ML19209D090

Monthly Operating Rept for Sept 1979

ML19209D090
Person / Time
Site:	Crystal River
Issue date:	10/02/1979
From:	Beatty G, Stephenson W FLORIDA POWER CORP.
To:
Shared Package
ML19209D085	List: ML19209D084 ML19209D090
References
NUDOCS 7910190382
Download: ML19209D090 (6)

Text

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p 9 *g INTEROFFICE CORRESPONDENCE CRYSTAL RIVER UNI!' 3 CR-3 (tillCil (E AIL COIll IllitCT:

NRC MONTilLY OPERATING REPORT 19:

PATSY BAYNARD BATE: OCTOBER 3, 1979 3-0-1-C2 Attached is the Crystal River Unit //3 SEPTEf tllER. 197'l input to the NRC Monthly Operating Report required by Regulatory Guide 1.16.

Guy

. Beatty, J,'

Nuclear Plant Manar,er cc:

A. E. Friend E. C. Simpson P. D. Breedlove W. A. Stephenson

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30 520 15 1'O 31 16 146 INSTRUCTIONS On this format. hst the nerip daily mut power lesel m \\lhe. Net f or e.r.h d.iy m the reportune m..nih C..mpive t,

the nearest whole mepw.itt.

ren;i 1175 258

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MONTHLY STATUS REPORT REFULLING INFORMATION REQUEST 1.

Name of Facility:

Crystal River Unit 3 2.

Scheduled date of next refueling shutdown:

April, 1980.

3.

Scheduled date for restart following refuelino:

June, 1980.

4.

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

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

a.

Moderator Temperature Csefficient (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)

'Sese specifications will be reviewed and changed as necessary based

-n the reactivity of the second cycle as compared to that of the first cycle.

5.

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

Februa ry, 1980.

6.

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, or new operating procedures.

Florida Power Corporation is presently discussing with the NRC staf f 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 MW (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 report justifying continued operation of 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.

60 assemblies 8.

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

a.

Present storage capac:ty - Pool A - 120 plus 8 failed fuel assembiles.

Pool B - 120 plus 8 failed fuel assemblies.

WPSemhW01 1175 259 5

8.

(Continued) b.

Filed request on January 9,1978 with NRC concerning expansion of Pool A from 120 to 544 assemblies plus 6 f ailed fuel assemblies and expansion of Pool B from 120 to 609 assemblies.

Ex;)ansion of Pool A is to occur at the refueling in April,1980.

The Pool B expansion will occur at a later refueling outage (approximately 1986).

Additional detailed design information concerning our f uel pool expansion was submitted to the Commission on March 3 and March 28, 1978, January 18, 1979, March 16, 1979, June 29, 1979, September 5, 1979 and October 10, 1979.

9.

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

1981-1982.

1175 260 WPSemhW01 05