ML17199U410
| ML17199U410 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/09/1988 |
| From: | Silady J COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8803150318 | |
| Download: ML17199U410 (4) | |
Text
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y Common.Ith Edison One First Nati Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 - 0767 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 March 9, 1988 subject:
Dresden Nuclear Power Station Unit 3 Proposed License Amendment and Analysis for Cycle 11 Reload NRC Docket No. 50-249
References:
See Enclosure A
Dear Mr. Murley:
Pursuant to 10 CFR 50.90 and 10 CFR 50.59, Commonwealth Edison requests NRC Staff review and approval of the proposed Dresden 3 License and Technical Specification changes in support of refueling and startup for Cycle 11 operation (June, 1988).
These changes are contained in Enclosure E.
The reload analyses were performed by the Cycle 11 fuel supplier, Advanced Nuclear Fuels, and are discussed in several Attachments as listed in Enclosure B.
A summary of the reload design, supporting analyses, and proposed license changes is contained in Enclosure c.
We have reviewed this amendment request and conclude that* no pignificant hazards consideration exists as discussed in Enclosure D.
- Noteworthy features of the reload include:
a) use ~f ANF 9x9 fuel with axially zoned burnable absorber (Gd203).rods, b) modified limits for single loop operation based on ANF analyses, c) provisions for extended operation with a relief valve out-of-service, and d) analyses which support operation, including coastdown, with reduced feedwater heating.
Although all ANF analyses for Cycle 11 have been performed with methodologies and models previously approved by the Staff, the status of several topics from previous SERs is addressed in Attachment 5 for your convenience.
Dresden Unit 3 is currently scheduled to shutdown March 26, 1988 for the End-of-Cycle 10 refueling and maintenance outage.
Your approval of this amendment is requested by June 8, 1988 to support preparations for Cycle 11 startup.
The NRR Project Manager will be apprised of any significant schedule changes as the outage progresses.
8803150318 880309 I
I PDR ADOCK 05000249 I I
P DC:D 1:_,i
T. March 9, 1988 This amendment request has received onsite and Offsite Review approval.
The State of Illinois is notified of the proposed changes by a copy of this letter.
In accordance with the requirements of 10 CFR 170, a fee remittance in the amount of $150.00 is also enclosed.
Please contact this office should further information be required concerning this amendment.
lm Enclosures A:
B:
c:
D:
E:
Very truly yours, PC!~
. J. A. Silady Nuclear Licensing Administrator List of References List of Attachments (5)
Summary of Reload Significant Hazards Evaluation License and Tech. Spec. Changes cc:
A.B. Davis - Reg. Admin. (RIII)
M. Grotenhuis - NRR (5 copies)
NRC Resident Inspector - Dresden M.C. Parker - IDNS 4321K
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ENCLOSURE A REFERENCES XN-NF-85-67(P) (A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel", September, 1986.
ANF-87-llO(P), "Dresden Unit 3 Cycle 11 Nuclear Design Report", July 1987.
XN-NF-84-115, "Criticality safety Analysis of Dresden 2, 3 Spent Fuel Storage Pool with ENC 9x9 Reload Fuel", December 1984.
TR-BR-82-98 Revision 1, "Performance Verification of an Improved BWR Control Blade Design", by ASEA-ATOM, May 1983.
TR-VR-85-225-A, "Topical Report of ASEA-ATOM BWR Control Blades for us BWRs," OCtober 1985.
XN-NF-79-7l(P), Revision 2 (as supplemented), "ENC Plant_Transient Methodology for Boiling water Reactors", November 1981.
XN-NF-85-62, "Dresden Unit 3 Cycle 10 Plant Transient Analysis",
September 1985.
XN-NF-81-75(P), Dresden Unit 3 LOCA Analysis using the ENC EXEM Evaluation Model", November 1981.
GE document, NE00-30052, "Analysis for Operation with One Relief Valve out-of-Service for Quad Cities Units 1 and 2," dated February, 1983.
ANF document, XN-NF-84-49, "Analysis of Dresden Units 2 and 3 Operation with one Relief Valve out-of-Service," da.ted September, 1984 (enclosed as Attachment 3).
ANF document, XN-NF-85-63, "Dresden Unit 3 LOCA-ECCS Analysis MAPLHGR Results for 9x9 Fuel," dated September, 1985.
NRC Safety Evaluation for Quad Cities 1 Cycle 10 Reload (Amendment No. 103 to DPR-29) dated December 15, 1987.
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f ENCLOSURE B ATTACHMENTS
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ANF-87-097, "Dresden Unit 3 Cycle 11 Reload Analysis," September, 1987.
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ANF-87-096, "Dresden Unit 3 Cycle 11 Plant Transient Analysis,"
September, 1987.
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ANF Document, XN-NF-84-49, "Analysis of Dresden Units 2 and 3 Operation with One Relief Valve Out-of-Service", dated September, 1984.
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ANF-87-111, "LOCA-ECCS Analysis for Dresden Units During_ Single Loop Operation with ANF Fuel," September, 1987.
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Discussion of Previous SER Topics.
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