ML20093G333
| ML20093G333 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/12/1995 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20093G335 | List: |
| References | |
| VPNPD-95-080, VPNPD-95-80, NUDOCS 9510190022 | |
| Download: ML20093G333 (2) | |
Text
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- Wisconsin Electnc POWER COMPANY l
- 231 W Michigan. PO Box 2046. Milwaukee.WI 53201 4 046:
LG.1*^* MS VPNPD-95-080 10CFR50.4 1.
10CFR50.90 lOctober 12, 1995 l
Document Centrol Desk U.S.. NUCLEAR REGULATORY COMMISSION Mail: Station P1-137 Washington, DC 20555 Lad es/ Gentlemen:
- DOCKETS 50-266 AND 50-301 1 TECHNICAL SPECIFICATION CHANGE REOUEST 171 HEATUP AND COOLDOWN LIMIT CURVE EXPIRATION DATE EXTENSION RESPONSE TO REOUEST FOR ADDITIONAL INFORMATION POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 On May 26, 1994, we submitted Technical Specifications Change Request 171, "Heatup and Cooldown Limit Curve Expiration Date J
i.
Extension," which requested amendments to Facility Operating j
Licenses DPR-24 a"d DPR-27 for Point Beach Nuclear Plant (PBNP),
Units 1 and 2, r
actively.
T1.e proposed amendments extended the operation of bott-mits with the current heatup and cooldown limit curves in the Tect.aical Specifications to 23.6 effective full power years (EFPY).
On January 5 and April 25, 1995, in accordance K
with NRC staff's requests, Wisconsin Electric provided additional
.information'regarding this matter.. On May 11, 1995, the NRC staff i
requested additional: clarification of our submittal with respect to the neutron cross-section. library-used in supporting analyses.
This letter provides the requested-information.
In August 1995, Westinghouse! Electric Corporation issued Revision 3
-to WCAP-12795, " Reactor Cavity Neutron Measurement Program for Wisconsin Electric Power Company, Point Beach Unit 2."
This revision incorporates dosimetry results from fuel cycles 18 through 4
20, and implemented'thejlatest available nuclear cross-section data derived from ENDF/B-VI. 'WCAP-12795, Revision 3 is enclosed in support of the requested amendments.
The'results of WCAP-12795, Rev. 3 are consistent with the results determined in' Revision 2 for the PBNP Unit 2 limiting materials.
For the beltline circumferential weld (SA-1484) at 32.0 EFPY, the 2
inside; surface fluence determined in Revision 3 is 2.49E+19 n/cm g(E > 1.0LMeV).-lThis is approximately 1% less than the fluence value determined in Revision 2.
Based on our reviews, the SA-1484
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Document Control Desk October 12, 1995 Page 2 weld remains limiting for the evaluation of the PBNP Unit 2 heatup and cooldown curves.
Therefore, the heatup and cooldown limit curve expiration date in the proposed Technical Specification remains valid for PBNP Unit 2.
During the 1995 PBNP Unit i refueling outage, neutron dosimetry was removed for fuel cycles 20 through 22.
This dosimetry is currently being evaluated by Westinghouse using the latest ENDF/B-VI cross-sections.
We expect results to be available in carly 1996.
Based on the close agreement between WCAP-12795, Revision 3 with previous
. analyses, we expect the updated' Unit 1 analysis to be in close agreement with previous results.
However, if the results change the projected effective period of the heatup/cooldown limit curves
'for PBNP Unit 1, Wisconsin Electric will request the appropriate amendment.
Please contact us should you have any further questions.
Sincerely,
^
1 l.
Bob Link Vice President Nuclear Power JRP/jg Enclosure cc:
NRC Regional Administrator NRC Resident Inspector Public Service Commission of Wisconsin l
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