U-601685, Monthly Operating Rept for May 1990 for Clinton Power Station
| 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
{{#Wiki_filter:U 601685 s ? 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
- angeherg, I
F. A. 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 l i 1
r 4 Pcg31 cf 4 to U-601685 i CllA11ENGES TO MAIN STEAM SAFETY / RELIEF VALVES Month May 1990 None B
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Attachment.1 to U 601685 i AVERACE DAILY UNIT POWER LEVEL o s r. DOCKET NO. 50 461 l j UNIT Clinton 1 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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i p, Pcg) 3 ef 4 to U.601685 OPERATING DATA REPORT DOCRET NO. 50 461 UNIT Clinton 1 DATE 05/31/90 I COMPLETED BY F. A. Sonneenbere. III 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 (MWe Net): 930 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, IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A j J
a-Page o of 4 4 ~ 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 , _. _}}