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Discusses Recent Analysis on Effects of Reserve Shutdown Matl Present in Region 27.Potential May Exist for Operating Outside Limits.Plot Indicating Potential Reactivity Insertion Conditions Encl
	ML20027B514
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/03/1982
From:	Warembourg D; PUBLIC SERVICE CO. OF COLORADO
To:	Kuzmycz G; NRC
References
	P-82370, NUDOCS 8209210184
	Download: ML20027B514 (3)
	v • d • e

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                         .'      Public service company or cellomde

J . ' ~ i 16805 WCR 19 1/2, Platteville, Colorado 80651 i

September 3, 1982 Fort St. Vrain Unit No. 1 P-82370 Mr. George Kuzmycz 3 Nuclear Regulatory Commission , 7920 Norfolk Avenue i Betnesda, Maryland 20034

REFERENCE:

Telephone Conversation of 9-3-82

Dear Mr. Kuzmycz:

          .A   conservative ana'ysis performed by General Atomic Company on the effects of reserve shutdown material being present in Region 27 i           indicates that a potential may exist for operating in a mode outside i           the limits specified in LCO 4.1.3. Due to the flux tilt created by the suspected presence of reserve shutdown material in Region .27, the calculated reactivity worth of the control rod pair in Region 11 may exceed the maximum allowable worth as determined conservatively             ,

! by interpolation between the end of cycle values given in Figure 5.5 of the Safety Analysis Report For Fuel Reload 1 Extended Operation and those given in Figure 5-5 of the Safety Analysis Report For Fuel

Reload 2 (Cycle 3).

In view of the information above, General Atomic Company has provided to Public Service Company the attached plot which indicates the. conditions under which the potential reactivity insertion due to the withdrawal of the control rod pair in Region 11 may exceed that analyzed in the Design Base Rod Withdrawal Accident. Public Service Company intends to operate in accordance with this plot until such time as reserve shutdown material is not present in Region 27 or until a future analysis reveals another acceptable operating strategy. In addition, Public Service Company will review its operating history to determine whether past conditions could have allowed the potential for a reactivity insertion greater than that analyzed in the Design Base Rod Withdrawal Accident to exist. 820 9 21o 184 g

.g.

Of course, any deviation from the forementioned approach will be reported promptly in accordance with the Fort Saint Vrain Technical Specifications. If you have any questions, please contact me. Very truly yours, l

                                              '{     ($11i   W
                                                              /

Don Warembourg Manager, Nuclear Production DW/lsb Enclosure I

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ML20027B514

Text

REFERENCE:

Dear Mr. Kuzmycz:

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