ML20002C951

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Forwards Proposed Change 3 to License DPR-6,requesting Authorization to Permit Storage in New & Spent Fuel Storage Areas of Phase 2 Developmental Fuel & to Permit Verification of Fuel Upon Receipt
ML20002C951
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 04/08/1964
From: Kettner R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Case E
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101150322
Download: ML20002C951 (4)


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((>.-7 CONSUM ERS POWER COMPANY GENER AL OFFICF.S e J ACKSON, MICHIGAN

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Transrn! t ted nerevitn sr.- three (3) exacut -c er.1 nine+ een (19': aonfomed copies of Proposeo C"arpa Nc. 3 to '.he Twhat;:al Specificaticc.J inenr-porated in Provisio.ai Operatir.g License bo. DFB-6 issued to :nnsumers hver Ccopar.y or. Amas'. 30,1%2. for the Bir, Rock hint M.: lent Plant.

Proposed Cnange No.

%. s if ch is sulnittec in font.nl confimet :on of a telegraphic request of Acril 6, Iro., r idressed

  • o Mr. Rober* Lower. stein asp.s thest the Technical 3pecifications be changed to pemit t ne sic,ra6e ir. both the new snd spen + iuel storage areas of Fhose II developcental fuel preset.tly en rout s to the plant and tc pamit verification of the fuel upon rece.pt.

Tne ; rovisio.a1 Techn!0al Specific >>tions, it.clucing the char.ges herein regaested, if granted, v.ll of ccarse be sup-rseded by the Technical Specifiestions to be incorp3rstec in tha full-tem oparat ir.g license,

It v.il not t.e r.ecessery s.ceever, te c9rry these changee aver into "fcil-tem" Technieni Specifications which adequately covers the o

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CONSUMERS POWER COMPANY iA M

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Proposed Change No. 3 Qp

.A Docket No. 50-155 c.,

Consumers Power Comnany hereby requests the Commission to authorize changes, as appropriate, to the Technical Specifications incorporated in Provisional Operating License No. DPR-6, issued to Consumers on August 30,1%2, in order to permit Consumers to store and make verification checks of approximately twelve (12) developmental fuel bundles associated with Phase II of the Research and Development Program.

The following aut.horizations are hereby sought:

1.

To store in either the new fuel storage racks, described in Section h.2.11-(a) of the-Technical Specifications, or the spent fuel storage racks, described in Section 4.2.11 (b) of the Technical Speci-fications, Phase II developnental fuel as described on Pages 17 and 18 of Attachment C of Amendment No. 14, dated November 15, 1963, to Consumers' application for reactor construction permit and operating license. Phys-ics characteristics of this fuel are described on Pages 19 through 21 of

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Attachment C of Amendment No. 14. Statements in Sections h.2.11 (a) and (b) of the Technical. Specifications presently limit fuel stored in the new fuel and spent fuel storage racks, respectively, "to that described in Sections 5 and 8."

It is suggested that the authorization requested by this paragraph may be appropriately granted by referencing each of these statements to a footnote which would read as follows:

" Phase II develognental fuel described in Attachment C to Amendment No. 14, dated November 15, 1963, to Consumers I

Power Company's application for reactor construction permit and operating license may also be stored in these racks. "

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Analysis: The Phase II developmental fuel bundles vould be visually inspected upon receipt, in essentially the same manner as was used to inspect all fuel now on hand at the plant, after which they would be stored in both the new and spent fuel stcrage racks. The fuel storage facilities as described in Sections 4.2.11 (a) and h.2.ll (b) of the Technical Specifications were designed to adequately handle fuels of the type described in Attachment C to Amendaent No.14; that is, fuels capable of achieving burnup to 15,000 Mvd/ ton average. The k for the most reactive of the Phase II develo pental fuel types in the spent fuel i

storage racks is less than O.8.

Due to the larger spacing in the new fuel storage racks, the flooded k for Phase II developmental fuel stored in these racks would be even lover.

2.

To perform fuel verification checks on the Phase II developental fuel bundles by comparint the reactivity effect of each bundle with the reactivity effect of an initial core fuel bundle. Such reactivity effects would be measured within the plant reactor core utilizing conventional rising and falling period measurements.

It is requested that verification be permitted both with and without boron carbide poison rods inserted in the Phase II developmental fuel bundles. It is suggested that the authori-zation requested by this paragraph may appropriately be granted by means of a new Section 8.6 of the provisional Technical Specifications, which would read ac follows:

"8.6 VERIFICATION OF PHASE II DEVELOPMENTAL FUEL Phase II developmental fuel bundles received at the plant prior to the issuance of a full-term operating license shall be veri-fled upon receipt by comparison of the reactivity effect of each such Phase II developmental fuel bundle with the reactivity effect of an initial core fuel bundle, in accordance with written procedures. Boron carbide poison rods may be inserted in fuel bundles to be verified as desired. Boron carbide poison rods are described in Attachment C to Amendment No.1k, dated November 15, 1963, to consumers' application for reactor construction permit and operating license.

Only one Phase II developmental fuel bundle at a time vill be inserted into the array for verification.

The standard operating requirements outlined in the Technical Specifications with respect to refueli low power physics testing, etc, shall be observed. "

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Analysis: Verification of the Phase II developmental fuel bundles will generally follow the procedures previously used to verify the Phase I developmental fuel bundles and the instrumented fuel bundles. Utilizing either the present 74-bundle array, or a smaller array giving the symmetry used with the Phase I verification, each bundle vill be individually in-

.serted into one selected core location and period measurements taken. These period measurements can then be compared with period measurements from a clean original core fuel bundle.

Verification of selected bundles both with and without boron carbide poison rods inserted will provide experimental data to check cal-culated worth of the boron carbide poison rods.

Results of the verification checks on Phase I developmental fuel and instrumented fuel are shown on Page 15 of Attachment C to Amend-ment No. 14.

It is believed that the proposed changes do not present sig-j nificant hazards considerations not described or explicit in the Final Hazards Summary Report and that there is reasonable assurance that the-health and safety of the public will not be endangered.

CONSUMERS POWER COMPATE By 7

Director of Nuclear AcEivities Jackson, Michigan April 8, 1964 4,

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