ML20071B442
| ML20071B442 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/10/1983 |
| From: | Farrar D COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20071B436 | List: |
| References | |
| 5984N, NUDOCS 8302280303 | |
| Download: ML20071B442 (3) | |
Text
,
+,e, x x Commonwealth Edison
) One First Nation 31 Plaza, Chictgo, Illinois C
.j
-p( C
~1 Address R: ply to: Post Offics Box 767 A,
j Chicago, Illinois 60690 February 10, 1983 Mr. James G. Keppler, Regional Administrator Directorate of Inspection and Enforcement - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Byron Station Units 1 and 2 I&E Inspection Report Nos.
SC-454/82-18 and-50-455/82-13 Reference (a):
January 11, 1983 letter from C. E. Norelius to Cordell Reed.
Dear Mr. Ke?cler:
Reference (a) provided the results of an inspection conducted by Mr. R.
N. Sutphir. during April, May, and December,1982 of activities conducted at Byron Station.
During this inspection certain activities were found to be in noncompliance with NRC requirements.
Attachment A to this letter contains Commonwealth Eoison's response to the Notice of Violation appended to reference (a).
To the best of my knowledge and belief the statements contained herein and in the attachment are true and correct.
In some respects these statements are not based on-my personal know-ledge but upon information furnished by other Commonwealth Edison and contractor employees.
Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
j-Please address further questions regarding this matter to this office.
l Very truly yours,
.A =m i
- 0. L. Farrar Director of Nuclear Licensing l
l TRT/kiin Attachment FEB11 1993 5984N 2h O
-v ATTACHMENT A
' Response >to; Notice of-Violation Violation' 10 CFR 50, Appendix B, Criterion III states in part that, " Measures.shall be-established to assure that applicable ~ regulatory requirements...are correctly-translated.into specifications, drawings, procedures, and instructions."
~
The. Ceco Topical Report 'CE-1-A,-Revision 15, SectionJ3.1 states in part that, " Review and evaluation 1by Architect Engineer, the Nuclear Steam' Supply. System vendor, and/or1Proj*ct Engineering or the Station Nuclear Engineering Department will assure that designs n'nd materials will confore i
to the ASME and other applicable codes, stEndards, regulatory requirements,
- SAR commitments, and appropriate quel,ity star.dards, as applicable.
i
- Contrary tn the above, tne fol'10 wing eiamples were' identified in whicn the licensee failed to correctly translate the applicable regulatory require-ments into the specifications, crawings, procedures, and instructions:
(a)
The referenced edition dates for four civil / structural standards were inconsistent between FSAR Table 3.8-2 and S&L Specification F-2722.
-(b)
Five standards referenced in the FSAR Table 3.8-2 were not implemented for civil / structural' work performed at Byron.
-(c).
Neither~S&L Specification F-2722 nor Specification F-2850 included the FSAR Table B.1-5 requirement to test the first-batch of concrete placed each day. - The FSAR statement was not implemented, in.that, three of six concrete pour packages which
['
were reviewed indicated that the first batch had not been tested.
1 i
Corrective Action Taken and Results-Achieved
[
The FSAR is being revised as follows:
'(a).The only dates to be retained in FSAR Table 3.8-2 will be for l
the codes used in the design of safety related structures.
All other standards delineated in this table are for recommended l
practices in concrete construction and material specifications I
that do not affect the design of safety related structures.
(b)
Five standards referenced in the FSAR Table 3.8-2 that were not implemented for civil / structural work performed at Byron will be l.
deleted from the Table.
I
. (c) LTesting the first batch is intended to control-overnight.
variations in the moisture content of aggregate and variations in the concrete materials.
Since the batch plant bins'and silos store material overnight, the materials used.iri the first pour are the same materials already in the batch plant from the preceeding. production day.
Segregation, contamination, degra-dation in properties or moisture variations in the aggregate are therefore reduced to a minimum.
Therefore, testing of the first batch of concrete will not be of any additional' significance in controlling the auality of concrete.
Experience has shown that variations in slump, air content and temperature occur several batches after production is started every day.
These variations are related to material transition from the material stored in the batch plant to material that is stock piled.
Corrective Action-Taken to Avoid Further-Noncompliance The Byron /Braidwood FSAR will be reviewed for other conflicts with structural design drawings and specifications.
Any necessary FSAR revision will be subnitted to the NRC for review.
Date When Full-Com.oliance Will-Be Achieved April 1, 1983.-
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