ML20137L649
| ML20137L649 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/03/1997 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | Grigg R WISCONSIN ELECTRIC POWER CO. |
| References | |
| TAC-M97837, TAC-M97838, NUDOCS 9704070279 | |
| Download: ML20137L649 (3) | |
Text
_
.o April'3l1997 Distribution
' Docket File 4
LKopp PUBLIC CGratton JRoe OGC Mr. Richard R. Urigg PD3-1 Reading ACRS Chief Nuclear Officer MShuaibi EAdensam (EGAl)
Wisconsin Electric Power Company JMcCormick-Barger, RIII 231 West Michigan Street, Room P379 Milwaukee, WI 53201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGE
. REQUEST 193, " NUCLEAR FUEL STORAGE ENRICHMENTS" - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M97837 AND M97838)
Dear.Mr. Grigg:
We have received your January 24, 1997, application to amend your technical specifications to replace the existing enrichment limits (approximately 4.0 weight percent (w/o) for standard fuel assemblies and 4.75 w/o for optimized fuel assemblies) while maintaining-the original K 'ned that additionallimits for spent fuel pool storage.
During the review, the staff deterIn#i information was required. -Enclosed is the request for additional information.
Please provide your response to these questions by May 15, 1997.
In addition, please specify any information that you believe meets the criteria that it be withheld from public disclosure pursuant to 10 CFR 2.790.
Section 2.790(b)(1)(ii) of 10 CFR Part 2 of the Commission's regulations requires that each supporting affidavit contain a full statement of the reasons on the basis of which it is claimed that the information should be withheld from public disclosure. The section further requires the statement 1
to " address with ' specificity" the considerations listed in 10 CFR 2.790(b)(4).
If.you have any questions, please contact me at (301) 415-1380.
Sincerely, Original signcxi by
. Linda L. Gundrum, Project Manager Project Directorate III-1 Division of Reactor Projects III/IV
/
,0ffice of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc w/ encl:
See next page DOCUMENT NAME: -G:\\WPDOCS\\PTBEACH\\PTB97837,RAI To receive a copy of tNo document, indicate in the bos:
~*C" = Copy without enclosures *E*' = Copy with enclosures
- N* = No copy 0FFICE PD31:PM l
PD31:LA l.
PD31:PD M j
NAME LGundrum:1g CJamersonIT/ JKannon(
DATE
(/g/97
(/F/97 Z 4 /1 /97 OFFICIAV RECORD COPY g
9704070279 970403 PDR ADOCK 05000266 p
(
o April 3,' 1997 Distribution Dock;t Fila LKopp PUBLIC CGratton JRoe OGC Mr. Richard R. Grigg PD3-1 Reading ACRS Chief Nuclear Officer MShuaibi EAdensam (EGAl)
Wisconsin Electric Power Company JMcCormick-Barger, RIII 231 West Michigan Street, Room P379 Milwaukee, WI 53201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGE REQUEST 193, " NUCLEAR FUEL STORAGE ENRICHMENTS" - POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M97837 AND M97838)
Dear Mr. Grigg:
We have received your January 24, 1997, application to amend your technical specifications to replace the existing enrichment limits,bproximately 4.0 weight percent (w/o) for standard fuel assemblies and 4.75 w/o for optimized fuel assemblies) while maintaining the original K,,# limits for spent fuel pool storage. During the review, the staff determined that additional information was required.
Enclosed is the request for additional information.
Please provide your response to these questions by May 15, 1997.
In addition, please specify any information that you believe meets the criteria that it be withheld from public disclosure pursuant to 10 CFR 2.790.
Section 2.790(b)(1)(ii) of 10 CFR Part 2 of the Commission's regulations requires that each supporting affidavit contain a full statement of the reasons on the basis of which it is claimed that the information should be withheld from public disclosure. The section further requires the statement to " address with specificity" the considerations listed in 10 CFR 2.790(b)(4).
If you have any questions, please contact me at (301) 415-1380.
Sincerely, Origimi signed by 4
. Linda L. Gundrum, Project Manager Project Directorate III-l Division of Reactor Projects III/IV f
0ffice of Nuclear Reactor Regulation i
Docket Nos. 50-266 and 50-301 cc w/ encl:
See next page s
DOCUMENT NAME: G:\\WPD0CS\\PTBEACH,\\PTB97837.RAI
- / receive a copy of this document, in cate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy 0FFICE PD31:PM l
PD31:LA l
PD31:PD lA
}
NAME LGundrum:lg CJamerson of / JH,annon(
DATE
- /g/97 Af/p/97 W 4f%/97 0FFICIAV RECORD COPY t
9704070279 970403 i
PDR ADOCK 05000266 p
w-a.
l 4
Mr. Richard R. Grigg Point Beach Nuclear Plant Wisconsin Electric Power Company Unit Nos.-1 and 2 cc:
Ernest L. Blake, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, DC 20037 l
Mr. Scott A. Patuiski Vice President 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 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road i
Two Rivers, Wiscor, sin 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin l
P.O. Box 7854 Madison. Wisconsin 53707-7854 i
bearch 1997 P
4 REQUEST FOR ADDITIONAL INFORMATION POINT BEACH TECHNICAL SPECIFICATION CHANGE REQUEST 193 SPENT FUEL ASSEMBLY ENRICHMENT 1.
Provide a summary of the results of the September 1996, blackness tests at Point Beach including the number of Boraflex panels tested, number of gaps identified, gap sizes, and gap distribution.
2.
Provide a copy of Westinghouse criticality analysis CAA-96-146.
i 3.
Please explain the statement included in the No Significant Hazards Analysis that "The proposed changes do not involve a change to plant design."
4.
Please provide information on planned changes in burnup to accommodate the 18-month cycle and any effects on spent fuel pool cooling capability.
I s
i i
ENCLOSURE l