ML18347A550

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Referring Report Transmitted on 9/15/1976, Analysis of Relative Probability of Failure at Various Locations in Primary Cooling Loop of Pressurized Water Reactor....., Advising Failure of Reactor Coolant System Is Acceptably Small
ML18347A550
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/12/1976
From: Bixel D
Consumers Power Co
To: Schwencer A
Office of Nuclear Reactor Regulation
References
SAI-001-PA
Download: ML18347A550 (1)


Text

consumers Power company Director of Nuclear Reactor Regulation Att:

Mr Albert Schwencer, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET.50-255 - LICENSE DPR PALISADES PLANT - VESSEL TRANSIENT LOADS

I F COP'l By letter dated July 28, 1976 we advised you that the results of a probability study concerning vessel transient loads would be submitted formally in August 1976.

This letter is to advise you that this study h~s now been formally sub-mitted.

The report was submitted by letter to Karl Goller from R C Erdmann dated September 15, 1976.

This letter transmitted a report titled "An Analysis of the Relative Probability of Failure at Various Locations in the Primary Cooling Loop of a Pressurized Water Reactor Including the Effects of a Periodic Inspec-tion" (Report No SAI-001-PA).

The report was prepared by Science Application (SAI) and is dated June 1976.

As stated previously, we conclude, based on the above-referenced report, that the probability of a failure of the reactor coolant system in* the annular region between the reactor vessel and the cavity shield wall is acceptably small.

David A. Bixel Assistant Nuclear Licensing Administrator CC:

JGKeppler, USNRC 10439