ML20238E562
| ML20238E562 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 12/28/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 4036K, NUDOCS 8801050227 | |
| Download: ML20238E562 (2) | |
Text
- _ _ - _ _, _ _ _ _ _ _.
1 Ccmm:nw21!th Edis:n
,n One First National Plaza. Chicago, Illinois v
Address Reply to: Post Oifice Box 767 Chicago, Illinois 60690 0767 1
December 28, 1987
)
Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20S55 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Regulatory Guide 1.97 Compliance Final Report NRC Docket Nos. 50-454/455 and 50-456/457 References (a): February 27, 1987 K.A. Ainger letter to H.R. Denton (b): September 1, 1987 S.C. Hunsader letter to T.E. Murley (c): November 6, 1987 L. Olshan letter to L.D. Butterfield
Dear Mr. Murley:
Reference (a) provided our preliminary evaluation of the Byron and Braidwood instrumentation for compliance with Regulatory Guide 1.97, l
Revision 3 " Instrumentation for Light-Water Cooled Nuclear power plants to Assess plant and Environ Conditions During and Following an Accident". That preliminary report delineated the extent to which our current design met the requirements of each variable in the regulatory guide.
It also discussed the degree of compliance found and identified those parameters where deviations exist that required further evaluation. Reference (b) provided the results of our final evaluation. Attachment A to reference (b) provided an update of Table 5-1.
Attachment B to reference (b) provided the revised Human Factors Engineering Review. These supplemented the information provided in reference (a) and, together references (a) and (b) constituted our " Final Report" concerning Regulatory Guide 1.97 compliance.
Reference (c) provided the NRC review and evaluation of references (a) and (b).
In that letter it was stated that the NRC review did not consider the information provided in reference (b).
The letter further stated that there were some items that E.G. & G could not conclude had been provid3d with adequate justification and, as such, identified those as unjustified exceptions.
(
goo 3 8801050227 871228 i(
I PDR ADOCK 05000454 N Mk
.-w T. E. Murley Decemb r 28, 1987 Commonwealth Edison believes that we have addressed those items in reference (b). We request that the NRC complete their review of reference (b), and if upon completion, there are any questions or concerns, then these can be presented to us to be addressed accordingly. Please address these to this office.
Very truly yours,
. c.1M S. C. Hunsader Nuclear Licensing Administrator cc:
L. Olshan S. Sands NRC RIII Byron Resident Inspector Braidwood Resident Inspector l
i 1
4036K l
t
_ _ _ _ _ _ _ _ _ _ _.