U-601183, Monthly Operating Rept for Apr 1988

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Monthly Operating Rept for Apr 1988
ML20154E604
Person / Time
Site: Clinton Constellation icon.png
Issue date: 04/30/1988
From: Spangenberg F
ILLINOIS POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
U-601183, NUDOCS 8805200263
Download: ML20154E604 (6)


Text

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Pego 2 of 5 Attech;;nt to U-601183 MONTHLY OPERATING REPORT FORMAT AND INSTRUCTIONS AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-461 UNIT Clinton 1 DATE 04/30/88 COMPLETED BY F. A. Spangenberg TELEPHONE (217) 935-8881 X3400 MONTH April 1988 DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

l 13 0

29 0

14 0

30 0

1 15 0

31 NA 16 0

l 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 I

apparent anomaly.

8805200263 880430 i

PDR ADOCK 05000461 R

DCD

Page 3 of 5 Attachnent to U-601183 OPERATUU IWTA ICPORT DOCKET 10, 50-461 UNIT Clinten 1 DATE 04/30/88 014PLETED BY F. A. Spangenberg TEEPHotE (217) 935-8881 X3400 OPERATING STATUS 1.

REEOKIDE PERIOD: April 1988 GROSS HOURS IN RENRTHU PERIOD: 719 2.

CURRDTfLY AUDORIZED POWER LEVEL (FMt):

2894 MAX, DEPDO. CAPACITY (FWe-Net):

930 DESIGN ELECIRICAL RATHE (FWe-Net):

933 3.

POWER IEVEL TO MIIG RESTRICIED (IF ANY) (FWe-Net): None 4.

REASONS FOR RESTRICTION (IF ANY):

N/A THIS M0tml YR TO DATE CG ULATIVE 5.

hMGER OF 10URS REACIOR k%S CRITICAL...

0 1875.3 2,773.6 6.

REACIOR RESERVE SHUrDOWN HOURS.........

0 0

0 7.

HOURS GENERATOR ON LHE................

0 1870.5 2,768.8 8.

UNIT RESERVE SIRTfDOWN HOURS............

0 0

0 9.

GROSS THERtRL DERGY GEIERATED (SE)...

0 5,085,874 7,231,374

10. GROSS ELECTRICAL ENERGY GE2EPATED (&R) 0 1,703,040 2,419,690
11. hTT ELEC1RICAL DERGY GENERATED (SE)..

0 1,628,016 2,312,119 12 REACIOR SERVICE FACIOR.................

0.0%

64.6%

73.0%

13. REACIOR AVAIIABILITY FACIOR............

0.0%

64.6%

73.0%

14 UNIT SERVIG FACI 0R....................

0.0%

64.4%

72.8%

15. UNIT AVAIIABILITY FACTOR...............

0.0%

64.4%

72.8%

16. LUIT CAPACITY FACIOR (Using l'DC).......

0.0%

60,3%

65.4%

17. UNIT CAPACITY FACIOR (Using Design FWe) 0.0%

60.1%

65.2%

18. UNIT EDRCED OUTAGE RATE................

0.0%

0.0%

0.0%

19. SIMIIXLES SGEDULED OVER NEXT 610NTHS (TYPE, IRTE, AND DURATION OF EAG): N/A
20. IF SHUR DOWN AT DO OF REPORT PERIOD, FSTD%TED IRTE OF STARTUP: 05/05/88
21. UNITS IN TEST STATUS (PRIOR TO CQ14ERCIAL OPEPATION): FORECAST AGIEVED INITIAL CRITICALITY 2/27/87 INITIAL ELECIRICITY (Synchronization) 4/24/87 014PIETION OF k%PMNIY RUN 10/09/87

Peg 2 4 cf 5 Attcchment to U-601183

~.*

UNIT SHUTD0k'NS AND POk'ER REDUCTIONS DOCKET NO.

50-461 UNIT Clinton 1 DATE 04/30/88 COMPLETED BY F. A. Spangenberg TELEPHONE (217) 935-8881 X3400 REPORT MONTH April 1988 METHOD OF TYPE SHUTTING D0k'N F: FORCED DURATION THE REACTOR OR NO.

DATE S:

SCIIEDULED (HOUPS)

REDUCING P0k'ER (2) CORRECTIVE ACTIONS / COMMENTS 8

880319 S

719 B: Plant shutdown to 4: Continued from Reason perform surveillance last period testing and scheduled A-Equipment Failure maintenance.

(explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training &

License Examination F-Administrative G-Operational Error (explain)

H-Other Method 1-Manual 2-Manual Scram 3-Auto Scram 4-Continued 5-Reduced load 9-Other 1

Pags 5 of 5 Attcch:2nt to U-601183 REFUELING INFORMATION 1)

Name of facility Clinton Power Station 2)

Scheduled date for next refueling shutdown January 3, 1989 3)

Scheduled date for restart following refuel March 5, 1989 4)

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment? Yes If Yes, list in general what these will bet An Operating License and Technical Specification change in response to the Reduced Feedwater Temperature Analysis.

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:

The reload license amendment is scheduled to be submitted on October 18, 1988.

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 core 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) 9)

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

U-601183 L30-88(05-10)-LP 1A.120 ILLINDIS POWE/7 COMPANY CLINTON PontR STATION P.O. BOX 678. CLINTON. ILLINOl$ 61727 10CFR50.36 RG 1.16 May 10, 1988 Docket No. 50-461 Document Control Desk U.S. Nuclear Regulatory Commission k'ashington, D.C.

20555

Subject:

Clinton Power Station, Unit 1 April 1988 Monthly Operating Report NPF-62

Dear Sir:

Please find enclosed the Monthly Operating Report for Clinton Power Station, Unit 1, for the period ending April 30, 1988.

Sincerely yours, IVAwf F. A. Spangenberg, III Manager - Licensing and Safety CSL/krm Enclosure cc: Regional Administrator, Region III, USNRC

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Pcge 1 cf 5 Attech::nt to U-601183 CHALLENGES TO MAIN STEAM SAFETY / RELIEF VALVES Month April 1988 None t

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