ML17199F793
| ML17199F793 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/03/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8606110100 | |
| Download: ML17199F793 (4) | |
Text
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3 1986 Docket No.:
50-249 DISTRIBUTION
~:;;::J)J) G-ket-=N o:~_:_:SO~ 2 491 NRC PDR Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear~Mr. Farrar:
';1
,f*'suBJ~CT :~ REQUEST FOR ADDITIONAL INFORMATION - DRESDEN 3
- {*,..-:,' CYCLE 10 RELOAD
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Dresden Nuclear Power Station, Unit No. 3
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.. BWD-1 r/f RBernero Attorney, OELD EJordan BG rimes JPartl ow*
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- .~')By~ a*:lett¢.r.dated February 21, 1986 as supplemented by a letter dated
. *:*: (.:;.t, "Apri.L f?, 1986,.you transmitted a request for, information relating to,
- * :; :, :-.a Techni,c.al Specification amendment for the Dresden 3 Cycle 10 Reload.
The
, : t;,,.~ ~*.:. *'staff-'h'as*.reviewed this material and find that we need the information
- ~,, *
<<reque.st~d in the enclosure in order to complete our review regarding your.
~
amendm~nt req~est. Please respond to this request promptly so that the staff *
- ; *~
1
' calf complete the review in time to meet your present schedule for restart
- Th"~"~eporting and/or'recordkeeping requirements contained in this letter affect fewer than ten respondents.
Therefore, OMB clearance is not required
.under.P.L.96-511.
Enclosure:
Request for Additional
- Information cc w/enclosure:
See next page S i*ncere l y,
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Director WR Project Directorate #1 Division of BWR Licensing ki
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8606110100 860603 PDR ADOCK 05000249 PL ____ '<
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Mr. Dennis L. Farrar Commonwealth Edison Company cc:
Mr. Michael I. Miller Isham, Lincoln & Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602 Mr. Doug Scott Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Commission Resident Inspectors Office Dre!>den Station Rural Route #1 Morris, Illinois 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Nuclear Regulatory Commission, Region III
.799 Roosevelt Road Glen Ellyn, Illinois 60137 Gary N. Wright, Manager Nuclear Facility Safetv Illinois Department. o{.Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Dresden Nuclear Power Station Units 1, ? and 3
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE DRESDEN UNIT 3 CYCLE 10 RELOAD. AMENDMENT COMMONWEALTH EDISON COMPANY '
DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 DOCKET NO. 50-249
- 1.
A supplement to the propos~d license amendment for the Dresden 3 Cycle 10 reload was provided by the '.licensee by letter dated April 18, 1986.
An additional change was proposed to incorporate LHGR limits for EXXON 8x8 and 9x9 fuel as a Limiting;Condition for Operation (LCO).
In its review, the NRC *staff noted that two topical report references were used which may no longer be valid. Specifically, we understand that Exxon's Generic Report XN-NF-81-21, Revision 2 has been withdrawn by the vendor. This affects the validity of the 8x8 LHGR data.
In the Figure 3.5-lA provided in the supplemental submittal, the curve for the ENC 8x8 fuel does not conform to the LHGR limit curves presented in both Topical Report XN-NF-81-21, Revision 1 and XN-NF-81-21, Supplement 1.
Please clarify the reference to the 8x8 data and provide an explanation of any
- deviations of the 8x8 curve in Figure 3.5-lA from that given in the applicable Exxon Topical R~port.
- 2.
Figure 3.5-lA of the April '18, 1986 submittal should be clarified in the following area:
1 The terminology "nodal exposure" appears to be incorrect when related to the report XN-NF-81-67 (Rev. 1) Figures for ENC 9x9 fuel.
Please provide a corrected Figure.
In addition, the staff notes that the 8x8 LHGR limit curves presented in XN-NF-81~21, Rev. 1 and Supplement 1 thereto were in terms of peak:pellet exposures whereas the exposures
.. in Figure 3.5-lA appear to be in terms of planar exposure.
Provide the peaking factors used to convert the peak pellet exposures to planar exposures.
- 3.
- The second reference in the Supplement does not specify the revision number of the Exxon Generic Report XN-NF-85-67.
The licensee should confirm that the latest version is applicable to Dresden 3 Cycle 10.
The NRC is basing its review o~ Revision 1 and considers Revision 0 obsolete.
- 4.
The licensee has identified ENC Topical Report XN-NF-524(P)(A) Revision 1, "EXXON Nuclear Company ~ritical Power Methodology for Boiling Water Reactors", November 1979 as the methodology used to determine the Minimum
. Critical Power Ratio (MCPR). safety limit for the D3C10 reload. This same
/*
- methodology was used in the previous Dresden 3 Cycle 8 and 9 reload analyses.
The NRC Safety Evaluation Report (May 1983) on this methodology specified certain restrictions on its use which dealt with.the method of accounting for uncertainties in parameters associated with the thermal margin calculation, the use of a Monte Carlo technique and the fitting of a Pearson curve to the resultant distribution. The Dresden Unit 3 Cycle 10 Plant Transient Analysis Topical Report XN-NF-85-62 identifies the main input parameters and uncertainties used in the safety limit analysis*
for the D3C10 reload application. The licensee should verify that the
. contingencies identified in the staff SER on XN-NF-524, Revision 1 have been suitably accounted for in the application of the methodology.