ML20097D669

From kanterella
Revision as of 09:54, 1 May 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Application for Amends to Licenses DPR-24 & DPR-27, Consisting of TS Change Request 170,modifying TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review
ML20097D669
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 02/08/1996
From: Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20097D670 List:
References
VPNPD-96-010, VPNPD-96-10, NUDOCS 9602130120
Download: ML20097D669 (1)


Text

  • , *. i e-Wisconsin Electnc POWER COMPANY 231 W Michigan. PO Box 2046. Mawaukee WI 53201 2046 (414)221 2345 VPNPD-96-010 10 CFR 50.4 10 CFR 50.90 February 8,1996 Document Control Desk US NUCLEAR REGULATORY COMMISSION Mail Station PI-137 I Washington,DC 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 j TECHNICAL SPECIFICATIONS CHANGE REOUEST 170 l MODIFICATION OF TS 15.3.10. ]

" CONTROL ROD AND POWER DISTRIBUTION LIMITS" AND j TS 15.4.1 " OPERATIONAL SAFETY REVIEW" l POINT BEACH NUCLEAR PLANT. UNITS I AND 2 l In accordance with the requirements of 10 CFR 50.4 and 50.90, Wisecmsin Electric Power Company (Licensec) hereby requests amendments to Facility Operating Licenses DPR 24 and DPR-27 for Point Beach Nuclear Plant, Units 1 and 2 respectively, to incorporate changes to the plant Technical Specifications. The proposed revisions will modify Technical Specifications Section 15.3.10 " Control Rod and Power Distribution Limits," to improve the clarity of this section. A surveillance is being moved to Section 15.4.1 and a surveillance is being added to Section 15.4.1. Additionally, the guidance i contained in the Westinghouse Owner's Group Improved Standard Technical Specifications, NUREG 1431, Revision 0, was used to aid in improving the specifications that were not clear. A description of the current license condition, proposed changes, safety evaluation, no significant hazards consideration, and edited Technical Specifications pages are provided as attachments to this letter.

It has been determined that the proposed amendments do not involve a significant hazards consideration, authorize a significant change in the types or total amounts of any effluent release, or result in any significant increase in individual or cumulative occupational exposure. We, therefore, conclude that the proposed amendments meet the requirements of 10 CFR S t.22(c)(9) and that an environmental impact statement or negative declaration and envircamental impact appraisal need not be prepared.

Please contact us if there are any questions.

Sincerely, l

( l Bob Link Vice President Nuclear Power CAC/jg Enclosure cc: NRC Regional Administrator, Region 111, NRC Resident inspector 9602130120 960200 PDR ADOCK 05000266 P PDR

.4subsdm ofliinanE em Gqvatkw l

__ __