Text

Letter Proposed Changes to Technical Specifications Relative to ECCS Analysis & Fuel Design
	ML18227B315
Person / Time
Site:	Turkey Point
Issue date:	04/30/1975
From:	Robert E. Uhrig; Florida Power & Light Co
To:	Rusche B; Office of Nuclear Reactor Regulation
References
	Download: ML18227B315 (18)
	v • d • e

e 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 DOC 4-30-75 ORIG 1 Signed DATE R EC'D 5-5-75 CC OTHER ILTR XXX 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 the following....

~ PLANT NAME:

Turkey Point.,3

& 4 ENCLOSURES:

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

~....

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$'I'lip FLORIDA POWER & UGHT COMPANY April 30, 1975 L-75-209 Mr. Benard C.

Rusche, Director Office of Nuclear Reactor Regulation U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Rusche:

TURKEY POINT PLANT DOCKET 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 submitted several questions to us on April 15, 1975, relative to the ECCS analysis and fuel design.

We are enclosing with this letter the answers to those questions.

Very truly yours, Robext E. Uhxig Vice Pxesident REH:GEL:tg Enclosures J.I, g Pt()~

HELPING BUILD FLORIDA

t IL

r

QUESTIONS AND ANSWERS RELATiNG TO TURKEY POINT UNIT 4 RELOAD AND ECCS REEVALUATION On the second and third pages of the Appendix to your proposed amendment to your operating license dated February 10,

1975, you indicate four factors which were considered in establishing control rod insertion limits for Cycle 2 of Unit 4.

Please furnish details on which of 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 establishing these limits; At the end of cycle, maintaining adequate shutdown 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 worth for Cycle 2 in Unit. 3.

Please furnish details as to whether this is a problem and its potential effect on startup tests and operation of Unit 4.

Westinghouse has recalculated BOL control bank worth 'for Uni.t 3, Cycle 2 based on actual EOL Cycle 1 boron measure-ments.

The results of these calculations indicate that measured rod worth is within 8-o of the revised predictions and this analysis shows that adequate shutdown margin is available at the end of Cycle 2 for Units 3 and 4.

In-dependent calculations, performed by FPL, are in excellent agreement with the revised Westinghouse results.

Since the same procedure will be used'y Westi~nghouse for Unit 4, BOL predictions, we foresee no problem in this area.

QWe have received information for other nuclear power facilities that the partial flux map option in the iproposed ECCS Technical Specifications may allow operating conditions for which the DNB analysis is not 'complete.

Is this the case for Turkey Point?

We have been advised of this situation by Westinghouse

and, at their recommendation,,we do not intend to utilize the partial flux map option until such time as the DNB analysis

,is complete.

4.

Q-Will the proposed ECCS Technical Specifications resu'lt in restriction to power level at any time in the future? If power level restrictions will result, describe the magnitude and duration of such restrictions.

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

DGC.~Pi~,.>08.

50-250

(:. >0-2>l

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4

QUESTIONS AND ANSWERS (Continued) 5.

Q Will the proposed ECCS Technical Specifications affect fuel utilization by changing fuel through-put?

If fuel utilization is affected, describe th'e magnitude of this change.

A Fuel utilization (through-put) is continuously being evaluated from an economic fuel management standpoint but we do not expect any affect due to the proposed ECCS Technical Specifications.

6.

Q Will any. change in effluent releases result from the pro-posed ECCS Technical Specifications?

If effluent releases are changed, describe the magnitude and composition of the new releases.

A None.

DOCKET 80S, 50-250

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1
9 Analytically justify the HPI flow splits across the small-to-intermediate break spectrum.
Describe these calculations and show that sufficient HPI flow is injected to the reactor vessel for a break in an HPI line (i.e.,
show that all HPI water is not pumped to the break).
A Each of the three cold leg high pressure safety injection lines connects to one of the three 10 inch accumulator in-jection lines just upstream of the 10 inch check valve.
(See FSAR Figure 6.2-1).
Therefore, a break in one of the high pressure safety injection lines would not.result in a blow-down of the reactor coolant system and there is no concern for the resulting pressure imbalance at. the discharge points for the broken lines versus the intact lines.
In the event that a "small break" occurs downstream of the 10 inch check valve in the low pressure injection connection to the RCS a blowdown of the RCS will'occur.
However, the pressure in the broken line at the point of high pressure safety injection will be the.same as the rest of the reactor coolant system except for a minor adjustment for pressure losses caused by the break flow through the reactor coolant system.
Thus for "small breaks" where the flow from the high pressure injection system is important there is no significant pressure imbalance at the injection points into the RCS and thus there is no preponderance of safety injection flow through the broken line on.to the containment floor. It should also be mentioned that no credit is taken for any safety injection flow into the broken line.
For the analysis credit is taken only for flow through the two lines with the highest line resistance and the line with the lowest resistance is assumed to be pumping to the broken line and spilling to the contain-ment.
The safety injection line resistances for the Turkey Point units were verified by pre-operational testing to be in satisfactory. agreement with the analysis.
They demonstrated that the safety injection system. would deliver a flow to the core greater than the flow assumed for the analysis assuming a 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 the RCS and the safety injection line is exposed to containment backpressure, a pressure imbalance will exist between the discharge points of the intact and broken S.I. lines during the RCS blowdown.
Such a pressure imbalance is considered in the analysis.
The analysis accounts for this difference in pressure at the injection points and calculates the corresponding S.I. flow through each line.
However, such a
break is a "large break" and blowdown of the reactor coolant system is completed in a short time and the reactor coolant system and the containment are then at the same pressure, thus terminating the flow imbalance that resul'ted from the different backpressures.
DOCKS',!. NOS.50-250,& 50-251
il 0
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The attached curves depict the results of. the analysis for a case considering a spilling.line.
Curve l Flow delivered through tha two high head S.X. lines with the higher flow resistance.
Flow for which credit for core cooling is taken.
s Curve 2
Total flow delivered through all three high head safety, injection lines.
The difference between the two curves represents the flow to the line connected to the broken RCS loop,(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 pressure during the injection phase of a LOCA to be exerted on the water in the line from the RWST (thereby preventing flow from the RWST).
Verify the complete electrical separation (separate cable trays, etc.) is achieved up to the power supply which is common to each of these sets of valves.
The power supplies for the MOVs 860A and B, and 861A and B
comply with electrical train separation criteria.
Valves designated to function as part of the "A" train have their control 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 not affect its duplicate.
There is no requirement to have further separation of cabling to individual components of a given train and thus the power cabling for valves 860A and 861A are run in the same cable tray and the power cable for valves 860B and 861B are also run in the same cable tray.
The control cable for these valves is similarly routed (i.e. separation by train only).
3.
Q For a CD of 0.4, the generic 3-loop analysis showed a pos'tive core 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 to confirm that the expected decrease in core flow after 10 seconds (with pumps running) would not cause an increase in PCT.
~A Figure 1 shows plots of the coreflow during blowdown for the Double Ended Cold Leg Break with CD = 0.4 for two conditions:
1)
The "design" assumption that the
~RCS pumps trip at the time of the pipe break.
2) Assuming that the RCS pumps run at 100%
speed during blowdown.
All other input assumptions were'identical for these cases and the results are that the design case (pumps trip) had a'peak clad temperature 26 F higher than the pumps run case.
This confirms the results and conclusions reached in the generic 3 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 confirmed that the station Tech Specs require the power supply to these valves to be locked out.~~
~~A The circuit breakers for motor operated valves 866A and 866B are locked open at their respective motor control centers.~~
~~The valves are administratively controlled by plant operating procedures.~~
~~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 confirmed that the station Tech Specs require the power supply to these valves be locked out.~~
~~A These valves are controlled as discussed above and have no specific Tech Spec requirement.~~
~~DOCKET NOS.~~
~~50-250~~
~~& 50-251~~
~~~ll~~~

ML18227B315

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Dear Mr. Rusche:

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