ML20128H255
| ML20128H255 | |
| Person / Time | |
|---|---|
| Site: | Point Beach |
| Issue date: | 10/07/1996 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | Link R WISCONSIN ELECTRIC POWER CO. |
| References | |
| IEB-96-001, IEB-96-1, TAC-M95040, TAC-M95041, NUDOCS 9610090289 | |
| Download: ML20128H255 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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Mr. Robert E. Link, Vice President Nuclear Power Department Wisconsin Electric Power Company 231 West Michigan Street, Room P379 Milwaukee, WI 53201
SUBJECT:
NRC REVIEW OF SEPTEMBER 20, 1996, AND OCTOBER 2, 1996, SUPPLEMENTAL RESPONSES TO NRC BULLETIN 96-01, " CONTROL R00 INSERTION PROBLEMS" -
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M95040 & M95041)
Dear Mr. Link:
We have received your supplemental response to NRC Bulletin 96-01, " Control Rod Insertion Problems," dated September 20, 1996, for the Point Beach Noclear Plant.
In this letter you advised NRC of your intention to revise your commitment to perform EOC control rod drop testing and B0C drag testing during the upcoming Point Beach Unit 2 refueling outage. This commitment was part of your response to the subject bulletin. At the staff's request, you submitted additional information by letter dated October 2,1996.
Wisconsin Electric's revision was based on the assertion that "the NRC staff has received significant data on this particular fuel type," which is 14x14 Westinghouse Optimized Fuel Assemblies (OFA). While the staff has reviewed the summary of rod drop data as presented in Figure 1 of 0G-96-069, only one set of data comparing BOC and E0C rod drop times for 14x14 0FA fuel has been submitted and that was for a plant operating at a lower temperature than the Point Beach units. The staff is continuing to review the relationship between B0C and E0C rod drop times and incomplete control rod insertion. Thus, the staff still considers the control rod drop test at E0C to be essential.
With regard to the drag testing, the majority of the fuel assembly burnups for Point Beach Unit 2 Cycle 23 are enveloped by the data submitted for the Point Beach Unit I drag tests. The fuel assemblies in Unit 2 with burnups between 20,000 MWD /MTU and 40,000 MWD /MTU are not covered by the previous data and
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should still be drag tested at BOC Cycle 23.
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3C 3.E CBITER COPY 090064 9610090289 961007 PDR ADOCK 05000266 G
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4 If you have any questions, please contact me at (301) 415-1390.
You may also directly contact Margaret Chatterton at (301) 415-2889, Larry Kopp at (301) 415-2879, or Kris Thomas at (301) 415-1362.
Sincerely, OriginalSigned by
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Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page DJstribution
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Mr. Robert E. Link, Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company Unit Nos. I and 2 cc:
Ernest L. Blake, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mr. Gregory J. Maxfield, Manager Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 i
Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4531 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Ma.dison, Wisconsin 53707-7854 l