ML19254E190

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Requests Relief from Tech Specs SR 5.2.6 Re Removal & Analysis of Plateout Probe.Plateout Probe Has Decayed Due to Plant Shutdown
ML19254E190
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 10/25/1979
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Kuzmycz G
Office of Nuclear Reactor Regulation
References
P-79247, NUDOCS 7910310277
Download: ML19254E190 (2)


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Public service company oe' cdondo x 16805 Road 19 1/2, Platteville, Colorado 80651 October 25, 1979 Fort St. Vrain Unit No. 1 P-79247 Mr. George Kuzmycz, Proj ect Manager U. S. Nuclear Regulatory Commission Division Project Bhnagement Special Projects Washington, D. C. 20555 Docket No. 50-267 Subj ect: Plateout Probe

Reference:

(1) P-79028 (2) P-79040

Dear Mr. Kuzmycz:

In Reference (1) we requested relief from SR 5.2.6 of the Fort St. Vrain Technical Specifications which involved removal and analysis of plateout probe. At that time we indicated that we would fulfill the requirement of SR 5.2.6 during the next scheduled outage.

We had planned to remove the plateout probe during our scheduled outage of October 20 through November 30 of this year. As you are aware, we exparienced a forced plant shutdown on October 14, 1979, and we were not able to return to any significant power levels until October 23, 1979, and we are scheduled to shutdown on October 25, 1979, in preparation for installation of the region constraint devices.

With the extended shutdown of nine days, the platout probe has decayed sufficiently that it would require about two weeks of operation at power levels in excess of 50% to reactivate the probe to permit a meaningful analysis. In this respect, we find ourselves in a position similar to that experienced last February and are requesting relief from SR 5.2.6.

We believe that delaying the plateout probe removal at this time will have no significant impact on the healch and safety of the public based on the following:

1. The plateout probe analyses is utilized to determine compliance with LCO 4.2.8 for comparison of calculated estimates of 90Sr and the degree of conservatism for 131 I plateout assumptions. y 1245 359 E7 7910310

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Mr. George Kuzmyc:

Page Two October 25, 1979

2. At the present time, based on primary coolant analyses we are considerably lower than predicted on the circu-latory activities as follows:

Total Circulating Activity 0.027 Ci Mev/16 Tech. Spec. Allowable (LCO 4.2.8) 2.4 Ci Mev/16 Circulating Iodine Inventory 0.374 C1 131 1 Tech. Spec. Allowable 24.0 C1 1317 Circulating Strontium Inventory .33 Ci 90Sr Tech. Spec. Allowable 7.0 Ci 90Sr Iodine Plateout (calculated) 187 C1 1311 Tech. Spec. Allowable 5000 Ci 131 I/ loop Activity of Noble Gases are a factor of 2 to 4 less than predicted and factors of 20 to 40 less than the design bases used for accident analyses.

With the conservatism represented by the above comparisons, delaying the analyses of the plateout probe at this time will not have any effect on the design accident analysis or our ability to meet the requirements of LCO 4.2.8. We will reschedule the removal of the plateout probe for the next scheduled refueling.

Your immediate attention to this matter will be appreciated.

Very truly yours,

/ Y I*u Don W. Warembourg v Manager Nuclear Production DWW:dkm 1245 360