ML20126E327

Submits Addl Info in Support of Request for Change to Tech Specs Per

ML20126E327
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/02/1965
From:	Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Boyd R, Doan R US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101190458
Download: ML20126E327 (6)

Text

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TUY 517 7E',.1985 PAF,NELL ROAD OTTICE 4 1965 W1.4 2 /. aR i JACK 50h r.ICHICAN * .

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// I .eei cc:N 3-2-65 E-05 AM v.s.r. 1 /.UNn I F {74 g

>- a TO - DR. R. L. DOAN, DIRECTOR f* (Tn DIVISION OF REACTOR LICENSING F 5 g R C

UNITED STATES ATOMIC ENERGY COMMISSION $m I

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I ATT - MR. ROCER S BOYD DOCKET 5C-155 gile copy, 1

IN RETLY TO YOUR LETTER DATED TEERUARY 19, 19 62, TO MR. H. R RECUESTING ADIITIONAL INFORMATION IN SUPPORT OT CHANGE TO OUR TENNICAL SPECITICATIONS, DATED JANUARY 13,19C RELATIVE TO LOW SOURCE LEVEL STARTUPS OF THE PLANT, WE SUBMIT THE TOLLOWING -

l AN ANALYSIS OT A STARTUP ACCIDENT RESULTIN REACTIVITY INSERTION DURINC THE PROPOSED LO  !

HAS BEEN MADE. THIS STUDY SHOWED THAT THE CONDITICMS THE STARTUP ACCIDENT ANALYSIS PRESENTED THE ANALYSIS SHOWS MA2ARDS

SUMMARY

REPORT - FMSR - foe STILL VALID. f7 THAT NO LOSS OF TUEL INTEGRITY R~ ULTS, IN FACT, NO CENT /.

OCCURS.

Fp" -- 'W v$ 4 %

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'o'E .INVI': YOUR ATis N110h 10 Tbi. iERY UOsSERV AY)Jta. cwSt91Dj w .c

. ASSUMPTIONS OT SECTION 12.7 THSR -

1. INITIAL POWER LEVEL IS ASSUMED TO BE ELEVEN DECADES BELOW TULL POWER . THIS IS THE EQUIVALENT OF A FULLY SHUT DOWN CORE, AND THE RESULTING ANALYSIS SHOULD BE APPLICABLE REGARDLESS OT SOURCE CONDITION.

2. SCRAM 15 ASSUMED TO OCCUR AT 125 PERCENT OF RATED NEUTRON TLUI.

IN ACTUALITY, THE REACTOR WOULD SCRAM TROM SHORT PERIOD OR AT SCRAM WOULD OCCUR MANT 125 PERCENT OF EACH PICOAKMETER SCALE.

BECADES BELOV THE 125 PERCENT OF RATED NEUTRON TLUX ASSUMED.

3. TURTHER CONSERVATISM OT THE ANALYSIS RESULTS TROM THE USE OT &

MAIIMUM VORTH ROD WHICH IS PROHIBITED BY THE CONTROL PATTERR$

UTILI2ED AND THE ASSUMPTION OF CONTINUOUS 10D WITHDRAWAL - RODS ARE J0GGED OUT DURING CRITICAL APPROACHES. .

IN PARAGRAPM 12.7.6.3 THSR, RETERENCE IS RASE TO A PRESSURE INCREASE OT LESS THAN 50 PSI IN THE NUCLEAR STIAM SUPPLT SYSTEM RESULTING FROM COMPARED TO SUCH AN ACCIDENT VITH THE REACTOR VESSEL HEAD IN PLACE.

THE NUCLEAR EVENTS, THIS IS A RELATIVELT LONG-TERM PRESSURE RISE WHICH BEGINS ATTER THE NEUTRON TLUX TRANSIENT HAS BEEN TERMINATED ST T)

DOPPLER ETTECT. IT THIS TR ANSIENT WERE TO OCCUR VITE THE VESSEL MEAB l

REMOVED, TME ENERGY PRODUCED WOULD BE RELEASED 70 THE CONTAINMENT l THROUGH DOILING OF THE COOLANT. THIS TOTAL ENERGY RELEASE TO THE l

CONTAINMENT 15 CONTAINED BT A VOLUME APPROIIMATELY 380 TIMES LA l l

THAN THE REACTOR SYSTEM AND WHICH IS DOUNDED BY MANY POTENTI AL ABf0RBING ELEMENTS SUCH AS THE CONTAINMENT SPHERE W STRUCTURES. THE CONTRIBUTION TO CONTAINMENT PRESSURE AND TEMPERAT IS, THERETORE, NEGLIGIBLE FOR THE POSTULATED ACCIDENT WITH THL Vi3SL-READ REMOVED.

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THE MAXIMUM CREDIBLE ACCIDENT WAS REANALY2ED T OF AN ASSUMED METAL-WATER REACT 10N FOR A COR THIS ANA5YSIS ZIRCALOY TVO-CLAD FUEL AND ZIRCALOY TWO CHANNELS.

EXTENDS THAT REPORTED IN SECTION 13 THSR To THE

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SPRAY SYSTEM IS UNAVAILABLE AND A[L FUEL IS CLAD l

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A ZIRCALOY-WATER REACTION TAKES PLACE WITH A C 23 PERCENT OF THE TOTAL ZIRCALOY IN THE CORE, AND THE ENTIR CONSIDERED TO MELT FROM DECAY HEAT PLUS ENERGY REA CTION.

WITH REFERENCE To FIGURE 13.1 FHSR, THE FOLLOWING RESULTS NDICATING ONLY MINOR CONTRI- i CAN BE CITED FOR THE ABOVE CONDITIONS, l

SUTIONS TO THE SEVERITY OF THE ACCIDENT THAT DO [

ALTER THE CONCLUSIONS CITED IN THE FHSR -

1. THE ADDITIONAL ENERGY CONTRIBUTION AS A RESU REACTION DOES NOT INCREASE THE CONTAINMENT PR 35 PSIA PEAV, CITED.

2. THE PARTI AL PRESSURE IN THE CONTAINMENT DUE T 0.2 PSI FOR THE PRISENT CORE CONFIGURATION OF 8 CHANNELS AND 8 ZIRCALOY TWO FUIL BUNDLES, AND IS 0 5 PSI TSR ULTIMATI RELOAD CORE OF 88 ZIRCALOY TWO CHAN TWO FUEL BUNDLES. .

3. THE RESULTING MOL TRACTION OF MfDR0 GEN To A IS 1.25 PERCENT FOR THE PRESENT CORE AND 3 PERC ULTIMATE RELCAD CORI.

THESE ARI BOTH LESS THAN THE FLAMMARILIT MOL TRACTION RATIO of APPROIIMATELY 5 PERCENT.

l A CAREFUL CONSIDERATION OF THESE00NTICUU.* TWO SETS O (5 TO CONCLUDE THAT THE PROPOSD STARTUP PROCEDUR TION DO NOT PRESENT SIGNIFICANT MAIARDS CONS OR IMPLICIT IN TIE FMSR DATID WOfEMBER $4,1961, AS AMENDED.

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O CALCULATED ROD WORTHS, A WAITING TIME WILL BE REQUIRET REFORE FURTHER -l REACTIVITY ADDITIONS. THIS WAITING TIME VILL BE APPE0IIMATELY 2 TO 3 PERIODS, WITH THE PERIOD CALCULATED TROM THE ESTIMATED VALUE OF THE e REACTIVITY ADDITION AND THE ASSUMPTION THAT THE REACTOR IS JUST CRITICAL PRIOR TO THE REACTIVITY ADDITION. THE SAME ROD SEQUENCE WILL RE USED TOR THE HEAD-ON APPROACH THAT WAS DETERMINED AS ADEQUATE DURING THE HEAD-0TT CRITICAL APPROACH.

1 DUT-0T-CORE STARTUP INSTRUMENTS WILL USE DIGITAL SCALERS To MEASURE COUNT RATES AND DETERMINE NOISE LEVEL AT THE CHAMBER FOR ALL LOW LEVEL Or ER ATING CONDITIONS .

DURING THE HEAD-ON STARTUP, REFERENCE WILL BE MADE TO MEASUREMENTS OT CCUNT RATE WHICH WILL HAVE BEEN MADE AT SMALL REACTIVITT ADDITION INTERVALS ON BOTH IN-CORE AND OUT-0T-CORE INSTRUMENTS DURING HEAD-OFT CEITICAL APPROACHES. GOOD VISIBILITY IS EXPECTED ON THE SMALL IN-CORE 1

CHAMBERS BEFORE K ETTECTIVE EQUALS 0.99.

IT THE SMALL IN-CCRE CHAMBERS DO NOT CORRELATE WITH THE READINGS TAKEN DURIN: THE HEAD-0TT CRITICAL APPROACH, THE MEASURED COUNT RATE INCREASE OF THE OUT-0T-CORE INSTRUMINTS WILL BE COMPARED TO THE PREVIOUSLY MEASURED COUNT RATE INCREASES. IN EITHER CASE, CRITERIA l l

OF ACCEPTABILITT WILL BE THE TOLLOWING -

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$ U. J O WE RN M E N T PRIN TING OF FICE: 4 96 A - 72S + 03b F 8 0M- Datt OF DOCUufNT: fivf D NO.

c Arr s c>.1.: Cr Aut 3-2-65 3 af55 DatE Tl3 1:, L.' flaucter tra uwO ee nOar. OrNta Jackson, liichigan TLil.GUE IO- On iG . C C. OTHEa i Dosn x & 1 20 cys vcrifaxed ACliON NECE55 ARY $ CONCuangNCE O D Are .N5weatD  ;

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CLA 554 .. 9051 OFFICE Fitt CODE-g,nn W55 efG NO DESCetPriON (Must Se Unclositt.ed) aEFraaED 10 Daft atCElvED ev DATE le1. in Irrly te our P-19-45 ltr req.

ad ti ir.fc in sappart cf request for b.d t 3-2 relative g'13 cye-F2 ACTIQi a

tochange low rourcetc Techlevel &:cce, dtd e1-13,he rtartu of t ENCLO50615 K:h ;. Dr. Doan (w/inio cy)

!.irtribution: 1 - forr.:.1 file (oric) 1 - suppl file ,..

1 - A!C mR 2 - Cocadiance 1 rGC 1 - L Steels 773

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