ML20209D748

Forwards Revised Tech Spec Table 15.4.1-1 Re Min Frequencies for Checks,Calibrs & Test of Instrument Channels,Specifying Required Test Periodicities for Logic Channel Testing of Reactor Coolant Flow Channel,Per NRC Request

ML20209D748
Person / Time
Site:	Point Beach
Issue date:	04/14/1987
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20209D753	List: ML20209D748 ML20209E812
References
CON-NRC-87-42 VPNPD-87-154, NUDOCS 8704290351
Download: ML20209D748 (2)

Text

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WNSCORSin Electnc m come 231 W MICHIGAN P.O box 2046 MILWAUKEE,WI53201 (414)277 2345 VPNPD-87-154 NRC-87-42 April 14, 1987 CERTIFIED MAIL Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Washington, D.C. 20555 Gentlemen:

DOCKETS 50-266 AND 50-301 MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REQUEST 115 SURVEILLANCE REQUIREMENTS - REACTOR TRIP LOGIC TESTING ON LOSS OF FLOW IN BOTH LOOPS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our letter dated January 6, 1987 requested license amendments for Point Beach Nuclear Plant, Units 1 and 2, to incorporate changes to Table 15.4.1-1, " Minimum Frequencies for Checks, Calibrations, and Test of Instrument Channels". The requested change applies to Item 5 of that table, " Reactor Coolant Flow",

and adds wording to the Remarks column which clarifies when logic channel testing for reactor trip on loss of reactor coolant flow in both loops is required to be performed.

Recently, Mr. Tim Colburn of your staff met with Mr. C. W.

Krause of our licensing staff. Mr. Colburn expressed a concern that the proposed wording of the Remarks column was confusing in that it did not mesh very well with the test periodicity specified in the " Test" column. The " Test" column specifies a monthly periodicity while the " Remarks" column calls for a refueling interval periodicity.

The confusion results from the fact that the proposed wording in the " Remarks" column applies only to logic testing for loss of flow in both loops, as opposed to loss of flow in a single loop.

Logic testing for loss of flow in a single loop does occur on a monthly basis, as dictated by the specifications. The purpose of the Technical Specification Change Request was to specify when the testing for loss of flow in both loops should occur, as this testing is not possible if the reactor power level is greater than approximately 49%.

O 8704290351 870414 PDR ADOCK 05000266 f

PDR l\

a Document Control Desk April 14, 1987 Page 2 i

I L

i As requested by Mr. Colburn, we have modified the " Test" and

" Remarks" column entries for Item 5 of this table to provide the

desired clarification. The revised wording more precisely t I

specifies the required test periodicities for logic channel testing of the Reactor Coolant Flow channel.

l In accordance with 10 CFR 50.91(a) and 50.92, we have examined this modification to our January 6, 1987 submittal and have determined that the significant hazards consideration 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 f reference and conclude that a significant hazards consideration does not exist.

Please-contact us if you have any questions concerning this request.

l l

Very truly yours,  ;-

l / .

8 C. W. Fay Vice President Nuclear Power l

l Enclosures i

Copies to NRC Regional Administrator, Office of Inspection and l

Enforcement, Region III NRC Resident Inspector R. S. Cullen, PSCW l Subscribed and sworn to before me this Jo1.h day of n$. 1987.

1 k@t MC Notary Public, State of wisconsin My Commission expires f- 2 7- 7 0 ,.

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