ML20215G848

From kanterella
Jump to navigation Jump to search
Forwards Proposed Rev to Tech Spec 15.5.3.A.1, Reactor Core General, Addressing NRC Concerns Over Wording in Tech Spec Change Request 117 to Licenses DPR-24 & DPR-27 Re Fuel Rod Substitution in Fuel Assemblies
ML20215G848
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 04/10/1987
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20215G851 List:
References
CON-NRC-87-43 VPNPD-87-158, NUDOCS 8704170298
Download: ML20215G848 (2)


Text

r o ')V '

l Wisconsin Electnc eomcoupw 231 W. MICHIGAN, P.O. 8OX 2046, MILWAUKEE, WI 53201 (414) 221-2345 VPNPD-87-158 NRC-87-43 April 10, 1987 CERTIFIED MAIL U. S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.

C.

20555 Gentlemen:

DOCKETS 50-266 AND 50-301 MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REQUEST 117 FUEL ROD SUBSTITUTION IN FUEL ASSEMBLIES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our letter dated March 12, 1987, requested license amendments for Point Beach Nuclear Plant, Units 1 and 2, to incorporate a change to Technical Specification 15.5.3.A.1, " Reactor Core General."

The proposed change modifies the specification addressing the substitution of fuel rods suspected of being damaged.

With this change, the specification would allow substitution of damaged fuel rods by inert rods or by vacancies if justified by a cycle specific reload analysis.

Subsequent to our submittal, the NRC staff expressed concern over the wording of our proposed specification.

The attached proposed revision addresses the NRC staff concerns.

In accordance with 10 CFR 50.91(a) and 50.92, we have examined this modification to our March 12, 1987, submittal and have determined that the significant hazards considerations evaluation presented in our original amendments request is unchanged and equally applicable to the specification revision discussed herein.

Accordingly, we hereby incorporate that evaluation by reference and conclude that a significant hazards consideration does not exist.

8704170298 870410 PDR ADOCK 05000266 P

PDR g

0 0g

\\

,p NRC Document Control Desk April 10, 1987 Page 2 Please contact us if you have any questions concerning this request.

Very truly yours,

(

[?N c C. W.

Fay Vice President Nuclear Power Enclosures Copies to NRC Regional Administrator, Region III NRC Resident Inspector R. S.

Cullen, PSCW Subscribed and sworn to before me this lo d-day of April 1987.

Yc e%)

M Notary Public, State hF Wisconsin My Commission expires 5[27!9d

.