ML20024G047
| ML20024G047 | |
| Person / Time | |
|---|---|
| Site: | Monticello |
| Issue date: | 04/13/1976 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Mayer L NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20024G048 | List: |
| References | |
| NUDOCS 9102070463 | |
| Download: ML20024G047 (2) | |
Text
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fjBISTh. dlTION d
NRC PDR jJ Local PDR Docket ORB #2 Reading KRGoller TJCarter Docket No. 50-263 APR 1 a 1976 DLziemann RPSnaider RMDiggs Northern States Power Company OELD l
ATTN:
Mr. L. O. Mayer, Manager 016E (3)
Nuclear Support Services VStello 414 Nicollet Mall - Eth Floor TBAbernathy Minneapolis, Minnesota 55401 JRBuchanan ACRS (16)
Gentlemen:
11 : Change to Bases
\\
In a letter dated March 12, 1975, you requested several changes to the Technical Specifientions for the Monticello Nucient Generating Plant.
A.,c ndu er.t 14, dated October 30, 1975, responded to all items of your recaert with the exception of ite*::s 3, 4, and 5 which concerned changes to 1
the technical specification bases to delete obsolete information, to correct errors, and to incorporate changes reflecting the adoption of the General Electric BVR Thermal Analysis Basir (GETAB).
tc hn e rc 'c i nt: the proposca changes and conclude that:
1.
The deletion of bases information rel8 ted to a reporting requirenent i
("Sunuary Status of Eucl") v:hich was eliminated as part of License AuenJc:ent No. 15 dated January 22, 1976, is acceptabic.
2.
The correction of the hirh steam. flow retpoint of the Reactor Cra e Isob tion Coolin;' (' CIC) systen fmn 1504, as originally shown, to 300*,, is required to make the bates consistent with the applicable i.
specification (Table 3.2.1) and is therefore acceptable.
j 3.
The chan; es to the I ases for Section 3.2 to incorporate the new ter,1-nology associated with GETAb ("inirum Critical Power Ratio (MCPR) i ir. stead o' ':inin;" Critical Feat riux Ratio ("C!<TR)] and the related chanRes referencing the Safety Limit of Technical Specification 2.1.A are ccecptable.
Revised pages 16 nnd 67 incornorating the above bases changes are enclosed.
Sincerely, hg Dennis L. Ziemnn, Chief Operating Reactors Branch # 2
(
'g Division of Operating Reactors
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