ML20206D303
| ML20206D303 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/07/1988 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20206D308 | List: |
| References | |
| CON-NRC-88-105 VPNPD-88-539, NUDOCS 8811170040 | |
| Download: ML20206D303 (2) | |
Text
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4 UlSCORSin Electnc POWER COMPANY 2Ji w Metcan, Po ec-204 houkes wt S3204 (414)221 2345 VPNPD 539 NRC 105 November 7, 1988 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 Washington, D.C.
20555 Gentlemen DOCKET NOS. 50-266 AND 50-301 MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REQUEST 123 REACTOR COOLANT TEMPERATURE, NUCLEAR POWER RANGE AND CONTAINMENT PRESSURE CHANNEL SURVEILLANCE TESTING tUCLEAR PLANT, UNITS 1 AND 2 POINT BEACH j Our letter dated May 24, 1988, requested changes to the Point Beach Nuclear Plant Technical Specifications regarding nuclear power range, reactor coolant temperature, and containmant pressure instrument surveillance periodicities.
In subsequent discussions regarding this request, Mr. W. Swenson of your staff indicated that the NRC technical staff has completed their review of this application and that the proposed changes have been found to be acceptable.
It was noted, however, that the channel check for reactor containment pressure, Item 18 of Table 15.4.1-1, presently is not in conformance with the recommendation of the Standard Technical Specifications (STS).
The STS recommends that this check be performed once each shift.
Mr. Swenson requested that we revise our May 24 change request accordingly.
We have reviewed this item and agree to conduct this channel check on a once per shift basis.
Accordingly, we hereby request that our May 24, 1988 license amendment application be modified to include the requirement that the channel check for Table 15.4.1-1, Item 18, Reactor Containment Pressure be conducted once each shift.
We have attached a revised page from Table 15.4.1-1 with this change.
As required by 10 CFR 50.91(a), we have evaluated this change in accordance with the standards specified in 10 CFR 50.92 to deter-mine if the proposed change constitutes a significant hazards consideration.
As stated in 10 CFR 50.92, a proposed amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not 1
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November 7, 1988 Page 2 (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
Since this proposed change would increase the frequency of channel checks on the reactor contain-ment pressure instrument from daily to once cach shift, which is a more conservative requirement, the probability or consequences of any accident is not affected.
Because this change modifies only the frequency of an instrument check, and introduces no new testing, it does not create a new or different kind of accident and no reduction in a margin of safety would occur.
Therefore, we conclude that no significant hazards consideration exists for this modification to our May 24, 1988 submittal.
Please contact us if you have any further questions concerning this request.
Very truly yours, 0
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C.W.
Fay Vice President Nuclear Power i
Copies to NRC Resident Inspector, PBNP NRC Regional Administrator, Region III i
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Subscribed and sworn to before me this 7 th day of November, 1988.
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(4, Notary Public, State of Wisconsin 1
My Commission expires P 27 '/ d