ML20207R062
| ML20207R062 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 02/27/1987 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20207R063 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 2793K, NUDOCS 8703110144 | |
| Download: ML20207R062 (2) | |
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b.
i One Phe Ndond Resa, CNoego, Mncie t
-(v) asmens Mapsy to: Pos anos som is7 CNeage,MnoisGONO 0787
't February 27, 1987 c
i Mr. Harold R. Denton, Director office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Ceaunission Mashington, DC 20555 I
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subjectt tyron station Units 1 and 2 i
Braidwood station Units 1 and 2
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Regulatory Guide 1.97 Compliance
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preliminary Report 4
IRC Docket Mos. 50-454/455 and 50-456/457
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References (a)
Cordell Reed letter to H. R. Denton dated i
April 14, 1983 i
(b)
Byron Unit 1 License No. WPF-37 Condition 2.C.(9)
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i (c): Byron Unit 2 License No. NPF-66 i
condition 2.C.(4) i i
(d): traidwood Unit 1 License No. NPF-59 Condition 2.C.(7) l Dear Mr. Dentont I
I Reference (a) contained a commitment for comunonwealth Rdison to submit a preliminary report to the NRC by March 1, 1987 which describes how the requirements of Regulatory Guide 1.97 as specified in supplement 1 to i
t Nunso-0737 have been'or will be met. The purpose of this letter along with j
the enclosed report is to fulfill our casunitments in references (a) through (d).
The enclosed report provides nur preliminary evaluation of the Byron
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and Braidwood instrumentation for compliance with Regulatory Guide 1.97, r
i Revision 3, " Instrumentation for Light-Water Cooled Nuclear Power plants to l
Assess plant and Environ Conditions During and pollowing an Accident". This report delineates the entent to which our current design meets the
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requirements of each variable in the regulatory guide.
It also discusses the acceptable degrees of compliance found; whether the instrument parameter is I
in full compliance, is not in compliance but deviations are acceptable l
l through justification, or where previous specific NRC reviews found the t
3 deviation acceptable. The report also identifies those parameters where l
j deviations entst that require further evaluation to address the existing design adequacy, and whether replacement or modification is warranted. The i
results of this evaluation along with proposed changes, if any, will be provided in the final report.
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w'A8m 8;88pM..
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N.R. Denton. February 27, 1987 i
As described in reference (a), our final report concerning Regulatory Guide 1.97 compliance is integrated with the control room human factors review and various emergency response capability activities.. Our September 1, 1987 submittal date for the final report is conditioned on receipt of batc approval of our Detailed control Room Design Review (DcRDR) report.
It is our understanding that NRC review of the DcRDR is in progress.
It should be noted that commonwealth Rdison's commitments to Regulatory Guide 1.97 is to Revision 2.
As indicated on page 3 of reference (a), "should future revisions to guidance documents including regulatory guides (e.g., R.O. 1.97, Rev.
3).... impact our technical or schedular commit-monts, changes to our commitments may become desirable and will be evaluated."
our preliminary evaluation of the differences between Revision 2 and Revision 3 indicates there is little impact on our Ryron and traidwood plant designs.
We have presented the enclosed report in terms of Regulatory Guide 1.97, i
Revision 3 compliance.
please address any questions you may have regarding this matter to i
this office, t
very truly yours, g:pj i
K. A. Ainger l
Nuclear Licensing Administrator la Rnclosure j
i cct Regional Administrator - RIII Ryron Resident Inspector traidwood Resident inspector i
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2793K i
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