ML20037B025
| ML20037B025 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/14/1965 |
| From: | Bower D COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| NUDOCS 8009030706 | |
| Download: ML20037B025 (7) | |
Text
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April 14, 196 /f L -u.t: :
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Dr.
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L. Doan, Director Division of Reactor Licensing Y*/
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U. S. Atomic Ener.a,y Commission
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'fashington, D.C. 20545 Docket: 50-10 nc a r.u n 3
Subject:
Amendment of Appendix A,,DPR-2 to authori
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operation with Type PF-10 Fuel Assembly modified. (Change No. 11)
D_ ear Dr. Doan:
4 Pursuant to 10 CFR 50.59 and Paragraph 3.a.(4) of License DP'l-2, as amended ("DPR-2"), Commonwealth Edison Company respectfully requests that Appendix " A" of DPR-2 be amended to authorize the operation with a Type PF-10 fuel assembly, modified.
The amendments
. ire as follows:
Amendment No. 1 Amend item "2.
Nuclear Core" of section "3.
DESIGN FE ATURES" or Appendix " A" to DP'l-2 to read in its entirety:
"2.
Nuclear Core
" Maximum core diameter (circumscribed circle) 129 in.
Maximum active fuel length - cold 112 in.
Maximum number of fuel assemblies by types:
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~%,._x.Q g - C )W Type I 263 g
/S Type II 102 a qJ e,s
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Type III 192 jy !
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Type III-F 104
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Type PF-10, modi fled 1
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Type PF-11 1
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Type SA-1 1
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sS kgp Maximum total number of fuel assemblies 4S8 "The fuel assemblies may be located in any position of the reactor, provided that fuel assemblies Type PF-10, modified, and'PF-11 are each separated'from the other by at least i
four Type I, Type II, Type III, or Type III-F fuel assemblies.
"The reactor may be operated at any power up to and including rated power with any configuration of the various types of fuel assemblies installed, provided 1
the ifaits the maximum number and location ar "e i
specified above."
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pr..R. L. Dacn paga 2 Apt]14, 1965 Amendment No. 2 Amend item "3.
Determination o f Maximum Reactor Power" of section "D.
POWER OPERATION" ot Appendix "A" to DPR-2 to read in its entirety:
"3.
Determination of Maximum Reactor Power "The rated power of the reactor shall be limited to a maximum steady state value of 700 MW(t).
"Themaximumallowablesteadystageheat flux limits
[
expressed in units of atu/(hr)(ft ) shall never exceed the following values:
Fuel Type I 350,000 Fuel Type II 410,000 Fuel Type III 360,000 Fuel Type III-F 360,000 Fuel Type PF-10, modified 510,000 Fuel Type PF-11 510,000 Fuel Type SA-1 425,000 "The reactor shall be operated within the above linits such that a minimum burnout ratio of at least 1.5, evaluated at 125 percent of rated power, will be maintained in each type of fuel closest to burnout in tho hottest channel in the core based on a uniform steam quality over the cross section of the channel.
This burnout ratio shall be based upon the correlation in Edison's " Recommended Curves of 3urnout Limit for Design and Operation of 3 oiling Nater Reactors," dated January 5, 1962.
The reactor shall be operated always well within the bounds of stability, as evidenced by the operation itself and any experimental data produced."
Amendment No. 3 Amend Appendix "A" to DPR-2 by deleting TABLE II (revised 11-13-64) attached thereto and substituting TABLE II (revised 4-14-65) attached herewith.
Pursuant to 10 CFR 50.59 and 3.a.(4) of DPR-2, a Description and Evaluation report (in the form of a letter to H.
K. Hoyt, Commonwealth Edison, from T. Trocki, General Electric) presents the salient factors) in support of these proposed amendments to Appendix "A" is attached hereto designated as " Exhibit I",
as well as a revised Table II, which reflects the Type PF-10 fuel assembly modification.
In our opinion the data in this document indicates that operation of the Type PF-10 fuel assembly, as modified, in the Dresden reactor will not present significant hazards considerations not described or implicit in the hazards summary and that there is reasonable assurance that the health and safety of the public will not be endangered.
In the event additional information is deemed necessary to expedito your review and deliberations in this matter, please call I
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Dr.
R. L. Dean Page 3 April 14, 1965
- se at 312 (area code) RAndolph 6-1200, Extension 3631, or $8r. John H.
!!ughes of my staf f.
Very truly yours, COVMONWEALT!! EDISON COMPANY t
3y Treasurer SUBSCRI3ED and sworn to before me this 14th day of April, 1965 0) t.e4 pry l'ubite Attachments:
Revised Tabic II and Exhibit I i
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TAME II (Revised 4/14/65)
Eegut Claadinc Wall 0.D.
'rni.chne ss Rod Number 1 Fuel f
Fuel Type Material (inchen)
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Cor. figuration Ee quired Co ::pocition I
Zr-2 0.>67 0.030 6x6 36 100 002 II 304 SS 0.441 0.019 7x7 LO 100 %%
0.035 99.85 002 6x6 31 0 15 Er2 3 0
III Zr-2 0 5M o,oSS.
29 100 002 III-F Zr-2 0 5625 0.035 6x6 95 3 Al 03 2
1**
4 7 Od 023 28 100 002 95 3 ^1023 Zr'2 0 5625 0.035 6x6 1
4.7 cd 023 III-F (Powde r) 1***
100 002 99*
PF-10 Zr-4 0.412 0.025 8x8 54 0 35 Er2 3 0
PF Zr-4 0.412 0.025 8x8 55 100 002 SA-1 Zr-2 0.M!4 0.022 7x7 25 100 U02 Five Corner Rods Poison Rod - Fellet Spacer Capture Rod - Pell'et
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,e P
r Bods Special Corner Rods
% 002 Fuel Nurmer
% Fuel
% Uo2 Fuol Enrichment Dia:ne te r Required Co::iposition Enrien wn:
Dias tar 15 0.498
-r 2.1 002 25 0 399 9
97 9 Tho2 93 5 0*399 99.85 LO2 1.83 0.438 1.03 o.k78 5
0.1s Er2 3 0
34 0.482 6
100 002 1 77 0.482 2 34 0.4925 o.465 6
100 002 1 77 o.4925 2 34
- 0. @
(3fg 1.5 o.358 2.0 0 358 9
1.8 002 93 5 0 358 2.0 0 358 9
98.2 Thoa 30-35 0 375 24 loo 002 2 76 o.375 l
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EXHIBIT I DESCRIPTION AND EVALUATION REPORT Type PF-10 Fuel Assembly Modification April 12,1965 Mr. H. K. Hoyt Superintendent Dresden Nuclear Power Station R. R. #1 Morris, Illincia 60450
Dear Mr. Hoyt:
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SUBJECT:
Removal of a Rod From Fuel Assembly PF-10 It is proposed to rersove a single rod from fuel assembly PF-10 for isotopic and mats 11egraphic emmination. The rod will be removed by cutting the 4 webs of the upper tie pists which permits the selected rod and its associated section of the upper tie plate to be withdrawn through the upper tie plate.
The red to be removed is from the central region of the bundle. The remainder of the bundle will not be affected mechanically. The bundle will be inspected
- wit.h an underweter borescope to verify its mechanical suitability.
j The effect of the absence of this rod on fuel performance has been estiasted.
An increase in local power peaking of 10 percent is estimated in the rc,ds adjacent to the removed rod. Even with this increased peaking, these roda do not exceed the peak in the cornar rods. Thus, the " bot" roda in the bundle are the same as before the alteration.
The removal of one rod causes some bypassing of flow from the other rods in the. assembly. The reduction in flow is consertatively calculated to be approximately 10 to 15 percent. This reduction in flow results in a change in burnout ratio frca 3.1 to 2.85 at 125 percent overpower.
On the basis of thesa calculations, it is concluded that the performance of the altered fuel bundle is not significantly affected and remains well within operating limits.
W C)
A Thomas Trocki A temic Power Equipment Department Generst Electric Company in the region of alteration, i.e.
the upper tie plate.
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B. T. Cox R. J. Ascher1 L. A. Steinert W. R. Kanne D. T. Weiss H. E. Williamso' n TT:jn
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DOCIEE NO /
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Subject:
Asseedsment of AM4v A, a rd:
4-16 a
i a to asthorize operati a v
PF-10 Fast A=:-Ny w/d Mr>MR.6 mrdified, (Change No.11) j (2:lEARD2D 4-14-63)
Dr.. Can v/ info cy)
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