ML20137L023

Rev 0 to JPN-PSL-SEFJ-95-003, Engineering Evaluation,Impact of Hot Leg Temp Oscillations on Safety Analysis

ML20137L023
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Issue date:	01/13/1995
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References
FOIA-96-485 JPN-PSL-SEFJ-95, JPN-PSL-SEFJ-95-003, JPN-PSL-SEFJ-95-3, NUDOCS 9704070140
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in JPN-PSL-SEFJ-95-003 Rev 0 Page 1 of 11 FLORIDA POWER & LIGHT CO.

ST. LUCIE UNIT 1 Engineering Evaluation l

Impact of Hot Leg Temperature Oscillations on the Safety Analysis JPN-PSL-SEFJ-95-003 Rev 0 January 13, 1995 9704070140 970402 Safety Related.h PDR FOIA l

BINDER 96-485 PDR i

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JPN-PSL-SEFJ-95-003 Rev. O Page 2 of 11 REVIEW AND APPROVAL RECORD

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PLANT ST. LUQIE UNIT 1

TITLE IMPACT OF HOT LEG TEMPERATURE OSCILLATIONS ON THE SAFETY

{

ANALYSIS LEAD DISCIPLINE Nuclear Fuel / PSL fuel Encineerina ENGINEERING ORGANIZATION Nuclear Technical Suppoit a

1 REVIEW / APPROVAL:

INTERFACE TYPE FPL GROUP PREPARED VERIFIED APPROVED APPROVED

• INPUT REVIEN N/A MECH X

N/A N/A N/A ELECT X

N/A N/A N/A I&C X

N/A N/A N/A CIVIL X

N/A N/A N/A NUC" X

N/A N/A N/A ESI X

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• For Contractor Evals As Determined By Project

" Review Interface As A Min On All 10crR50.59 Evals and PLAs FPL PROJECTS APPROVAL:

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DATE:

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OTHER INTERTACES JPN rorm 24, Rev. 9/92

~ - - - - -

l JPN-PSL-SEFJ-95-003 Rev 0 Page 3 of 11 1

1 i

TABLE OF CONTENTS f

DESCRIPTION h

]

I.

Purpose And. Scope 4

II.

Effect on Safety Analysis 4

III. Operability Assessment 4

IV.

Conclusions 5

i V.

Verification Summary 5

VI.

References 5

T l

ATTACHMENT 1.

St. Lucie Unit 1 Hot Leg Temperature Oscillations 6

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JPN-PSL-SFFJ-95-003 Rev 0 Page 4 of 11

!)

I.

PURPOSE AND SCOPE:

Recently during Cycle 13 operation of St. Lucie Unit 1, temperature oscillations were observed in the hot leg Resistance Temperature Detectors (RTDs) readings.

The measured hot leg temperatures in the two ' loops were seen to fluctuate within approximately f.1 F for

~eriods extending to a few hours (Attachment 1).

Temperature fluctuations of this nature were seen earlier at St.

Lucie Units 1 & 2, and at other plants (References 1, 2 and 3).

It is felt that these fluctuations result from stratification in the i

hot legs in combination with incomplete mixing and swirl of the core flow in the region from the upper plenum to the hot legs.

The purpose of this evaluation is to assess the impact of 1

temperature fluctuations on the safety analysis and the operability of the St. Lucie Unit 1 Reactor Protection System (RPS).

I II.

EFFECT ON SAFETY ANALYSIS:

'ho hot leg temperature measurement feeds into the RPS through the AT power calculator.

Reactor power is one of the inputs to the Variable High Power Trip, Local Power Density Trip and Thermal Margin / Low Pressure Trip.

These reactor trip functional units use

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the auctioneered higher of the AT power and the excore detector (Nuclear) power.

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The safety analyses performed by Siemens Power Corporation (SPC) for St. Lucie Unit 1 use only the nuclear power as input to the j

above trips during simulation of transients (Reference 4).

The

)

fluctuations in the hot leg temperature and the corresponding AT

power, therefore, have no effect on che safety analysis.

Additionally, the hot leg temperature does not explicitly appear as i

an input to any of the safety and setpoint analyses performed for St. Lucie Unit 1.

I

/

AT power is also not credited in the analysis of asymmetric events,

{

which rely on the asymmetric steam generator pressure trip,,(ASGPT),,,. fe to mitigate the consequences of such e pvp#pul m (ge I. e-l

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y o..n chtt%.D 9 I I1'

[Tlie-hot leg tiemperaturE ~ oscillations, theref ore, do-not-htve-eny-

,. adverse effect on St. Lucie Un

~b[saf etiyJ;_ analysis.

Temperature, fluctu qions of greater than 13Ep' require further investigatRn) hlthowgtr empnh1_e__ from the

,/

gfety anhWet Stem-+MEratT6n _,

d UL., OPERABILITY ASSESSMENT:

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eLN c' I

l' The recent hot leg temperature fluctuations observed at St. Lucie Unit 1 are consistent with those seen previously at St. Lucie,.Unjlts ic n.ps :m shl! hm W

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S and 2, and at other plants.

These fluctuations are shown to not impact the safety analysis for St. Lucie Unit 1.

The measured temperature oscillations are similar to those described in Reference 3 and are the result of such phenomena as fluid swirl and turbulence, incomplete mixing and stratification, resulting from a

{

non-uniform temperature distribution at the core exit.

The observed hot leg temperatures indicate that the present temperature measurement instrumentation,. which does-not me3nrg_t.heAlk-flui<i.

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_temperatureci-s-working,as designed._ /rhe present design would thus/

react to any system changes and provide artaccurate_ indication of)

(a change in AT required for the RPS. f' Therefore, t he r'e' Ere~n~o safety ~~5r ~operaiill~ty 6Hnde~rns ~related to the temperature

~-

fluctuations.

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5. C. l '

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CONCLUSIONS:

p g 6., q;

(,

.q rformed her(e concludes that there is no impact of p.

RThe evaluation G the obserred vari.a_tions in the hot leg tempera'tures on thegeJu, Qts

/crflhe_safetyanalywifor_S".Lucie, Uriiti~l Cy_cipJ,[No safety' limits will be violated due to variations in the hot leg

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C tem l

C

.Q s._peratures in excess of currently seen values. '

[ "p' t V.

VERIFICATION

SUMMARY

t/:[yThis

',o engineering evaluation, prepared per ENG QI 2.0, has been f

logically developed and used the necessary design and reference

([ d aterials to support l

the conclusions derived.

The results of the ation show that the observed variations in the hot leg

.hempeTature have no effect on the results of the current safety l

Q'been reviewed in evaluating the impact of the hot leg temperature analyses.

It is verified that the applicable transient events have 4L

' N } rclassified as Nuclear Safety Related.

variations.

This engineering evaluation has been properly

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VI.

REFERENCES:

t.

k,'N'k,.

FPL Letter FRN-88-149, R.A. Decker to J.A.

Handschuh, Safety N 't Evaluation ~ for St. Lucie Unit 2 Cycle 4 Temperature Anomaly, y

{ x. Q rch 3,1988

[.; ;2 CE Letter F-CE-7668, R.R. Mills to K.N. Harris (FPL), AT Power

.'. N}y T Calculator Evaluation, April 15, 1982 r'

y

-Q CE Infobu11etin 89-05, Reactor Coolant Temperature Fluctuations

.. N

4. I Siemens Letter RIW:94:106, R.I.

Wescott to E.R.

Knuckles (FPL), Verification of Power Input Assumption for Simulations, August 26, 1994 f

[&~

L X j'3 f,, y! {. ~. J f

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