ML17174A102
| ML17174A102 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 11/01/1979 |
| From: | Peoples D COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17174A103 | List: |
| References | |
| NUDOCS 7911060322 | |
| Download: ML17174A102 (2) | |
Text
Commonwe4t Edison One First National Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 November 1, 1979
- Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Dresden Station Units 2 and 3 Quad-Cities Station Units 1 and 2*
Proposed Amendment to Facility Operating License Nos. DPR-19, 25i 29 and 30 1 Associated with Expanding the _Power/Flow Ope~ating Region~
NRC Docket Nos. 50-237/249/254/265.
References (a):
~Load Line Limit Analysis License Amendment Subml.ttal for Dresden*
Nuclear Power Station Units 2 & 3, and Quaa~cities Nuclear Power Station
Dear* Sir:
- bnits 1 & 2 (NED0-24167, December 1978) enclosed (b) =*
"Millstone Unit 1 Loadline Limit
. Analysis," (NED0-21285-1, November 1977, Revision 1) submitted on NRC Docket No. 50-245, D. C. Switzer
- letter. t6 D. L; Ziemann dated February 15, 1978 (c): *Letter from A. J. Levin~ (GE) to
- z. R. Rosztoczy (NRCt, "Additional Effects of Core Flow on ECCS.LOCA Analysis," August 24, 1976 (d):
Letter from A. J. Levine (GE) to
- z. R. Rosztotzy (NRC), "Additional Effects of Core Flow on ECCS LOCA Analysis," November 4, 1976 Pursuant to 10 CFR 50.59, Commonwealth Edison Company proposes to amend Appendix A to Operating Licenses DPR-19, 25, 29 and 30 by incorporating the attached proposed changes into the Technical Specifications of Dresden Units 2 & 3 and Quad-Cities Units 1 & 2, respectively.
The changes (Attachments 1 through 41 will allow *reactor power ascension to proce~d ilong a modified power/flow line, which will facilitate compliance with procedures aimed at reducing fuel pellet-clad interaction.~\\..o The added operational flexibility during power ascension is ex-
~~
pected to result in significantly increased generation with
~
associated reduction in replacement power costs.
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Commonwealth Edison NRC,ocket Nos, 50-237/249 50-254/265
- 11.**
Difebtor of Nuclear Reactor Regulation November 1, 1979
- P'age 2 The FSAR and previous reload submittals for Dresden 2 & 3 and Quad-Cities 1 & 2 assumed riormai operation within the
- power/flow region below the.fi'gmina1 100% flow control line (also referred to as "lo.ad line".or "power/flow line").
Figure 2,1-3 of the Technical Specifications has, theref9re, been modified to re-flect an expanded region of the flow control map.
The new region is supported by det~iled transient and safety analyses (Reference 1, enclosed) which also considered scram and rodblock lines with a reduced slope*of 0.58.
A similar analysis was recently revie~ed and approved for Millstone Unit 1 (Reference 2) which effectively constitutes a lead plant analysis for BWR 3 class reactors.
The attached-documents have received on-site and off-site review and approval.
Based on General Electric's analyses
~f the prop6sed changes for potential impact on Scram Reactivity,
.Transients, ASME Pressure Vessel Code Compliance, Rod Withdrawal Error, Thermal Hydraulics, arid Stability (Reference 1) and previous apalyses in the areas* 6f Xenon Transients (Reference 2) and.ECCS Performance (References 3 and 4), our safety evaluation concludes that such. operation,does not involve an unreviewed safety question as defined in 10 CFR 50. 59. :
- Pursuant to.10 CFR 170, Commonwealth Edison has determined that the proposed: changes are two Class III and two Class I Amend-ments.
As such, we-h~ve enclosed a fee remittance in the amount of
$8,800.00, Three (3) signed originals and fifty-seven (57) copies of this transmittal are provided for your use, If you or your Staff have questions related to this proposal, please address them to this off ice,.
RFJ;mae attachments (4) enclosure Cll Very truly yours,
~ 1 p4F' D. L. Peoples
. Director of Nuclear Licensing