ML19269D878

Monthly Operating Rept for May 1979

ML19269D878
Person / Time
Site:	Crystal River
Issue date:	06/03/1979
From:	Stephenson W FLORIDA POWER CORP.
To:
Shared Package
ML19269D876	List: ML19269D875 ML19269D878
References
NUDOCS 7906200271
Download: ML19269D878 (5)

Text

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FLORIDA POWER CORPORATION INTER-OFFICE CORRESPONDENCE P4Y9 TAT QTVFD WM t'a D DT AW (Office - Locationi subject: NRC Monthly Operating Report Date: 6/3/79 W 1-C2 To:

Patsy.Baynard Attention Of:

Attached is the Crystal River Unit #3 MAY, 1979 input to the NRC Monthly Operating Report required by Pegulatory Guide 1.16.

L Guy Beatty, Jr.

Nuclear Plant Superintendent 2251 120 CC:

A.E. Friend E.C. Simpson W. A. Stephenson b

o 7906200S 7/2 1

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OPERATING DATA REPORT DOCKET NO.

50-302 DATE 6/3/79 COMPLETED BY W. A. Stephenson TELEPHONE (904) 795-6486 OPERATING STATUS

1. Unit Name: CRYSTAL RIVER UNIT 3

. Nates

2. Reporting Period:

5/1/79 - 5/31/79

3. Licensed Thermal Power (MWt):

2452

4. Nameplate Rating (Gross MWe):

890

5. Design Electrical Rating (Net MWe): 825 835

6. Maximum Dependable Capacity (Gross MWe):

797

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Thr> ugh 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted,If Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cuenulative

11. Hours In Reporting Period 744.0 3623.0 19439.0

12. Number Of Hours Reactor Was Criticr.1 0.0 2282.5 12139.7

13. Reactor Reserve Shutdown Hours 0.0 223.4 606.8

14. Hours Generator Or.-Line 0.0 2254.6 11799.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 0.0 5002488.0 25599656.0_

17. Gross Electrical Energy Generated (MWH) 0.0 1707369.6 8705215.A

18. Net Electrical Energy Generated (MWH) 0.0 1615921.0' 8245785.7

19. Unit Service Factor 0.0 62.2%

60.7%

20. Unit Avs!! ability Factor 0.0 62.2%

60.7%

21. Unit Capacity Factor (Using MDC Net) 0.0 56.0%

53.2%

22. Unit Capacity Factor (Using DER Net) 0.0 54.1%

51.4%

23. Unit Forced Outage Rate 0.0 12.9%

32.7%

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

25. If Shur Down At End Of Report Period. Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 1/14/77 INITIAL ELECTRICITY 1/30/77 COMMERCIAL OPERATION 3/13/77 i

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-302 UNIT FLCRP DATE 6/4/79 COMPLETED BY W. A. Stephenson TELEPHONE ronn 795-6486 MONTTI MAY. 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) t ywe. Net) 1 0

17 0

2 n

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 n

3 o

0 8

n 24 9

0 25 0

10 0

26 0

11 0

27 0

12 n

23 0

13 0

29 0

14 0

30 0

15 0

33 0

16 O

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

(4177) 2251 122 5

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DOCKET NO. 50-302 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME FLCRP-3 DATE 6/1/79 REPORT MONTil MAY, 1979 COMPLETED BY IL A-Stephonann TELEPilONE tonia 795-6486 1

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.! E j E5 Licensee P.

l"3 Cause & Corrective

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o No.

I.s.st e g

gg g

,3 g 5 Event u7 c.

Action to

$E 5

j 15 g Report #

1. C fu Present Recurrence 6

i 79-11 790423 S

744 C

1 ZZ ZZZZZZ l

N N

1 2

3 4

i w

F: Forced Reason:

Method:

Exhibit G. instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Ma!ntenance or Test 2 Manual Scram.

Entry Sheets for Licensee

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C Refueling 3 Automatic Scram.

Event Report (LER) File (Nt!RI:G.

N D-Regulatory Restriction 4-Other (Explain) 0161)

U E Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibii I. Same Source p:/77) llother (Explain)

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MONTHLY STATUS REPORT REFUELING INFORMATION REQUEST

^

1.

Name of Facility: Crystal River Unit 3 2.

Scheduled date of next refueling shutdown: April, 1979.

3.

Scheduled date for restart following refueling: June, 1979.

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes.

In general, changes to the CR #3 technical specifications will include:

a.

Moderator Temperature Coefficient (3.1.1.3) b.

Control Rod Insertion Limits (3.1.3.6) c.

Control Rod Group Assignments (3.1.3.7) d.

Axial Imbalance Limits (3.2.1) e.

Refueling Boron Concentration (3.9.1)

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These specifications will be reviewed and changed as necessary based on the reactivity of the second cycle as compared to that of the first cycle.

5.

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

February, 1979.

6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or perfor-mance analysis methods, signifigant changes in fuel design, or new opera-ting procedures.

Florida Power Corporation is presently discussing with the NRC staff

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our intent to request that the power level of CR #3 be raised from the present level of 2452 MW (t) to the ultimate core power level of 2544 MJ (t) as described in the CR #3 FSAR.

FPC submitted on February 28, 1979 our reload report justifying Cycle 2' operation of CR #3 at 2544 MW (t).

On May 25, 1979, FPC modified its Cycle 2 reload reoort justifying continued operation at 2452 MW (t).

It is our intent to continue our discussions with the NRC in order to obtain the power upgrade at a later date.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 assemblies b) 4 assemblies 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storace capacity that has been requested or is planned, in number of fuel assemblies, a.

Present storage capacity - Pool A - 120 plus 8 failed fuel assemblies Pool B - 120 plus 8 failed fuel assemblies s

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8.

(Continued) b.

Filed request on January 9,1978 with NRC concerning expansion of Pool A from 120 to 544 assemblies plus 6 failed fuel assemblies and expansion of Pool B from 120 to 609 assem-blies. Expansion of Pool A is to occur after the refueling in April,1979. The Pool B expansion will occur at a later refueling outage (approximately 1986).

Additional detailed design information concerning our fuel pool expansion was submitted to the Commission on March 3, March 22, 1978, January 18, 1979, and March 16, 1979.

9.

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

1981-1982.

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