ML20206G259
| ML20206G259 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/17/1988 |
| From: | Lippold W BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8811220184 | |
| Download: ML20206G259 (3) | |
Text
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./ N BALTIMORE GAS AND ELECTRIC
\\
CHARLES CENTER. P.O. BOX 1475 BALTIMORE, MARYLAND 21203 NUCLEAR ENGINEERING SERVICES DEPARTMENT cALysat eters wucteam Powsm Pt. ant LOSOY, WARvtAND 20657 November 17, 1988 U. S. Nuclear Regulatory Commission Washington, DC 20555 A'"TENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos, 50 317 6 50 318 Increase to Enrichment Littits
REFERENCES:
(a)
Letter, J. A. Tiernan (BG&E) to Document Control Desk (NRC), dated June 9,1988, Request for Amendment Centlemen:
This letter is in response to a verbal question from Mr.
S.
A.
McNeil, NRC Project Manager. We believe that this addresses all questions and concerns regarding Reference (a).
Reference (a) proposed changes to the Technical Specifications related to the enrichment limits for storage in the new and spent fuel storage racks. provides the additional information requested. This information does not affect the Determination of Significart Hazards Considerations as provided in Reference (a).
Should you have further questions regarding this matter, we will be pleased to discuss them with you.
l Very truly yours, l
s kgf/ uN
. J. Lippbid General Supervisor -
Technical Services Engineeritig l
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' Document C:ntral Deck November 17, 1988 Page 2 cc:
D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble/V. L. Pritchett, NRC T. Magette, DNR
e e
a ATTACHMENT 1 Item i NRC Request Evaluate the impact of the proposed increase to enrichment on the FSAR Chapter 14 safety analyses.
BG&E Response No FSAR Chapter 14 event was reanalyzed in connection with the proposed enrichment upgrade, since none of these events are directly affected by an increase in fuel enrichment.
The only issue that must be addressed to justify the proposed increase in the enrichment limit of the new and spent fuel pool storage racks is that of criticality.
This was addressed in our initial submittal.
Any indirect effects of higher enrichment, i.e., higher burnup, will be identified and evaluated during the reload enalysis performed for the cycle using the higher enrichment.
4 P
1
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