ML20039B295
| ML20039B295 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/15/1981 |
| From: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20039B291 | List: |
| References | |
| NUDOCS 8112220499 | |
| Download: ML20039B295 (5) | |
Text
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CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it 4 requested that the Technical Specifications contained in the Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 1964, for the Big Rock Point Plant be changed as described in Section I below:
d I.
Changes Section 5.2.1(b) - Table I Change the column headings on Table I of Section 5.2.1(b) to read:
" Reloads:
Reload Reload F & Modified F Reload G G-1U G-3/G-4/H-1/H-2" Section 5.2.I(b) - Table II Replace Table 2 of Section 5.2.1(b) with the new Table 2 attached.
oc1281-0009a142 8112220499 811215 PDR ADOCK 05000155 P
TABLE 2 MAPLHGR(KW/FT) LIMITS Planar Average Er osure Reload Reload-Reload Reload (MWD /STM.
Modified F Reload F Reload G G-1U-G-3/G-4/H-1 H-2 0
7,0 200 360 I
g i
1,000 SameaspreseEttech. specs.
7.8 1,630 3,810 3,900 5,000 6,440 6,620 7.48 10,000 12,880 13,520 13,610 15,000 19,050--
20,000 20,320 7.56 20,870 24,580 25,000 26,400 7.32 26,760 28,210 30,000 31,210 6.73 32,000 33,020 33,380 6.69 34,000 34,470 36,000 36,290 oc1281-0009a142
II Discussion The above proposed Technical Specifications changes are requested to implement reactor operating limits for Reload H-2 fuel which are based on the Loss of Coolant Accident (LOCA) Analysis required by 10 CFR 50.46.
The maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits for Reload H-2 are based on the LOCA analysis submitted by Consumers Power Company letter dated March 7, 1979 (Exxon Nuclear Company (ENC) Report XN-NF-78-53).
The MAPLHGR limits were derived in a manner identical to that described in ENC Report XN-NF-79-21, Revision 1, " Big Rock Point LOCA Analysis Using the Exxon Nuclear Company WREM NJP-BWR ECCS Evaluation Model - MAPLHGR Analysis" which was submitted by Consumers Power Company letter dated February 25, 1980. On the basis of these two submittals the NRC staff previously issued Amendment No 44 to the Big Rock Point Operating License which revised MAPLHGR limits for.
all fuel supplied by ENC to that point in time.
Reload H-2 is identical to Reload G-3 in all respects, except as described below.
Figure 1 (attached) shows the fuel rod arrangement for H-2 fuel. The l
differences between H-2 and G-3 are:
1.
Reload H-2 is of a higher average enrichment (3.43 w/o U-235) as compared to Reload G-3 (3.14 w/o U-235) in order to achieve a desired reload discharge burnup of 23,400 MWD /STM, 2.
The four gadolinia bearing fuel rods have been relocated from the
[
bundle centerline to three rods in from each corner, and 3.
The gadolinia content of the gadolinia bearing fuel rods is higher (1.5 w/o Gd 0 r H-5 C mPared to G-3 (1.2 w/o Gd 0 }*
23 23 The increase in enrichment from G-3 to H-1 fuel raises no new safety issues, as fuel with initial, enrichments up to 3.88 w/o (fuel type G1-U) is currently being used at Big Rock Point.
In addition, these minor differences have no effect on the thermal hydraulic design basis for ENC fuel. Although the changes have a small effect on local peaking factorc, the design local peaking factor of 1.20 for an unrodded bundle which was used in establishing the thermal margin (MCHFR) limit is not exceeded.
The change in local peaking factors has a minor effect on the ECCS performance for H-2 fuel. The change is such that LOCA peak cladding temperatures and ECCS MAPLHGR limits are adversely affected for H-2 as compared to G-3 at low bundle burnups (below 6.6 GWD/STM). This effect is largely eliminated as the fuel is burned, and therefore at higher bundle exposures the MAFLHGR values for H-2 fuel are identical to those for G-3 fuel. These effects are illustrated by comparing the last two columns of the proposed Table 2 of the Technical Specifications Section 5.2.1(b).
oc1281-0009a142
@@@@O@@@@@@
fD @@ @@ @ @@ @ @ @9 Number of Rods Description
(=:=Z
)
3 Inert Rods 12 1.66 wt% 235U 40 2.79 wt% 235 U 61 4.24 wt% 235U 4
2.79 wt% 235 U l. 50 wt% Gd 0 2 3 12 Tie Rods l
Inert Spacer Capture Rods Figure i Fuel Rod Arrangement - Big Rock Point F.eload H-2 t
l
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' i III.
Conclusion Based on the foregoing, both the Big Rock Point Plant Review Committee
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and the Safety and Audit Review Board have reviewed these changes and find them acceptable.
CONSUMERS POWER COMPANY x
By.
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R B DeWitt,'Vice President "i
Nuclear Operations
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I Sworn and subscribed to before me this 15th day of December 1981.
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Helen I Dempski, Notarf Public Jackson County, Michigan
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1 My commission expires December 14, 1983.
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