ML18227D131

Response to Request for Additional Information on the Appendices

ML18227D131
Person / Time
Site:	Turkey Point
Issue date:	05/10/1976
From:	De Mastry J, Robert E. Uhrig Florida Power & Light Co
To:	Lear G Office of Nuclear Reactor Regulation
References
L-76-185
Download: ML18227D131 (8)

Text

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NRC DISTR IBUTION Fon PART 50 DOCKET MATERIAL DOCKET NVMOI!n FILc NUMacn TO: '~Lear

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one signed DESCAIPTION Ltr re our 4-7-76'tr....trans the following:

ENCLOSU AE I

Addi Reload info......responding

.to our previeus Questions in Appendix A & furnishing info re Cycle '3 statrup test program as 'Appendix B......

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<<gs FLORIDA POWER IIt LIGHT COMPANY May 10, 1976 L-76-185 Director of Nuclear Reactor Regulation Attention:

Mr. George Lear, Chief Operating Reactors Branch 53 Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Lear:

Re:

Turkey Point Unit.

4 Docket No. 50-251 Additional Reload Information Cg g I

In response to requests from the Nuclear Regulatory Commission Staff, Florida Power and Light Company is submitting the information contained in the appendices to this letter.

Appendix A contains additional information regarding your previous questions of April 7, 1976.

Appendix B contains information on our planned Cycle 3 startup test program.

Very truly yours,

/

Robert E. Uhrig Vice President MAS/cpc Attachments cc:

Mr. Norman C. Moseley Jack R.

Newman, Esquire HELPING BUILD FLORIDA

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APPENDIX A The information below supplements FPL letter'-76-169 of.

April 21, 1976 which was submitted in response to an April 7 letter from George Lear.

The numbers correspond to,the questions in the April 7 letter.

'6.'mergency Operating Procedure 20003 (Loss of Reactor Coolant) contains instructions on changing the 'status of valves 862A&B

'nd 864A&B.

The procedure will be revised to include instructions on designating specific personnel for restoring power to the valve operators..

When approaching the Refueling, Water. Storage Tank low level alarm setpoint,, the Nuclear Operator will be sent. to stand by the "C" Motor Control Center.

The Nuclear Turbine Operator

'ill be sent. to stand.,by the "B" Motor Contxol Center. If either of these operators is not available, another operator may be substituted.

. When the RWST low level alarm is reached, the designated operators will unlock and close the circuit, breakers specified in the procedure'.

It is anticipated that the, recirculation phase will begin 30 minutes to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after LOCA initiation depending on whether

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the break size is large or small.

APPENDIX B 1.0 Ph sics Startup Tests to be Performed for C cle 3 Reload 1.1 Rod Worth Measurements Total rod worth is measured to verify adequate reactivity for control and determine that sufficient shutdown margin, including actual uncertainties, exists within the limits of the steam break analysis assumptions.

Acceptance criteria for total measured rod worth is

+20% of design.

1.2 Temperature Coefficient.

The moderator temperature coefficient is'easured and the acceptance criteria is that it must be zero or negative and within the limits assumed in the analysis for reduction in feedwater enthalpy.

1.3 Power Distribution Measurement Prior'o,operation above 35% power, a flux map is taken to verify power distribution and peaking factors.

Values for maximum F~H and F< must be less than those specified in the Technical Specifications to ensure that the assumptions used in the analysis for

'establishing DNB Margin, Linear Heat Rate, and thermal margins remain valid during operation.

1.4 Hot Zero Power Boron Concentration, All Rods Out The HZP, ARO boron concentration is measured to provide indication of overall available reactivity for the cycle and must be within + 100 ppm of the design value.

2.0 Detail Bank Worth Measurements 2.1 Rod worth is measured by starting with all rods out and then inserting each bank into the core.

The individual banks are inserted in small increments and the boron concentration is varied to maintain criticality.

Reactivity of the rods is measured in terms of rod height changes as calculated and recorded by a reactivity computer.

The maximum uncertainty expected from this measurement technique is +10% which includes uncertainties for reactivity computer error and errors in data reduction.

APPENDIX B (Continued) 2.0 Detail Bank Worth Measurements (Continued) 2.l (Continued)

The maximum uncertainty expected in the design values is

+10% which is due primarily to inability to model the exact core conditions during the test period.

Therefore, the total maximum expected deviation from design is expected to be within +20%.

,For deviations, greater than this, the test program is halted and all data is reevaluated, the design values are reverified and a shutdown margin is calculated using the actual deviation to determine if safe operation may continue.

3.0 Schedule for Submitting Summary Report, of Physics Tests The startup physics summary report is submitted to the NRC within 30 effective full power days of test completion.

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