L-76-185, Response to Request for Additional Information on the Apendices

Response to Request for Additional Information on the Apendices

ML18227D133
Person / Time
Site:	Turkey Point
Issue date:	05/10/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Lear G Office of Nuclear Reactor Regulation
References
L-76-185
Download: ML18227D133 (8)

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~ i ENCLOSURE APPENDIX "A" CONTAINS ADD'L INFO REGARDING

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APPENDIX "B" CONTAINS INFO ON THEIR PINNED CYCLE 3 STARTUP TEST PROGRAM....

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P. O. BOX 013100, MIAMI. FLORIDA 33101 FLORIDA POWER & LIGHT COMPANY May 10, 1976 L-76-185 Director of Nuclear Reactor Regulation Attention:

Mr. George Lear, Chief Operating Reactors Branch N3 Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

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Dear iM. Lear:

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'll QcE %$8 MAY 17 1976 Go D.~s lech@ RBXNCI~

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Re:

Turkey Point Unit 4 Docket No. 50-251 Additional Reload Information C

In response to requests from the Nuclea'r Regulatory Commission Staff, Florida Power and Light Company is submitting the

'nformation contained in the appendices to this letter.

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

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

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Very truly yours, v

7M4.4~f l~/r Robert 'Z. Uhrig Vice President MAS/cpc

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Attachments cc:

Mr. Norman C. Moseley Jack R.

Newman, Esquire HELPING BUILD FLORIDA

APPENDlX A The information below supplements FPL letter L-76-169 of April 21, 1976 which was submitted in response to an

'pril 7 letter from George Lear.

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

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Emergency Operating Procedure 20003 (Loss of Reactor Coolant) contains instructions on changing the status of valves 862AGB

'nd 864AKB.

The pxocedure will be revised to incl'ude 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 Oper'ator vill be sent to stand.by the "B" Motor Contxol Center.

Xf either of the'se operators is not, available, another operator may be substituted.

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

~ Xt 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 the break. size is large or small.

APPENDIX B 1.0 Ph sics Startu Tests to be Performed for C cle 3 Reload 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.

II Acceptance criteria for total measured rod worth is.

+20% of design.

1.2 1.3 Temperature Coefficient The moderator temperature coe fficient 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..

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

Values for maximum F~H and'< 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.

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.

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f APPENDIX B (Continued) 2.0 Detail Bank Worth Measurements (Continued) 2.1 (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 j.s 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.

I 3.0 Schedule for Submitting Summary Report of Physics Tests S.

J The startup physics summary 'report is submitted to.the NRC within 30 effective full power days of test completion.