L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,

05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,

ML18227D859
Person / Time
Site:	Turkey Point
Issue date:	05/13/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-76-189
Download: ML18227D859 (14)

Text

NRC FOAM 196 IZ 7GI~

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~, U.S. NUCLI:AB BEOULATOIIY NRC DISTRIBUTION Fon PART 50 DOCKET MATERIAL QISSION DOCKET NUMOEA 50-251 FILE NUMOEB TO Mr. V. Ste o FROM: FPL DATE OF DOCUMFNT Miami, Fla.'3101 76

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0 A R. E. Uhrig DaTE AECEIVEO 5-14<<76 ETTEA ~$ 4OTOAIZED PAOP INPUT FOAM NUMOEB OF COPIES RECEIVED 7'SXNIGINAL RPGNC LASS IF I E 0 QCOPY 3 signed-37 CC DE cBIPTIDN Ltr notarize - - request or Revised Tech Spec pages. for Tech Spec amdt to OL'/DPR-41/Tech Specs in re to for Turkey Pt. Unit 4 ' ~ ~

parameters & trans .the following:

, (40 cys encl rec'd)'0"

,PLANT NAhIE: Turkey Pt. Un&.,4 KQI)Mgg SAFETY FOR ACTION/INFO RMATION ENVXRO ASSIGNED AD: ASSIGNED AD :

BRANCH CHIEF: BRANCH CHXEF ~

PROJECT hIANAGER: PROJECT hfANAGER:

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~ REG FI fCC PDR E NST I&E BENAROYA ALLARD QE D SPANGLER GOSSXCK & STA,F EN INEER N IPPOLITO SITE TECH QASE KNIGHT OPERATING REACTORS GAKIILL hIA SIPCEIL STELLO STEPP PAHLICKX HULlIAN OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY EXSENHUT SITE ANALYSIS BOYD ROSS SHAO VOLLhIER P. COLLINS NOVAK BAER BUNCH HOUSTON ROSZTOCZY SCIWENCER COLLXNS PETFRSON ClIECK GRTffES KREGER

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SKOVHOLT SALTZMAN ANALYSIS RUTBERG DENTON & hIUI.LFR EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR ~ .Miami Fla. NATL LAB BROOKIIAVI'.N NATL LAB TXC REGS V"IE ULRIKSON(ORNL) 5897 N iI LA PDR ASLB CONSUf TANTS E

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fg @9Vb'LORIDA POWER at LIGHT COMPANY st May; 1:31976 11ig- 6 L-76-189 gt NegIIiatorJ Docket File Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington,'. C. 20555

Dear Mr. Stello:

"W <rg Re: Turkey Point Unit 4 Docket, No. 50-251 DPR-'41'p Proposed Amendment to Facility 0 crating License In accordance with 10 CFR 50.30, Florida Power and Light Company submits herewith three (3) signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating License DPR-4 1.

This proposal is being submitted in response to a request, from your staff. The proposal is as described below and as shown on the accompanying Technical Specification page bearing the date of this letter in the lower right hand corner.

~@V A new specification 3.1.6 on Unit 4 DNB Parameters is added. This specification is similar to one previously incorporated for Unit 3.

Pages B3.1-7 and B3.1-8 A new Bases section is provided to describe one of the new DNB Parameters. Uncertainty in the flow determination method to be used is estimated to be from three'o five percent.

HELPING BUILD FLORIDA

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Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Jr., Director

'age Two'ay 5, 1976 The proposed amendment has been reviewed and the con-clusion reached that it does not involve a significant.

hazards consideration, therefore, prenoticing pursuant to 10 CFR 2.105 should not be required.

Very yoursI Robert E. Uhrig Vice President REU/cpc Attachment cc: Mr. Norman C. Moseley Jack R. Newman, Esquire

0 6., DNB PARQKTERS ~pegofetory Docket File The following DNB related parameters limit shall be maintained during power operation:

a. Reactor Coolant System Tavg < 578.2I 'F

b. Pressurizer Pressure > 2220 psia*

c. Reactor Coolant Flow >,i268,500 j gpm With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce thermal power to less than 5% of rated thermal power using normal shutdown procedures.-

Compliance with e. and b. is demonstrated by verifying that each of the parameters is within its limits at least once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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Compliance with c. is demonstrated by verifying that the parameter is within its limits"after each refueling cycle.

>> Limit not applicable during either a THERMAL POWER ramp increase in

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excess of (5%) RATED THEK1AL POWER per minute or a .THERMAL POWER step increase in excess of (10%) RATED THERMAL POWER.

3.1-7a Unit No. 4 5/S/76

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• reactor coolant would be released

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to the secondary system.

All the noble gas activity transferred to the steam gen-erator was assumed released, while the iodine was assumed to partition between the liquid and vapor phases.

The resultant site boundary dose. is approximately 0.25 rem whole body and approximately 2.5 rems to the thyroid, using the tw'o-hour meteorological dispersion factor for the plant.

These doses are less than 1% of the guideline doses of ~ ~

3.0CFRl00.

Maximum Reactor Coolant Oxv en and Chloride Concentration

.3'aintaining the reactor coolant chemistry within the

,29m%'ts specified, the integrity. of the Reactor Coolant

~ ':. System is protected. (3) , \

.', If these li'mits are exceeded,, measures can be taken to cor-

'eet the

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condition, e.g., replacement of ion exchange resin or ad)ustment of the hydrogen concentration in the volume "control tank, and further because of the time dependent

~ture of any adverse effects arising from concentrations M excess of the limits, it 'is unnecessary to shut'.down.-

~ediately since the condition can be corrected. Thus the period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for corrective action to restore the aoncentrations within the limits has been established. If

'he corrective action has not been effective at the end of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, .then the reactor will be brought to the cold shutdown condition and the corrective action will continue.

B3.1-P 5/5/76

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6. DNB Parameters Reactor Coolant Flow Measurements (4)

Elbow taps are used in the reactor coolant system as an instrument device that indicates the status of the reactor coolant flow. The basic function of this device is to provide information as to whether or not a reduction in flow rate has occurred. The correlation between flow reduction and elbow tap readout has been well estab1ished by the following equation:

AP C~ 2 (W ') where AP is the referenced pressure

'AP 0, 0 0

differential with the corresponding referenced flow rate W , and AP is the pxessure differentia1 with the 0

corresponding flow rate W. The full flow reference point is established during initial startup. The low flow trip point is then established by extrapolating along the correlation curve.

References (1) FSAR Table 4.1-3 (2) FSAR Section 14.1.10 (3) FSAR Section 4.2.8 (4) FSAR Section 4.2.9 B3. 1-8

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STATE OF FLORIDA )

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COUNTY OF DADE )

E. A. ADOMAT, being first duly sworn, deposes and says:

That he is a Vice President. of Florida Power 6 Light Company, the Licensee herein; That, he has executed the foregoing instrument; and that the statements made in this said instrument are true and correct to the best of his knowledge, information, and belief; and that he is authorized to execute the instrument on behalf of said Licensee.

E. A. Adomat Subscribed and sworn to before me this day of 1976.

Notary Public in and for the County of Dade, State of Florida No/ARk ~

iN COMMISSION EXPIRESkI.O'ISA 'I EARG'.

PUr<(IC C vI'AIK Qf NO BONDEO THRU My Commission expires '

E INS. UNDER@%R Pl

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