ML20030A455
| ML20030A455 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/03/1975 |
| From: | Lamley R, Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Muntzing L US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101090545 | |
| Download: ML20030A455 (7) | |
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January 3, 1975 N
1 DV Mr. L. Manning Muntzing Re: Docket No 50-155 Director of Regulations License No DPR-6 US Atomic Energy Commission Big Rock Point Plant Washington, DC 20545 ECCS Acceptance Criteria
Dear Mr. Muntzing:
On October 31,197h, Consumers Power Company submitted a pre-liminary evaluation of ECCS performance consistent with the requirements of Appendix K of 10 CFR 50 although not containing the full detail and documentation called for in Appendix K, along with a proposed Technical Specifications Change which would bring reactor operation into conformity with the requirements of 10 CFR 50.h6.
On November 25, 197h, we received the results of a preliminary Appendix K analysis from General Electric Company for Type F fuel. These results are more restrictive that, those presented in our October 31, 1974 evaluation and, accordingly, we hereby submit a proposed change to the Technical Specifications which would bring reactor operation into con-formance with the results of the General Electric preliminary analysis.
This proposed change applies to Type F fuel only. The changes in the MAPLHGR limits proposed on October 31, 1974 for Reload G and NFS fuel are unaffected.
Because of vacations for key personnel, the Big Rock Point Plant Review Committee has not completed its review of this proposed change. This review will be completed within the next two weeks and the results of the review transmitted to the Directorate of Licensing.
The attached proposed change to the Technical Specifications is intended to be valid until March 31, 1975, the late on which the FAC evaluation is to be submitted. Based on the SARB review performed, we believe that the Big Rock Point Plant is currently operating within this proposed Technical Specifications.
The results of the GE preliminary evaluation submitted herewith are more conservative than our previous submittals of May 30,197h and October 31, 1974, because the GE-determined maximum value of MAPLHGR of 10.2 kW/ft is lower than the MAPLHGR of those earlier submittals.
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Big Rock Point Plant ECCS' Acceptance Crii,eria-January 3,1975 In addition, the GE preliminary evaluation results are more conservative than the results of the May 30,197h submittal, even when the effect of densification on the pellet-clad gap conductance is con-sidered. This effect was analyzed with the MOXXY/ Mod hB code (described in our May 30,197h submittal) by determining the particular value of the gap conductance (uniform for all fuel rods) required to produce a peak cladding. temperature of 2300 F (IAC) for Modified-F fuel experiencing a DBA while operating at an MAPLHGR of 10.2 kW/ft, as determined by the GE preliminary evaluation.
2 A gap conductance of h50 Btu /(h ft F) is needed to make the FOXXY heatup analysis coupled with the IAC of 2300 F equivalent to the GE preliminary evaluation coupled with the FAC of 2200 F.
Since this value of h50 is lower than could reasonably be expected for Modified-F fuel at burnups of more than 12,500 mwd /MfU, it is seen that the GE preliminary evaluation result of 10.2 kW/ft is more conservative than an IAC-M0XXY analysis considering densification effects. Thus, the GE results in the attachment to this letter represent the most conservative results and the most stringent limits to date.
Yours very truly, TWC/ map Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USAEC l
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Decket No 50-155 E% QUEST FOR CHANGE TO THE TECHNICAL SPECIFICATIONS
~ License No DPR-6 For tne reasons hereinafter set forth, the following change to the Technical Specifications of License No DPR-6, issued to Consumers Power Company on May 1,196h, for the Big Rock Point Plant,-are requested:
I.
CHANGE
-Change the' table contained in Section 5 2.1(b) to read as ~ follows :
- (Table follows on next page. )
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" TABLE Reload E-G &
F. J-l & J-2 Reload G Minimum Core Burnout Ratio at Overpower 1.5*-
1 5**
Transient Minimum Burnout Ratio in Event of Loss of Recirculation Pumps From Rated Pol.er 15 15 Maximum Heat Flux at Overpower, Btu /h-ft 500,000 395,000 Maximum Steady-State Heat Flux, Btu /h-ft h10,000 324,000 Maximum Average Planar Linear Heat 7 00 Generation Rate, Steady-State kW/ft
-Stability Criterion: Maximum Measured Zero-to-PesA Flux Amplitude, Percent of Average Operating Flux 20 20 2h0 2h0 Maximum Steady-State Power Level Wt Maximum Value of Average Core Power Density at 240 W, kW/L h6 46 t
Maximum Reactcr Pressure During Power Operation, Psig 1,h85 1,h85 Minimum Recirculation Flow Rate, Lb/h (Except During Pump Trip Tests or Natural 6
6 Circulation Tests as Outlined in=Section 8) 6 x 10 6 x 10 Maximum mwd /T of Contained Uranium for an Individual Bundle 23,500 23,500 a
Rate-of-Change-of-Reactor Power During Power Operation:
Control-rod withdrawal during power operation shall be such that the average f
rate-of-change-of-reactor power is less than 50 Wt Per minute when power is t
Per minute when power is butveen 120 and less than 120 MW, less than 20 MWt 200 W, and 10 Wt per minute when power is between 200 and 240 MW -
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Based on correlation given in " Design Basis for Critical Heat Flux Condition in Boiling Water Reactors " by J. M. Healzer, J. E. Hench, E. Janssen and S. Levy, September 1966 (APED 5286 and APED 5286, Part 2).
- Based on Exxon Nuclear Corporation Synthesized Hench Levy.
- To be determined by linear interpolation from the following points:
Planai Average Exposure (mwd /T)
MAPLHGR (kW/ft) 1,250 9.h 6,250 97
'12,500 10.1
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17,500 10.2
'30,000 10.2"
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3 II.
DISCUSSION On October 31, 197h, Consumers Power Company submitted a pre-liminary evaluation of Big Rock Point ECCS performance as required by the AEC. That evaluation and accompanying proposed Technical Specifica-tions Change were based on our analysis using Interim Acceptance Criteria computer codes to determine MAPLHGR values resulting in a peak clad temperature of 2200 F for the Design Basis Accident (DBA).
General Electric Company has recently made a preliminary evalua-tion of Big Rock Point ECCS performance for GE fuel using current GE com-puter codes to give a best estimate of MAPLHGR which results in a peak clad temperature of 2200 F or. less for the DBA. As GE's results are more re-strictive than Consumers Power Company's results, GE's results are herewith submi'.ted as a proposed Technical Specifications Change, as was indicated
'in c r October 31, 1974 submittal.
The results of this preliminary evaluation represent GE's best estimate of the limiting MAPLHGR based on GE's previous experience of the effect of significant rule changes caused by the promulgation of Appendix K to 10 CFR 50.
The following changes were specifically considered:
1.
Swelling and Rupture The GE analysis shows that low fission gas release in the relatively short, low-powered fuel rods results in insufficient internal pressure to cause fuel rod perforation or significant swelling during the LOCA transient.
2.
Gap Conductance Nonuniform gap conductances for each fuel rod were used in the GE analysis.
3 Peak Clad Temperature Limit The peak clad temperature limit of 2200 F was applied in the GE analysis.
Other rule changes fran the Interim Acceptance Criteria rules, for example, spray cooling heat transfer and blowdown heat transfer, were not specifically considered because recent GE experience with other nonjet pump plant calculations has shown their effects to be negligibly small.
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l-III. CONCLUSION Based on the foregoing, the Safety and Audit Review bard has concluded that this change noes not' involve a significant hazards con-l-
sideration; CONSUMERS POWER COMPANY L
A d fzw By R. A. Lamley, Vice President
. Sworn and subscribed to before me this 3rd day of January 1975 J
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Sylvia'B'. Ball,' Notary Public Jackson County, Michigan W commission expires May 18, 1976' 1
i AEC DISTRISUTION FOR PART 50 DOCKET.iATERI AL (TET.1PORARY FOR:.1) 1 CONTROL NO:
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[ ROT.1: Consumers Power Company DATE OF DOC DATE REC'D l LTR TWX RPT OTHE Jackson, Mich. h9201 y
Ralr>h B. Sewell 1-3-75 1-6-75 u
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ORIG CC OTHER SENT AEC PDi; Mr. L. Manning Muntzing 1 signed 39 SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXX XX 40 50-155
' DESCRIPTION-Ltr re CPC submittal of 10-31-Th.E( CLOSU R ES: Request for Change to the Tech Specs for Lic. DPR-6 notarized 1-3-75....
furnishing addl info re ECCS & Proposed Change to Tech Specs.....trans the following:
SAME DISTIRELTION AS 10-31-74 SUBMITIAL (1 Orig & 39 CC rec'd)
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