ML20094B380
| ML20094B380 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/25/1995 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| VPNPD-95-085, VPNPD-95-85, NUDOCS 9511010014 | |
| Download: ML20094B380 (1) | |
Text
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, eoWER COMPANY 231 W Mich' an, PO Box 2046.Mdwoukee W 53201-2046 (414) 221-2345 g
VPNPD-95-085 October 25, 1995 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlement DOCKETS 50-266 AND 50-301 ADDENDUM 2 TO TECHNICAL SPECIFICATIONS CHANGE REOUEST 181 MODIFICATION TO TS 15.3.1.G.3 F
REACTOR COOLANT SYSTEM RAW MEASURED TOTAL FLOW RATE POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 On September 13, 1995, we submitted Technical Specifications change Request 181 to request amendments to Facility Operating Licensea DPR-24 and DPR-27 for Point Beach Nuclear Plant (PBNP) is 1 and 2, respectively, to incorporate changes to the plant Technical Specifications (TS).
The proposed revisions modified Technical Specification Section 15.3.1.G, " Operational Limitations," Specification 3.b, to reduce the reactor coolant system (RCS) raw measured total flow rate limit for Unit 2. On October 19,1995, we submittad an Addendum to TSCR 181.
Our October 19, 1995, letter included a safety evaluation which evaluated the effects of a 4500 gpm reduction of the Unit 2 RCS flow rate limit. This evaluation assumed that operation at the conditions specified for the 4500 gpm RCS flow rate limit reduction would be limited to two cycles.
In NRC Safety Evaluations dated October 27, 1993, and October 28, 1994, the NRC staff accepted the reactor coolant systems and components evaluation for operation of PBNP Unit 2 at an average reactor coolant system temperature (Tave) of 570 F through December 31, 1996. We will continue to restrict oporation in accordance with this provision.
We have reviewed the safety evaluation and no significant hazards consideration included in our October 19, 1995, submittal and have determined that they apply to this addendum.
If you require additional information, please contact us.
Sincerely,
/
Bob Link Vice President na00110 Nuclear Power 9511010014 951025 0
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