ML20235K499
| ML20235K499 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/28/1987 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Butterfield L COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8710050114 | |
| Download: ML20235K499 (2) | |
Text
..
September 28, 1987 Docket No. 50-454 and 50-455 s
s
'I 1
Commonwealth Edison Company ATTN:
Mr. L. D. Butterfield, Jr.
Nuclear Licensing Manager a
P. O. Box 767 Chicago, Illinois 60690 Gentlemen:
'j
SUBJECT:
BYRON STATION - REGULATORY EFFECTIVENESS REVIEW Enclosed is the final report of a Safeguards Regulatory Effectiveness Review l
(RER) conducted by the NRC at Byron Station, April 6-10, 1987.
A timely response within 45 days will be appreciated.
(Part.III of the report, Vital Area Definition, will be forwarded later under separate cover.)
In preparing the final report, subsequent to each RER site' visit, we review the j
findings in light of NRC regulations and commitments in the NRC-approved security plan.
As a result, we identify in each report any deficient. ins which appear to involve possible violations of NRC requirements and refer them to the cognizant regional office for follow-up inspection and enforcement actions as appropriate.
Other deficiencies not involving violations of NRC regulations, which could nevertheless result in substantial additional protection if corrected through
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security plan changes, include those characterized as " potential. vulnerabilities,"
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" inadequacies" and possibly " concerns." Where such items are identified in the j
report, they are accompanied by a brief' description of the merits of corrective actions.
In reviewing and responding to such< findings,-licensees have an opportunity to voluntarily propose improvement actions or to indicate that such actions are not warranted. _Of course, where a licensee indicates that j
corrective action is not warranted but the NRC believes it would result in substantial additional protection, NRC may initiate a regulatory analysis and proposed backfit in accordance with 10 CFR 50.109.
The reporting and/or recordkeeping requirements contained in this; letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
B710050114 go 54 UPON REMOVAL OF ATTACHMENT TlilS DOCUMENT PDR ADOCK PDR DEC0NTR0LLED G
Document Transmitted Herewith.Contains SAFEGUARDS INFORMATION i
a 4
SAFEGUARDS FORMATION
4 Commonwealth Edison Company 'The enclosures to this letter contain Safeguards Information of a type specified
.in 10 CFR 73.21.and must be protected against unauthorized disclosure.
Sincerely,-
Dennis M. Crutchfield, Director Division of Reactor Projects -'III, IV, V l
l and Special Projects I
Office of Nuclear Reactor: Regulation a
Enclosures.
l 1.
Safeguards Systems Effectiveness Review, Part I 2.
Safety / Safeguards Interface Review Part II cc w/ enclosures:
J. Hind, Region III W. Rogers, Sr. Resident Inspector cc w/o enclosures.
4 See next page DISTRIBUTION:s(w/o. enclosure),s.
DISTRIBUTION (w/ enclosures).
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