ML20002D101
| ML20002D101 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/26/1967 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML20002D102 | List: |
| References | |
| NUDOCS 8101190440 | |
| Download: ML20002D101 (2) | |
Text
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( NITED STATES
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ATOMIC EN,7RGY COMMISSION i* h I*
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I WASHING 1vN, D.C. 20545 5
May 26, 1967 pe nmv==
Docket No. 50-155 04' Consumers Power C=pany 218 West Michigan Avenue Jackson, Michigan is9201 Attention: Mr. Robert L. Haueter Assistant Electric Production Superintendent Change No. 12 License No. DPR-6 Proposed Change No.12 to the Technical Specifications of License DPR-6, Docket No. 50-155, subnitted by letter dated December 23, 1966, requests that the latest General Electric Cm pany critical heat flux (CHF) corm -
lation as presented in " Design Bases for Critical Heat Flux Condition in Boiling Water Reactors," APED 5286, be used to calcula^e limiting themal eceditions for the Big Rock Point Reactor. The new " critical Heat Fluy.
Correlation" yields, it is aported in a supplemental telegram dated February 6,1967, an overall gain of about 10 to 50% in CHF ratio, anl themfore, pmvides mom operating f]exibility in core armngement a d cycle length. Specifically, the new cormlation will pemit operation thmughout com life without the necessity to mduce power near the end of the fuel cycle in order to remain within the 1.5 MCHFR at 122% over-power. The proposed change will pemit operation at full power to the en! of the fuel cycle (com life) accmpanied by an increase of only 5%,
in peak heat flux over the mid-life peak heat flux.
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We have found that the pmposed change does not present significant hazards considerations not described or implicit in the hazards sunmary report, and there is reasonable assunance that the health and safety of the public will not be
,ered since the average heat flux and power density, 116,500 B1U/hr ft and 46 KW/ liter respectively, mmain uncharged at rated conditions. A copy of the safety evaluation report is enclosed.
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b wumers Power C.1mpany Nay26,1967
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Accordingly, pursuant to Section 50.59, 10 CFR 50, the Technical Specifi-cetions of Operating License No. DPR-6 are hentby changed as set forth in Attachment A to this letter.
Sincerely yours, i
Peter A. Morris, Director Division of Reactor Lice / sing
Enclosures:
1.
Safety Evaluation 2.
Attachment A - Change No. 12 I
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BIG ROCK POINT Tran0iento cf Resetor Sy; tem Rupture For Maxianan Credible Accident Evcluation With Metal Water Reaction 35 300 n ~ Peak =35.6 PSIA
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Dost Incident Spray System in Operation Enclosure Pressur* /]
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' Core Spray System 100
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Hottest Point, Perforation 15 $00 Volurte Per Cent M
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10 10 10 ABSTRACT FROM BIG ROCK TECH SPEC Time After Accident M eonds PROPOSAL #8 (DECEMBER 23, 1965) s u
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MAY 2 61967 t
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Docket No. 50-155 fi Consu ers Power Cortrany 218 West Michit'an Avenue Jackson, Michigan 49201 Attention: Mr. Pobert L. Hauctcr Assistant Electric Production Superintendent Change 16.12 License No. DPR 6 Gentlenen:
Proposed Chan?e No.17 to the Technical Specifications of License DPE-6, Docket No. 50-155, subnitted by letter dated Decerrber 23, 1966, requests that the latest General Electric Corr [wny critical heat flux (CHT) corre-lation as presented in " Design Bases for Critical Heat Flux Condition in Boiling Water Reactors," APED 5286, be used to calculate limiting therml conditions for the Big Rock Point Reactor. The new "
ical Heat Flux -W w-Cormlation" yields, it is mported in a supplemental.
February 6,1967, an ovemil gain of about 10 to 50%
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therefom, provides norm operating flgxibility in core armncement and s
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Specifically, the new cormlation will pemit operation cycle length.
throughout core life without the necessity to reduce power near the end of the fuel cycle in order to mmain within the 1.5 MCHFR at 122% over-The proposed change will pemit operation at full power to the power.
end of the fuel cycle (core life) accorpanied by an increase of only 5%,
l in peak heat flux over the ild-life peak heat flux.
We have fourd that the proposed chmge does not 1.=esent significant hazards considemtions not described or irolicit in the haz. mis sunerary report, and them it masonable assumnce :: hat the health and safety of the public will not be erdangered since the aserage heat flux and power density, 116,500 B1U/hr ft2 and 46 )(W/ liter respectively, remain unchanged at rated corviitions. A copy of the safety evaluation mport is ervlW.
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Consumers Pcwer Company M AY ? 61957 Accortlingly, pursuant to Section 50.59, 10 CFR 50, the Technical Specifi-cations of Operating License No. DPR-6 arv hereby changed as set forth in Attachment A to this letter.
Sincerely yours, Peter A. Morris, Director Division of Reactor Licensing Enclosurec:
1.
Safety LValuation 2.
Attachrnent A - Change No.12 DISTRIBUTION:
L. Kornblith, CO (2)
H. K. Shapar, OGC N. Dube, DRL (5)
W. B. Cottrell, NSIC Docisment Room Suppl.
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SAFLTl EVAWATION BY THE DIVISION OF REAC'IDR LICENSING CONSUMERS POWER COMPANY PROPOSED CHNGE NO. 12 DOCKET NO. 50-155 I?frRODUCTION 1he Consumers Power Ccrapany of Michigan has proposed a change, by letter dated December 23, 1966, and supplemental M dated February 6,1967, to the Technical Specifications of License DPR-6, Docket No. 50-155, issued to Consumers Power Ccunpany on May 1,1964, for the Big Rock Nuclear Ibwer Plant. This Proposed Change No. 12 would permit the use of the latest General Electric Company critical heat flux (CHF) correlation as presented in "Desikn Basis for Critical Heat Flux Condition in Boiling Water Reactors" by J. M. Healzer, et al, September.s66 (APED 5286, Part 2) instead of the critical heat flux correlation, " Burnout Limit Curves for Boiling Water Reactors" by E. Janssen and S. levy, April 14, 1962 (APED 3892) used in the original Final Hazards Sunrary Report.
The effect of this change, according to Consumers Power Cernpany would be an overall gain of furn 10 to 50% in CHF ratio resulting in more operating flexibility and cycle length. Rated power could thus be maintained over the fuel lifetime instead of reduced near the end of core life if the old correlation were to be used. (Ref Technical Specifications section 8.2.4.1).
DISCUSSION The significance of Proposed Change No.12 is illustrated in the following comparative calculations for the present core arrangement provided for Con-sumers Power Cornpany in M dated February 6,1967.
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