ML20002D126

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Submits Addl Info in Response to Questions Re Request for Change 12 to Tech Specs of License DPR-6
ML20002D126
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 02/06/1967
From: Haueter R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Boyd R, Morris P
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101190497
Download: ML20002D126 (3)


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gg3 70, DR. PETER A. MORRIS' DIRECTOR DIVISION OF REACTOR LICENSING UNITED STATES ATOMIC ENERGY COMMISSION D

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WASHINGTON' D.C.

(o co ATTENTION, MR. ROGER S. B0YD FROM, R. L. HAUETER' ASST ELECTRIC PRODUCTION SUPERINTENDENT - NUCLEAR DATE, FEBRUARY 6' 1967 DOC}_ET, 50-155 ygg,go THE FOLLOWING INFORMATION IS SUBMITTED TO YOU IN REPLY TO QUESTIONS FROM YOUR STAFF CONCERNIN3 OUR RECENT REQUEST FOR CHANGE NO. 12 TO THE TECHNICAL SPECIFICATIONS OF LICENSE NO. DPR-6.

IN OUR REQUEST FOR CHANGE NO. 12' WE STATED THAT.

... THE NEV CHF CORRELATION GIVES AN OVERALL GAIN OF ABOUT 10 PERCENT IN CHF RATIO AND' THEREFORE' PROVIDES MORE OPERATING FLEXI-BILITY IN CORE ARRANGEMENT AND CYCLE LENGTH."

FURTHER DISCUSSION

FOLLOWS, FIRST' WE WISH TO CORRECT A TYPOGRAPHICAL ERROR IN IHE ABOVE STATEMENT.

IT SHOULD HAVE RE AD, "THE NEW CHF CORRELATION GIVES AN OVERALL GAIN OF ABOUT 10 TO S0 PERCENT IN CHF RATIO... ETC."

THE FOLLOVING TABULATION IS PRESENTED AS AN EXAMPLE OF MCHFR CONDITIONS AS THEY WOULD VARY DVER THE LIFE OF A TYPICAL CORE LOADING.

COMPARISON OF MCHFR WITH OLD AND NEW CORRELATIONS POWER SHAPE,r, MCHFR FOR 11 X 11 C FUEL AT 4.22 X RATED POWER RATIO

.................................. NEW TO RADIAL AXIAL OLD CHF CORRELATION NEW CHF CORRELATION OLD FACTOR FACTOR

., NODE,

, NODE, CONDITION, BEGINNING LIFE,MANY CONTROL RODS INSERTED, 45 1.99,5,, AT X,~0.159 2.25 7 AT X 0.1265 1.12 f/

["f O f 7

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AND G/A - 2T3'000 AND k/A,

y 325 000

,G/A (EAK, 542'000

,t/A, PEAK, 34t'000

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w CIODLE LIFE 0.0415 1.32.T. AT X g 0.116 1.21 8.32 1.625,5,

't.92,5, af X g AND t/A, 374 000 AND G/A, 316 000

,t/A, PEAK, 374'000

,G/A, PEAK, 374'000 CONDITITN,

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A):0l END OF LIFE,CONTRDL RODS ALL OUT, 0.167 1.48 0.2205 3.11,6. AT X g

1. 823 l'385,1, 1.42,8, AT K g AND G/A 184 000 AND Q/A, 192 000 s

,G/A, PEAK, 392'000

,G/A, PEAK, 392'000 50DE FOR MINIMUM CRUTICAL NEAT FLUX RATIO BASED ON 9 NODES' e

STARTING v!TH 1 AT THE 80TTOM OF THI FUEL.

r LOCAL POWER FACTOR OF l.3 FOR ALL CASES.

NCDE FOR PEAK KEAT FLUX IS IN PARENTMESIS.

es, CORRECTION = LAST SECTION SECOND FIGURE SHOULD BE I.355,2, THE AB0VE TABLE SHOWS THAT FOR THIS C ASE, TYPIC AL OF CORE LOADINGS EXPECTED DURING THE NEXT YEAR,* TKE MCHFR AT BEGINNING OF LIFE IS VEtt A90VE 1.5" AS IS THE MCHFR FOR THE MIDDLE OF LIFE.

AT THE END OF LIFE CONDITION

  • THE MCKFR USING THE OLD CORRELATION IS BELOW l.S' WHILE THE MCHFR USING TKE NEW CORRTLATION SHOWS CONSIDER-ABt E PARGIN. THUS USE OF THE OLD CHF CORRELATION WOULD REQUIRE A PLANT DERAIE OF S TO 15 PERCENT,TO STAY APOVE A MCHFR OF 1.5, SOME-

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TIME DURING THE LAST NALF 0F THE CORE LIFE. THE OTHER ALTERN ATIVE I

i WCULD BE EARLY REFUELING WITH ITS ATTENDANT INCREASED FUEL COST.

I ACCUMUL ATED OVER A NUMBER OF CYCLES' THE LOSS OF CAP ACITY AND/OR l

FUEL BURNUP AMOUNTS TO A SEVERE ECON 0rIC BURDEN. THE APPLICATION OF THE NEW CHF CORFELATION TO OUR OPERATIONS WOULD PERMIT US TO RUN A i

l SPECIFIC CORE TO ITS END OF REACTIVITY LIFETIME' AT THE PLANT,5 j

FULL CAPACITY.

I TO SUMMARIEE OUR REASONS FOR REQUESTING CHANGE NO. 13, i

l.

SENERAL ELECTRIC,S NEW CMF CORRELATION REPRESENTS YHE LATEST AND BEST MULTI-ROD HEAT TRANSFER D AT A APPLIC ABLE TO THE FUEL DESIGN USED IN THE BIG RUCK POINT PLANT. IT IS CONSUMERS POWER COMPANY,5 STANDARD PRACTICE TO INCORPORATE ALL NEW TECHNOLOGICAL DEVELOPMENTS INTO ITS OPERATIONS AS SOON AS IS FEASIBLE.

2.

THE CHANGE 'FROM THE OLD CMT TO TME NEW CHT WOULD l

NOT SUEETANTI ALLY CHANGI REACTOR CORE CONDITIONS OVEP A CORE LIFETIME.

AS NOTED ON THE ABOVE TAPLE' TKI PEAK HOT CHANNEL HEAT FLUX AT END OF LIFE VOULD ONLY BE S PERCENT ABOVE THE MIDDLE OF LIFE VALUE AND STILL SIGNIFICANTLY BELOW THE TECHNICAL SPECIFICATION LIMIT OF 530'000.

TMI CORE AVERAGE KEAT FLUK REMAINS THE SAME IN ANY CASE.

3.

TMI CHANGE VOULD ALSO PROVIDE MORE FLEXIBILITY IN CORE ARRANGEMENT AND CYCLE LENGTH. THE HITEROGENEOUS MIXTURE OF FUEL IN THE REACTOR MAKES IT DIFFICULT TO ARRIVE AT A CORE ARRANGEMENT WHICP l

IS ACCEPTAPLE FROM A MCHTR VIEWPOINT OVER THE WHDLE LIFE OF THI CORE i

l LOADING. IN MOST INSTANCES' TFI OLD CHF CORRELATION FORCES A CORE ARRANGEMENT WHICH MAS A MCKTR BELOW l.5 BEFORE TME END OF CORE LIFE.

4.

THE DEVELOPMENTAL FUEL IRRADI ATION PROGRAM AT BIG ROCK POINT IS COMING TO A CLOSE. BASED UPON INF0PMATION FROM TM15 PROGR AM* AND STMEF ADV ANCES IN TME ST ATE OF THE ART' WE PLAN IN THE NEAR FUTURE TO SPT!MIZE THE FUEL DESIGN AT 516 RDCK POINT TO BRING If RORI IN LINI VITH CURRENT BVR COMMERCI AL FUEL' E.G. 9 K 9 LATTICE AND 9.16 INCH OD FUIL RODS COMPARED TO BIG ROCK POINT,5 11 X Il LATTICE l

I AND 0.449 INCH OD FUEL RODS. SEFORE LARGE AMOUNT OF TIME AND EFFORT IN DESIGNING TM15 FUEL FOR BIG ROCK POINT CAN BE JUSTIFIED' AP?ROVAL l

FOR BSE OF TMIS NEV CHF CORRELATION IN TMI BIG ROCK POINT REACTOR 15 EECESSART.

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