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NRC DISTRIBUTION FOR PART 50 DOC MATERIAL~ (TEMPORARY FORM).

CONTROL NO:

FILE'ROM

Florida Power & Light Co,Miami, Fla.Robert E Uhri

TO:Benard C, Rusche

DATE OF DOC4-30-75

ORIG1 Signed

DATE R EC'D5-5-75

CC OTHER

ILTRXXX

TWX RPT OTHER

SENT AEC PDR

SENT I.OCAL PDR XXX

CLASS UNCLASS PROPINFO INPUT NO CYS REC'D

1

DOCKET NO:-25 251

DESCRIPTION:

Ltx. refer. their Ltr of 3-11-75, also refer,our ltr of 4»15-75, concerning ECCS trans thefollowing....

~ PLANT NAME: Turkey Point.,3 & 4

ENCLOSURES:

Proposed Changes to Tech, Spec., relative tothe ECCS Analysis and fuel design. ~ ....

( l cy. Encl, rec'@~ RpMOV XJ

go QU'7.

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INTERNALDISTRIBUTION'REG F TECH REVIEW

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$ 'I'lip

FLORIDA POWER & UGHT COMPANY

April 30, 1975L-75-209

Mr. Benard C. Rusche, DirectorOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D. C. 20555

Dear Mr. Rusche:

TURKEY POINT PLANTDOCKET NOS. 50-250 and 50-251

PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS

In the review of our Proposed Changes in Technical Specifi-cations submitted March 11, 1975, your staff submittedseveral questions to us on April 15, 1975, relative to theECCS analysis and fuel design. We are enclosing with thisletter the answers to those questions.

Very truly yours,

Robext E. UhxigVice Pxesident

REH:GEL:tg

Enclosures

J.I, g Pt()~

HELPING BUILD FLORIDA

tIL

:r

QUESTIONS AND ANSWERS RELATiNG TOTURKEY POINT UNIT 4

RELOAD AND ECCS REEVALUATION

On the second and third pages of the Appendix to yourproposed amendment to your operating license datedFebruary 10, 1975, you indicate four factors which wereconsidered in establishing control rod insertion limitsfor Cycle 2 of Unit 4. Please furnish details on whichof these factors were controlling and why.

The control rod insertion limits for Cycle 2 of Unit 4,are conservative based on all four factors in establishingthese limits; At the end of cycle, maintaining adequateshutdown margin is typically the most limiting factor.

2. Q — We understand that there appeared to be substantial differ-ences between predicted and measured control bank worthfor Cycle 2 in Unit. 3. Please furnish details as to whetherthis is a problem and its potential effect on startup testsand operation of Unit 4.

Westinghouse has recalculated BOL control bank worth 'forUni.t 3, Cycle 2 based on actual EOL Cycle 1 boron measure-ments. The results of these calculations indicate thatmeasured rod worth is within 8-o of the revised predictionsand this analysis shows that adequate shutdown margin isavailable at the end of Cycle 2 for Units 3 and 4. In-dependent calculations, performed by FPL, are in excellentagreement with the revised Westinghouse results. Sincethe same procedure will be used'y Westi~nghouse for Unit 4,BOL predictions, we foresee no problem in this area.

Q—We have received information for other nuclear power facilitiesthat the partial flux map option in the iproposed ECCSTechnical Specifications may allow operating conditions forwhich the DNB analysis is not 'complete. Is this the casefor Turkey Point?

We have been advised of this situation by Westinghouse and,at their recommendation,,we do not intend to utilize thepartial flux map option until such time as the DNB analysis,is complete.

4. Q- Will the proposed ECCS Technical Specifications resu'lt inrestriction to power level at any time in the future? Ifpower level restrictions will result, describe the magnitudeand duration of such restrictions.

A We do not anticipate any power level restriction for newcores .in the future.

DGC.~Pi~, .>08. 50-250 (:. >0-2>l

Ib ll)

'I

,I s 4

QUESTIONS AND ANSWERS (Continued)

5. Q — Will the proposed ECCS Technical Specifications affectfuel utilization by changing fuel through-put? If fuelutilization is affected, describe th'e magnitude of thischange.

A — Fuel utilization (through-put) is continuously being evaluatedfrom an economic fuel management standpoint but we do notexpect any affect due to the proposed ECCS TechnicalSpecifications.

6. Q — Will any. change in effluent releases result from the pro-posed ECCS Technical Specifications? If effluent releasesare changed, describe the magnitude and composition of thenew releases.

A — None.

DOCKET 80S, 50-250 & 50-251

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9 — Analytically justify the HPI flow splits across the small-to-intermediate break spectrum. Describe these calculationsand show that sufficient HPI flow is injected to the reactorvessel for a break in an HPI line (i.e., show that all HPIwater is not pumped to the break).

A — Each of the three cold leg high pressure safety injectionlines connects to one of the three 10 inch accumulator in-jection lines just upstream of the 10 inch check valve. (SeeFSAR Figure 6.2-1). Therefore, a break in one of the highpressure safety injection lines would not .result in a blow-down of the reactor coolant system and there is no concernfor the resulting pressure imbalance at. the discharge pointsfor the broken lines versus the intact lines.In the event that a "small break" occurs downstream of the 10inch check valve in the low pressure injection connection tothe RCS a blowdown of the RCS will 'occur. However, thepressure in the broken line at the point of high pressuresafety injection will be the .same as the rest of the reactorcoolant system except for a minor adjustment for pressurelosses caused by the break flow through the reactor coolantsystem. Thus for "small breaks" where the flow from the highpressure injection system is important there is no significantpressure imbalance at the injection points into the RCS andthus there is no preponderance of safety injection flow throughthe broken line on .to the containment floor. It should alsobe mentioned that no credit is taken for any safety injectionflow into the broken line. For the analysis credit is takenonly for flow through the two lines with the highest lineresistance and the line with the lowest resistance is assumedto be pumping to the broken line and spilling to the contain-ment.

The safety injection line resistances for the Turkey Pointunits were verified by pre-operational testing to be insatisfactory. agreement with the analysis. They demonstratedthat the safety injection system. would deliver a flow to thecore greater than the flow assumed for the analysis assuminga broken RCS cold leg and the worst single active failure(i.e. with minimum safeguards).

For a break where the 10 inch. line becomes separated from theRCS and the safety injection line is exposed to containmentbackpressure, a pressure imbalance will exist between thedischarge points of the intact and broken S.I. lines duringthe RCS blowdown. Such a pressure imbalance is consideredin the analysis. The analysis accounts for this differencein pressure at the injection points and calculates thecorresponding S.I. flow through each line. However, such abreak is a "large break" and blowdown of the reactor coolantsystem is completed in a short time and the reactor coolantsystem and the containment are then at the same pressure,thus terminating the flow imbalance that resul'ted from thedifferent backpressures.

DOCKS',!. NOS.50-250,& 50-251

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The attached curves depict the results of. the analysis for acase considering a spilling .line.Curve l — Flow delivered through tha two high head S.X. lineswith the higher flow resistance. Flow for which credit for corecooling is taken.

s

Curve 2 — Total flow delivered through all three high headsafety, injection lines. The difference between the two curvesrepresents the flow to the line connected to the broken RCSloop,(i.e. the spilling line flow for which no credit is taken). ~

t

2. Q — A spurious opening of MOVs 860A and 861A (or MOVs 860B and 861B)at the containment sump would permit containment pressureduring the injection phase of a LOCA to be exerted on the waterin the line from the RWST (thereby preventing flow from theRWST). Verify the complete electrical separation (separatecable trays, etc.) is achieved up to the power supply which iscommon to each of these sets of valves.

— The power supplies for the MOVs 860A and B, and 861A and Bcomply with electrical train separation criteria. Valvesdesignated to function as part of the "A" train have theircontrol cabling and power cabling routed in cable trays, ducts,conduits, etc. separately located from those for "B" train en-suring that any physical damage affecting one circuit will notaffect its duplicate. There is no requirement to have furtherseparation of cabling to individual components of a given trainand thus the power cabling for valves 860A and 861A are run inthe same cable tray and the power cable for valves 860B and 861Bare also run in the same cable tray. The control cable forthese valves is similarly routed (i.e. separation by trainonly) .

3. Q — For a CD of 0.4, the generic 3-loop analysis showed a pos'tivecore flow between 10-13 seconds compared to Figure 14.3.2-35

~ which shows a negative core flow during, this'eriod...Re-run this worst-case with reactor coolant pumps running toconfirm that the expected decrease in core flow after 10seconds (with pumps running) would not cause an increase inPCT.

~ A — Figure 1 shows plots of the core„flow during blowdown for theDouble Ended Cold Leg Break with CD = 0.4 for two conditions: *

1) The "design" assumption that the ~RCS pumps trip atthe time of the pipe break.

2) Assuming that the RCS pumps run at 100% speed duringblowdown.

All other input assumptions were'identical for these cases andthe results are that the design case (pumps trip) had a'peakclad temperature 26 F higher than the pumps run case.

This confirms the results and conclusions reached in the generic3 loop .sensitivity study presented in WCAP 8356.

*Applies for Turkey Point Units 3 and 4'.

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4. Q — Normally closed NOV 866A and 8668 — It should be confirmedthat the station Tech Specs require the power supply to thesevalves to be locked out.

A — The circuit breakers for motor operated valves 866A and 866B arelocked open at their respective motor control centers. Thevalves are administratively controlled by plant operatingprocedures. There is no requirement in the Technical Specifica-tions that specifically address locking these valves closed.

5. Q — Normally open HOV 862A and lIOV 8628 — It should be confirmedthat the station Tech Specs require the power supply to thesevalves be locked out.

A — These valves are controlled as discussed above and have nospecific Tech Spec requirement.

DOCKET NOS. 50-250 & 50-251

· e nrc~distribution for part 50 doc material (temporary form). control no: file'rom florida...

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