ML17341A869

Forwards Request for Addl Info Re Removal of Boron Injection Tank from Facilities

ML17341A869
Person / Time
Site:	Turkey Point
Issue date:	01/25/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
References
NUDOCS 8202100090
Download: ML17341A869 (8)

Text

Docket Nos. 50-250/251 (10g~qg50 He5%ltfFs g

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Sincerely, 10riginal Sinned BF~

Steven A. Varga, Chief Operating Reactors Branch 81 Division of Licensing

Enclosure:

Request for Additional Information J~N ~ ~

Distribution:

Docket File NS

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cPK NRC PDR Local PDR ORB 81 Rdg Dr. Robert E. Uhrig, Vice President D. Eisenhut Advanced Systems and Technology OELD'lorida Power and Light Company OIaE

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Post Office Box 529100 S. A. Varga Miami, Flor ida 33152 hl. Grotenhuis C. Parrish

Dear Dr. Uhrig:

J.

Guttman We have completed our prel iminary review of your letter dated November 30, 1981 (L81-502) regarding the removal of the Boron Infection Tank from the Turkey Point Plaqt Unit Nos, 3 and 4.

We find that we need the additional information outlined in the enclosure to this letter.

In order to maintain our review schedule, we will need your formal response before the amendment can be issued as scheduled on February 12, 1982.

cc:

See next page 8202i00090 820i25 PDR ADOCK 05000250

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Robert'E.

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Florida Power and Light Company cc:

Mr. Robert Lowenstein, Esquire Lowenstein, Newman, Reis and Axelrad

'025 Connecticut Avenue, N.W.

Suite 1214 Washington, D. C; 20036 Environmental and Urban Affairs Library

'Florida International University Miami, Florida 33199 Mr. Norman A. Coll, Esquire

Steel, Hector and Davis 1400 Southeast First National Bank Building Miami, Florida 33131

.Mr. Henry Yaeger, Plant Manager Turkey Point Plant Florida Power and Light Company P. 0. Box 013100 Miami, Florida 33101 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting. Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Res'ident Inspector Turkey Point.Nuclear Generating Station U. S. Nuclear Regulatory Commission Post. Office Box 1207 Homestead, Florida 33030

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L TURKEY PLAINT UNITS 1

5 2 QUESTIONS REGARDING THE REMOYAL OF THE BORON INJECTION TANK Q. 1:

Page 2.1.6 References the K ff versus temperature reactivity utilized in eff the LOFTRAN code.

The K ff referenced was for 1000 psi..

Confirm that the eff LOFTRAN analyses utilized other tables at the appropriate pressures during the postulated events.

Q2:

What were the limiting single failures used in the analyses (e.g., Pg.

2.1.6-4 states 2 SI pumps were assumed operational).

Q3:

Provide a schematic diagram of the system, as presently

designed, and another with the proposed hardware modifications (bypassing the BIT tank).

d Q4:

Page 2.1.6-12 states "The,power transient shown in Figure 2.1.6-8 is con-tt d

t th ~ddt 1

f th 'f dh 1

1 th 1

f1 dt-tion.",Discuss, in detail, the, reasons as to why underprediction of the reactivity feedback results in a conservative prediction.

Q5:

Provide details as to why the steam line break event, with offsite power, available, is limiting over the same event with offsite power not available.

It is our understanding that LOFTRAN utilizes the broken loop cold leg tem-perature when evaluating the moderator temperature reactivity feedback.

Since the primary coolant residence time through the, steam generator is ex'-

tended during the loss-of-offsite-power event,.the moderator temperature at 4

. the stuck-rod sector of. the core coul,d result in a more. limiting condition

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for DNBR. considerations.

Describe-why this event is.-'no't limiting and how LOFTRAN conservatively evaluates-the-.consequences of this event.

g6:

It is our understanding that LOFTRAN thermal-hydraulically homoginizes (assumes perfect mixing) the reactor coolant entering the vessel from the broken'nd intact recirculation loops.

This assumption provides identical hot leg '

L temperatures for all loops.

Of concern is that the broken loop cold leg temperature may be non-conservatively elevated since the broken loop hot leg temperature could be appreciably lower than analyzed.

Should this be the case, then the moderator temperature at the stuck rod location would

- be non-co'nservatively ana'lyzed.

Justify your analytical model with regards to the above concern.

g7:

Due to th'e uncertainties within the analytical techniques and possible op-erator errors, discuss why the operator procedures should not address the use of the Boric Acid Tank should criticality be obtained -during the event of a steam line-break.

g8:

Technical Specificat'ions (TS) should be clear and concise.

The proposed modifications to 'the TS could result in some confusion to the plant oper-ators and/or plant technicians. 'his confusion-can result from referencing a system'which is in the process of being modified on two units.

Justify the need for this interim TS or provide a revised TS which. incor-porates the removal of the BIT tank and will not be. implemented until the appropriate hardware modifications have been completed.

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