ML20043G126

Monthly Operating Rept for May 1990 for Clinton Power Station.W/900614 Ltr

ML20043G126
Person / Time
Site:	Clinton
Issue date:	05/31/1990
From:	Spangenberg F ILLINOIS POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L30-90(06-14)-L, L30-90(6-14)-L, U-601685, NUDOCS 9006190094
Download: ML20043G126 (5)

Text

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         .                                                                               U 601685

? i L30 90(06 14).LP 8E.100c CLINTON POWER STATION P.O. It0X 678. CLINTON. ILLINOIS 61727 0678. TELEPHONE (217) 93514861 h. June 14, 1990 10CPR50.36 p Docket No. 50 461 l U.S. Nuclear Regulatory Commission - Document Control Desk ' Washington, D.C. 20555

Subject:

Clinton Power Station, Unit 1 May 1990 Monthlv Operatinc Report NPP 62

Dear Sir:

Please find in Attachment 1 the Monthly Operating Report for Clinton Power Station, Unit 1, for the period ending May 31, 1990, Sincerely yours, V. , 90v t F. A. angeherg, I Manage. - Libansing nd Safety DAS/alh Attachment . cc: NRC Region III Regional Administrator NRC Resident' Office i I I' 9006190094 900531 PDR ADOCK 05000441 j' R pod i l 1

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CllA11ENGES TO MAIN STEAM SAFETY / RELIEF VALVES Month May 1990 None B

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i o AVERACE DAILY UNIT POWER LEVEL s r. DOCKET NO. 50 461 l UNIT Clinton 1 j DATE 05/31/90 l 1 COMPLETED BY F. A. Soangenberg. III TELEPHONE- (217) 935 8881 X3400 j

,,               . MONTH     May 1990

[- DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL i (MWe Net) (MWe. Net)  : 1-1 .. 929 17 79  ; 2 930 18 0 _j 3 926- 19 107 I- 4 929 20 578 i 5- 929 21 642  ; 6 893 22 814 -{ 7 916 23 918 i 8_ 908 24 -923 -{ 9 112 25 914 j 10 0 26 925 l

                 -11                0'                 27               895

• b -12 'O 28 924 13 0 29 922 14 0 30 923  !

< 1  : 1$ 0 31 921-  ! ' I 16 0

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          .                                                                                    Attachment 1           ,

to U.601685  ; OPERATING DATA REPORT - DOCRET NO. 50 461 UNIT Clinton 1 DATE 05/31/90 COMPLETED BY F. A. Sonneenbere. III ;I TELEPHONE (217) 935 8881 X3400 OPERATING STATUS I. REPORTING PERIOD: May 1990 GROSS HOURS IN REPORTING PERIOD: 241 [ [ 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2116 MAX. DEPEND. CAPACITY (MDC) s 930 (MWe Net): DESIGN ELECTRICAL RATING (MWe Net): 213

3. POWER LEVEL TO VHICil RESTRICTED (IF ANY) (MWe Net): E2ne 4 REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTil YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL.. _ $90.3 1953.7 14.495.7 '

6. REACTOR RESERVE SHUTDOWN 110URS . . . . . . .. 0.0 0.0 0.0,  ;

7. Il0URS GENERATOR ON LINE................ 517.2 1776.3 13.870.9

8. UNIT RESERVE SHUTDOWN 110URS . . . . . . . . . . . . 0.0 0.0 0.0

9. GROSS TilERMAL ENERGY GENERATED (MWil) . . .L357.493 4.641.404 34.698.569 7

10. GROSS ELECTRICAL ENERGY GENEP.ATED (MWH) 450.815 1.549.111 11.477.475

11. NET ELECTRICAL ENERGY GENERATED (MWH).. 426.785 1.463.497 10.870.246

12. REACTOR SERVICE FACTOR................. 79.34 53.9% , 65.7%  ;

13. REACTOR AVAILABILITY FACTOR. . . . . . . . . . . . 79.34 53.9% 65.74

14. UNIT SERVICE FACTOR.................... 69.5% 49.06 62.9% .;

15. UNIT AVAILABILITY FACTOR............... 69.54 49.0% 62.9%

16. UNIT CAPACITY FACTOR (Using MDC)....... 61.74 43.4% 53.0% i

17. UNIT CAPACITY FACTOR (Using Design MWe) 61.5% 43.3% $2.8%

18. UNIT FORCED OUTAGE RATE................ 30.5%_ 27.7%- 17.8%

19. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTilS (TYPE, DATE, DURATION OF EACH):

The second refueling outage is currently scheduled to begin October 14, -j 1990 and last for approximately 94 days. 20, j IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A J

a-Page o of 4 4 Attachment 1 ~ to U-601685 . UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-461 UNIT .Clinton 1 DATE 05/31/90 COMPLETED BY F. A. Somanenberr. III TELEPHONE (217) 935-8881 13400 REPORT MONTH May 1990 METHOD OF TYPE SHUTTING DOWN F: FT)RCED DURATION THE REACTOR OR CORRECTIVE ACTIONS NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER (2) /Cunnw15 90-04 900509 F 188.7. A,D: The Division 1 and 2 1,2: Reactor recirculation flow diesel generators were was reduced and control declared inoperable due rods were inserted. At 254 to expansion joint tie reactor power a manual scram rods on the service water was initiated. (LER 90-010) supply and return lines on the jacket water heat exchangers not being installed. These tie re-is were removed during plant construction Plant shutdown was initiated in accordance with Technical Specification 3.8.1.1 Action g. 90-05 900517 F 38.1 A: Power supply in the feed- 2: Manual Scram. Manual scram was water control system failed initiated per plant procedures causing both resceor after both reactor recirculation recirculation pumps to psamps received a signal to receive a signal to downshift. downshift. (LER 90-012) (1) Reason A-Equipment Failure (explain), B-Maintenance or Test, C-Refueling, D-Regulatory Restriction, E-Operator Training & License Examination, F-Administrative, G-Operational Error (explain), H-Other (2) Method 1-Manual, 2-Manual Scram, 3-Auto Scram, 4-Continued

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