ML20005G383
| ML20005G383 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/10/1990 |
| From: | Schuster T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20005G384 | List: |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 0507T, 507T, NUDOCS 9001190079 | |
| Download: ML20005G383 (2) | |
Text
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- January 10, 1990 i
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- Dr. Thomas! E.: Miirley:
Office'of: Nuclear Reactor Regulation
[U.S. Nuclear Regulatory Commission 1 Washington, DC--
20555
-Attns:' Document Control Desk M,
vt LSubject
. Byron' Station Units'1 and 2 Supplement'to: Application for Amendment
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.to^ Facility Operating Licenses Nos. NPF-37 and NPF-66 l
i NRC Docket Nos. 50-k54 and 50-455-y
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LReferences a) November 17, 1989 letter from R.A. Chrzanowski to Dr. T.E. Murley-g; 1
I DeariDr. Murley1-d q
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..In referenceL(a), pursuant to 10 CFR 50.90, Commonwealth Edison y
. proposed to' amend Appendix A,1 Technical Specifications of Facility Operating-License NPF-66._;The proposed changes to the Technical. Specifications included.
l l
' requested changes to Byron _ Unit 1 Reactor Coolant ~ System Heat-up' Limitation H
. Curve,' Figure;3.4-2a, to incorporate!a-reduced applicability limitation.
l Therefore,'we wish=to also' amend Facility Operating-License NPF-37 to include f
-the previously requested revision to Figure 3.4-2a.
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Additionally, in response to NRC questions posed during a j
l December-20, 1989 phone conversation, we wish to change the proposed change to
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- Figurei3 4-2a to' incorporate'further clarification of curve applicability.
^The calculations; performed per Regulatory Guide 1.99 Revision 2, which
..resulted inLthe: applicability < limitations to 29.5 EFPY (Reference 2), utilized
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actualucoppericontent'of 0.05 Wt. % instead of the conservative 0.1 Wt. %'of the. existing curve.
The new proposed change to Figure 3.4-2a provides further clarification of this applicability limitation. This change to Figure 3.4-2a,
[
- Tochnical Specification page 3/4 4-33, is attached.
l
- The desired changes to the amendment for Figure 3.4-2a and ref erence
'to'this am'ndment in Facility License NPF-37 have been reviewed and approved a
e Eby both.on-site and off-site review in accordance with 10 CFR 50.92(c).
The
. remainder'of;the previous submittal [ reference (a)] remains as originally requested. Since no new changes have occurred other than clarifying the
. applicability and basis of the Unit 1 curve, the original safety analysis, significant hazards evaluation and environmental assessment remain valid.
9001190079 900110
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Dr. T.E Murir,y
' 2-Jcnuary 10, 1990-o Additionally,'it is-permissible to distribute copies of the Letter h
' Report MT/ SMART-078(89) prepared by Westinghouse Electric for Commonwealth
?
Edison. The Letter Report was contained in the original' amendment submittal' of reference _(a).
s Commonwealth Edison is' notifying the State of Illinois of this supplement -to the application. for the amendment by transmitting a copy of this
. letter and its attachments to~the designated State Official.
m -.
Please direct any questions regarding this submittal to this office.
Very truly yours,
'T.K. Schuster Nuclear Licensing Administrator l :' >
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/sc1:0507T:1-2
~ Attachment
.cc : Senior Resident Inspector-Byron
.L.N.
01shan-NRR Office of Nuclear Reactor Safety-IDNS
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