ML19345A593
| ML19345A593 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/01/1966 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Coe R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011240253 | |
| Download: ML19345A593 (2) | |
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%,k UNITED STATES Formal i
ATOMIC ENERGY COMMISSION Suppl. y "E
WASHINGTON, D.C. 2?145 5,, fy f R&PRSB Reading i,,,g, #
P. E. Norian C. L. Henderson m.crov ar, '" "
NOV 1 1966 H.
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R. Haurd D. Skovolt N. D. Mason W. F. Nischan Yankee Atomic Electric Company 441 Stuart Street Boston, Massachusetts 02116 Attention:
Mr. Roger J. Coe Vice President Change No. 76 Gentlemen:
This refers to your request dated October 20, 1966, for AEC authorization of Proposed Change No. 76 in the Technical Specifications of Facility License No. DPR-3 for the Yankee reactor pursuant to the provisions of 10 CFR 50.59.
This change would authorize the irradiation in Core VI of two previously irradiated stainless steel clad fuel assemblies in place of the two zircalloy clad test assemblies that were irradiated in Core V and scheduled to be recycled in Core VI.
We have reviewed the proposed change and have found that it does not I
present significant hazards considerations not described or implicit in l
the hazards summary report, and thrt there is reasonable assurance that the health and safety of the publi. will not be endangered. A copy of our related safety evaluation is er closed.
In view of the foregoing, pursuant to Section 50.59, 10 CFR 50, Change No. 76 is hereby authorized as proposed.
Sincerely yours, 9d slped h5
. a A. Morrte j Peter A. Morris, Director Division of Reactor Licensing
Enclosure:
AEC Safety Evaluation SEE ATTACHED SHEET FOR CONCURRENCES DRL OGC DR PENorian/Itj GFHadlock R oy)
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D. Skovolt N. D. Mason W. F. Nischan Doc.2 om For al Yankee Atomic Electric Company 441 Stuart Street Boston, Massachusetts 0 16 Attention:
Mr. Roger J. Co Vice President Change No. 76 Gentlemen:
This refers to your request dated ctob 20, 1966, for AEC authorization of Proposed Change No. 76 in the T h cal Specifications of Facility License No. DPR-3 for the Yankee rea or pursuant to the provisions of 10 CFR 50.59.
This change would a h ize the irradiation in Core VI of two previously irradiated stai ess teel clad fuel assemblies in place of the two zircalloy clad est ass mblies that were irradiated in Core V and scheduled to be ecycled in ore VI.
We have reviewed the propo ed change and hav found that it does not present significant haza s considerations no described or implicit in the hazards summary re rt, and that there is asonable assurance that the health and safet of the public will not be ndangered. A copy of our related safety valuation is enclosed.
In view of the regoing, pursuant to Section 50.59, 10 CFR 50, Change No. 76 is her y authorized as porposed.
Sincerely yours, Peter A. Morris, Director Division of Reactor Licensing
Enclosure:
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SAFE'N EVALUATION BY THE RESEARCH AND POWER REACTOR SAFETY BRANCH DIVISION OF REACT (R LICENSING IN THE MATTER OF YANKEE ATOMIC ELECTRIC CG?fANY PROPOSED CHANGE NO. 76 DOCKET NO. 50-29 Introduction Pursuant to the provisions of Section 50.59 of the Commission's regulations, Yankee Atomic Electric Company, in Proposed Change No. 76, dated October 20, 1966, requested authorization to change the Technical Specifications attached as Appendix A to License No. DPR-3.
This change would authorize the irradt-ation in Core VI of two previously irradiated stainless steci clad fuel assemblies in place of the two zircalloy clad test assemblies that were irradiated in Core V and scheduled to be recycled in Core VI.
This change was requested because inspection of the test assemblies during the current shutdown indicated that some damage to the stainless steel wrappers had occurred during irradiation in Core V.
Discussion The fuel load pattern for Core VI was authorized by Change No. 74.
This change authorized the irradiation in Region A (Center) of two zircalley clad fuel assemblies that had previously been irradiated in Core V.
These test assemblics were inspected during the current shutdown to load Core VI, l
and some damage to the stainless steel wrappern was observed.
Since the cause of the damage has not yet been determined, Yankee has decided not to l
recycle these assemblies in Core VI.
Yankee has proposed to recycle two stainless steel clad fuel assemblies in place of the two previously authorized zircalloy clad fuel assemblics. These stainless steel clad am mblies were orig'nally 4.1*/. enriched, have an average exposure of appror.imately 13,700 M'.ID/T, a d are essentially identical to the two other assemblics that have been autho ized for irradiation in Region A during Core VI.
Yankee has reported the' the firadiation of these assemblies will not significantly effect the power distribution or hot channel facters previously evaluated and determined to be satisfactory for Core VI.
There-fore, we believe that the irradiation of the two stainless steel clad assemblies in place of the test assemblics will not significantly affect the safety of reactor operations.
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