05000461 , .

R PDR ,

Page 2 of 5 Attachmsnt to U-601005 MONTHLY OPERATING REPORT FORMAT AND INSTRUCTIONS AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-461 UNIT Clinton 1 DATE 07/31/87 COMPLETED BY F. A. Spangenberg TELEPHONE (217) 935-8881 X3400 MONTH July, 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 412 17 0 2 225 18 0 3 0 19 53 4 96 20 109 5 367 21 183 6 367 22 383 7 321 23 378 8 417 24 105 9 357 25 0 10 398 26 0 11 360 27 0 12 424 28 1 13 8 29 318 14 0 30 524 15 0 31 622 16 0 i 1

I INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

I i

1

b .

L >.

Page 3 of 5 Attachment to U-601005 OPERATING DATA REPORT DOCKET No. 50-461 UNIT Clinton 1 DATE 07/31/87 COMPLETED BY F. A. Spangenberg TELEPHONE (217) 935-8881 X3400 OPERATING STATUS

1. REPORTING PERIOD: July, 1987 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY _ AUTHORIZED POWER LEVEL (MWt): 2894 MAX. DEPEND CAPACITY j (MWe-Net): Not Available DESIGN ELECTRICAL RATING (MWe-Net): 933

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): None 4 REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE )

5. NUMBER OF HOURS REACTOR WAS CRITICAL... 608 2875.5 2875.5 6 REACTOR RESERVE SHUTDOWN HOURS......... 0 0 0

7. HOURS GENERATOR ON LINE................ 487 1156 1156

8. UNIT RESERVE SHUTDOWN HOURS............ 0 0 0

9. GROSS THERMAL ENERGY GENERATED (MWH)... 598,132 1,321,082 1,321,082

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 169,495 311,150__ ,311,150

11. NET ELECTRICAL ENERGY GENERATED (MWH).. 154,282 258,650 258,650

12. REACTOR SERVICE FACTOR................. N/A

13. REACTOR AVAILABILITY FACTOR............ N/A

14. UNIT SERVICE FACT 0R.................... N/A 15.- UNIT AVAILABILITY FACTOR............... N/A

16. UNIT CAPACITY FACTOR (Using MDC)....... N/A

17. UNIT CAPACITY FACTOR (Using Design MWe) N/A

18. UNIT FORCED OUTAGE RATE................ N/A

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Maintenance shutdown, October 28, 198/, 35 days.

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

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 2/27/87 INITIAL ELECTRICITY (Synchronization) 4/24/87 COMPLETION OF WARRANTY RUN 10/22/87 I

---

__- . 1

I i S a N o T OD t' N s ne s IN 5 - g 0 E a ov a TAN

_ t r 0 M w il w C O f n e 4 M t a E IGI R oe5 b 3 O s av t n

R RNT O R M) m0 n X C i l U TIA 4 h0 e / h ul e L T SNNER AN c1 g S t co m I S EIIVE MCA RI aa0 n 1 N rr u A E RAMI gt6 a 8 O s i t r F T RATL ASL at - p8 I E . cn t YTXAA R P PAU S 8 T t eo s T) RGR ERN) CCX

- C d s rc . n NNONOR TON SIE

. 5 A ee d i EI ITOESII T(

1 A 3 rt rwe MA .LATSITA ~LLA 6 9 E i oor d NPLTELANNALDAAMR e .OIPNUUREIRPOUUOE 4 . V ud tli

- 1 F ) I qe cf a ldSUXIFGECMEXHNNTH 0 7 7 T el a p ieAQEAEEPIDPETAAUT 5 n o

8

/

1

- 2 C ru E d eme rer arEE( MRROLAO( EMMAO fir M : : : :

t 1 Y( R ee t a .  : : : :  : :

n 3 B R nh ess ep)A BCDE FG ) 1 234

. i / O oc hya he1 2

(

Ol 7 DE C N s T sw Tr(

NC 0 EN TO T EH )

E LP 2 KTEPE (

CITML R _

ONAOE NOR DUDCT W E FORW ODOO TP DGC 2 3 3 ONAG HIEN S T 1RI N E 1 C O M UEU I HHD T STE C R n w U 7 o o l D 8 i dl r e a s ph s E 9 t ef o se n a i gi a R 1 l a l t ah mg erih e~ l i ecd eT oi d nthT y R ,

n ul ahaer rS ei b E y a cof t esc

.f x mb ee .

W l P rr ran mrnn.dt O u it yg eird u auiil en P J n cnl ner eel rtbbase w eosih cnwmF c rrnum sauugau D o2 rcust naom .

N d - oa i pah r rge t ti cr s

A H t8 rwieo d rf t T u2 oorrt eerciw ooea ss S N h - tl uc hsosHo t h nan N O SP cf pnrT ut p ctT mowi W M ) T a sie acrM al oi O

T (

1 eS em ree ,ta . caoR% eu .f rtld rsep aae D t etP5 T R ot t vnwewrcA7 rnl .

U O N ms ee esl e ro h y a pf ol nent a erisb gi raiia _

H P O h S E S RT Tsvoocfi raa Tat wvsf R A _

T E :  :  :

I R B A A N _

U N

O)

IS TR AU 9 1 6 RO 2 5 5 UH D(

D E

DL EU CD ERE _

POH YFC S F F T S _

F:

S _

7 7 7 8 8 _

8 / / -

E / 3 4 T 2 1 2 -

A / / /

D 7 7 7 O 0 N 8 9 1 -

' lflfl

^( .

Page 5 of 5 Attachment to U-601005 REFUELING INFORMATION l

1) Name of facility Clinton Power Station

2) Scheduled date for next refueling shutdown January 1989 l-I i 3) Scheduled date for restart following refuel March 1989

4) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If Yes, list in genercl what these will be:

An Operating License and Technical Specification change in response to the Reduced Feedwater Temperature Analysis if it is performed for CPS.

If No, has the reload fuel design and core configuration been reviewed by the Facility Review Group (FRG) to determine whether any unreviewed safety questions are associated with the core reload? No If no such review has taken place, when it is scheduled? July, 1988 *

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

A Technical Specification Amendment package will be submitted in the fall of 1987.

6) List any 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.

The new cote design is not yet finalized.

7) Number of fuel assemblies a) in the core 624 b) in the spent fuel storage pool 0

8) The present licensed spent fuel pool storage capacity 2,672 The size of any requested or planned increase in licensed storage capacity 0 (number of fuel assemblies) l

9) The projected date of the last refueling that can be discharged to the -l spent fuel pool, assuming the present licensed capacity 2010

• The refueling outage scheduled to begin in Oct. 1988, has been rescheduled to begin in Jan. 1989 To support an Oct. 1988 refueling outage IP review of the core reload documentation was scheduled to be completed in July 1988. l The date for the refueling outage has been rescheduled, but the date for this supporting milestone has not been changed.

U-601005 L30-87 ( 08- 12)-L 1A.120 ILLINDIS POWER COMPANY IP CLINTON POWER STATION P.o. BOX 678, CLINTON. ILLINOIS 61727 August 12, 1987 10CFR50.36 RG 1.16 Docket No. 50-461 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station, Unit 1 July 1987 Monthly Operating Report NPF-62

Dear Sir:

Please find enclosed the Monthly Operating Report for Clinton Power Station, Unit 1, for the period ending July 31, 1987.

Sincere

• ours,

&f F. A. S angen erg, III Manager - Liegnsing an Safety GSL/krm Enclosure cc: Regional Administrator, Region III, USNRC

>d i

1\

-