ML20198K969

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Responds to NRC 860312 Interim Rept on Util 860228 Submittal Re Reg Guide 1.97 Emergency Response Capabilities Instrumentation.Aspects of Environ Qualification Program Should Be Considered Prior to Final Reg Guide 1.97 List
ML20198K969
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 05/19/1986
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Berkow H
Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, P-86378, TAC-51092, NUDOCS 8606040177
Download: ML20198K969 (2)


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h., Public Service ~ e oo ., .

Company of Colorado 2420 W. 26th Avenue, Sui.te 1000, Denver, Colorado 80211 l

May 19, 1986 Fort St. Vrain Unit No. 1 P-86378 1

Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Emergency Response Capabilities Regulatory Guide 1.97

REFERENCES:

1) Generic Letter 82-33 (G-83009) dated 12/17/82
2) PSC Letter (P-83147),

Lee to Denton, dated 4/14/83

3) PSC Letter P-84079, Brey to Collins, Dated 3/09/84 4),PSC Letter P-85065, Warembourg to Johnson, Dated 2/28/86

, 5) NRC Letter to PSC (G-86134) Heitner to Walker, Dated 3/12/86

Dear Mr. Berkow:

Reference 5 provided an interim report on PSC's submittal (Reference

4) regarding Regulatory Guide (RG) 1.97 Instrumentation for the Fort St. Vrain Nuclear Generating Station. Several open items were identified in Reference 5 for which a response was requested at this time.

8606040177 860519 j0 DR ADOCK0500g7 ]

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P-86378 .

Page 2 May 19, 1986 Due to the integral relationship between RG 1.97 Instrumentation and 10CFR50.49 EQ Program Instrumentation / Equipment, PSC is developing the two lists containing those equipment items concurrently. At this i time, we have identified aspects of our EQ Program which should be considered further prior to finalization of our RG 1.97 list.

3 Secondly, we wish to provide you with further definition of the accidents (and resulting environments) considered in the development of our RG 1.97 category assignment and qualification level.

We consider this further definition an essential basis to the i resolution of the open items discussed above. Those responses and any appropriate revisions to our RG 1.97 submittal will be forwarded within 45 days of the date of this letter. If you have any i questions, please contact Mr. M. H. Holmes at (303) 480-6960.

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Very truly yours, 0 (Y YYinQ D. W. Warembourg, Manager Nuclear Engineering Division DWW/FWT:pa 4

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