ML20002C391
| ML20002C391 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/17/1976 |
| From: | Bilby C, Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101100237 | |
| Download: ML20002C391 (6) | |
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Company General Off*ces: 212 Vest Michigan Avenue. Jackson, Michigan 49201. Area Code 517788-0550 December 17, 1976 REGOTORY B00HI FiECOPY 3sAq 0Y QG
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Director of Nuclear Reacter Regulation
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US Nuclear Regulatory Cc=sission A
Washington, DC 20555
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C3 DOCKET 50-1,i5, LICEITSE DPR 6 -
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BIG ROCK POIUT PLA:T2 S
Transmitted herewith are three (3) originals and thirty-seven (37) conformed copies of a proposed change to the Technical Specifications for the 31g Rock Point Plant, Docket 50-155, License DPR-6.
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The purpose of this change is to keep the. MAP * :GR limits for Exxon Reload G d
and Reload G-1U fu'el consistent with updated analyses which resulted in lever MAPLEGR limits at high exposure. Events leading to this proposed change to the Technical Specifications vere reported in a Licensee Event Report to the Cc==ission dated October 28, 1976.
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CONSUMERS POWER COMPANY Docket No 50-155 f
Request for Change'to the Technical Specifications License No DPR-6 l
For the reasons hereinafter set forth, the following change to the Technical Specifications of License No DPR-6 issued to Consu=ers Power Company on May 1, 196h for the Big Rock Point Plant is requested:
I. - Change Table 2 of Section 5 2.1(b) to read as follows:
I TABLE 2 MAPLHGR (kW/Ft)
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Planar Average Exposure-F, E-G, Reload G (mwd /STU)
Modified F J-1. J-2_
and NFSDA Reload G-1U 6.453 6.h91 0
200 95 9.h 6.750 6.758 214 l
437 6.887 6.888 6 960 88h 6 978 i
885 1,758 6.929 6.970 l
1,769 3,49h 6.885 i
6 983 3,545 5,000 99 97 6.838 L
6,939 6.978 l
7,085 l
10,000 99 97 6.8hT l
10,422 T.019 i
10,690 13,938 6.867 7.069 t
ik,355 l
15,000 9.8 9.6 l
20,000 8.7 8.6 6.905 21,022 T.171 21,8h3 25,000 8.h 8.3 6.8h3 27,778 7.161 29,08h 6.703 l
3k,013 6.958 35,322 t
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II.
Change Table 8.2 in Section 8 to read as follows:
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TABLE 8.2 EEI UO -
Ceriter=elt 2
Inter-Pu02 madiate Advanced NFS-DA Minimum Core Burn ~2t Fatio at Overpower 1.5*
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1.5 Transient !!inimus Burnout Ratio in Event cf Loss ci Recirculation From Rated Power 1.5 1.5 1.5 15 Maximum riest Flux at Overpower, 402,000 Btu /h-Ft2 500,000 Maximum gteady State Heat Flux, Btu /h-Ft 410,000 500,000 500,000 329,000 (See Table 2 Maximum Average Planar Linear Heat Section 5 2.1)
Gsneration Rate, Steady State, kW/Ft Stability Criterion: Maximum Measured Z:ro-to-Peak Flux Amplitude, Percent 20 cf Average Operating Flux.
20 Maximum Steady State Power Level, W 240 240 t
Nominal Reactor Pressure During 1,335 Steady State Power Operation, Psis 1,335 Minimu= Recirculation Flow Rate, Lb/h (Except During Pu=p Trip Tests or Natural 6
6 Circulation Tests as Outlined in Sec 8) 6 x 10 6x13 Maximum mwd /T of Contained Uranium for 23,500 an Individual Bundle 23,500 Number of Bundles:
1 3
Pellet UO p
1 2
Powder UO 2
Rate-of-Change-of-Reactor Power Durin6 Power Operation:
Control rod withdraval during pover operation shall be such that the average rc.te-of-change-of-reactor power is less than 50 MWt per minute when power is 1 css than 120 W, less than 20 MWt per minute when power is between 120 and 200 MW, and 10 kW per minute when power is between 200 and 240 MW.
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g cBased upon critical heat flux correlation, APED 5286.
CONo longer used in reactor.
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III. Discussion.
Break spectrum sensitivity studies for the heatup of Exxon Reload G-3 fuel have 2 instead of the 3 926 ft2 i
indicated that the limiting break size is 0.25 ft used in previous ECC analyses of Exxon Reload G and Reload G-1U fuel. Subsequent reanalyses of the heatup of these last tvo fuel types with this change in limit-ing break size and updates in various portions of the Exxon Nuclear Co's Non-Jet-Pump Boiling Water Reactor Fuel-Heatup-Model (NJP-BWR-FEM) have provided nev
.MAPLHGR Limits versus' exposure. The new MAPLHGR limits are slightly higher at
'lov exposure and are slightly lower at exposures beyond 9,072 mwd /STO than those currently in Table 2 of Section 5.2.1(b) of the Big Rock Point Technical Specifi-cations. The revised MAPLHGR values in this proposed change to the Technical Specifications will conform with these new limits.
Updates to the NJP-BWR-FEM analysis are listed below:
(Items No 1 to IT on Pages 3 and h of XN-76-55.)
1.
Reduction of axial peaking in GAPEX from 1.5 to 1.4 to add conserva-tism and consistency with analyses for other plants.
2.
A reduction of convective heat transfer coefficient in GAPEX to estab-lish consistency with HUXY.
3 Minor changes in mixed-oxid9 veight fractions for better consistency with the fuel design reportl2).
4.
A doubling of points in the gap coefficient and hot gap versus LHGR look-up table in HUXY for improved solution convergence.
5 A reduction of HUXY time step size in the adiabatic heatup and spray cooling periods to ensure solution c nvergence.
6.
A switch after h0 seconds from the JSSS normalized power curve to the AUS curve as described in Reference 5 7
A replacement of the fuel pellet power depression versus radius table in EUXY for Reload G mixed-oxide fuel by one which may be conservatively applied to both mixed-oxide and all UO2 fuel pins in the fuel type.
8.
Application of thermal conductivity penalty to mixed-oxide fuel pins alone and not -to all fuel pins in a mixed-oxide bundle.
9 A change in the Yamanouchi canister quench algorithm in HUXY so that all parameters are evaluated relative to the input plane of interest.
This was done for SER compliance. Previously some parameters were evaluated at locations other than the plane of interest.
- 10. A correction of canister inside width from 6.h53 to 6.543 inches.
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11.
A reduction.'f initial zirc-oxide thickness in HUXY from 0.000032h inch to be consistent with most recent shop dat9 to 0.000023 3
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A change in the modeling cf inert pins from solid tire bars to cir -
clad zire bars with radial gap.
13 Increased radial noding of inert pins to ensure convergence.
14.
A change in the que"ch plane of interest frem 75% below the top of the core to mid-core to be self-consistent within the analysis.
15 An expansion of the Ellion rilm boiling 1cck-up table in HUXY to adequately cover all conditions in the Big Rock Point LOCA break spectrum.
- 16. A correction of end-of-life local peaking factors used in previous analyses.
17 An exact evaluatios of the bu..up candition associated with each MAPLHGR point.
COE E Uils POWi3 CCMFA..'Y I
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C 3 Bilty, Vice Presigd.t Production & Transmis*.on Sworn and subscribed to before te this 17th day of December 1976.
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w y7f), [' L d m d [j Linda R Thayer, I;otary Public Jackson County, Michigan My commission expires July 9,1979 f
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FlLL f.UPAL( 1 NRC, D.lCTRIBUTION Fon PAR r 50 DOCKET MATERIAL -
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Consumers Power Company 12/17/76 t
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Jac': son, Michis;an nAi t.,t ctiv t o l
Mr. Ralph B. Sc"cil 12/21/76 b TTtn
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. _. J DESenlPTION 1NCLOSURF Ltr. u/ attached....notorized 12/17/76....
/ndt. to ol/chan;;c to tech spec. to keep l
the MAPL!!CR limi ts for ':xxon Rtioad G and Reload G-1U fuel con';istant wi th upd ted f
i analyses uhich resulted in lower MAPLH:;n I
linits at high exposure.
p0 NOT REMOVE "t17 3 A nt ACKNOWLEDGED, I
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