ML20053D810
| ML20053D810 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/19/1982 |
| From: | Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20053D808 | List: |
| References | |
| 50-454-82-07, 50-454-82-7, 50-455-82-05, 50-455-82-5, NUDOCS 8206070342 | |
| Download: ML20053D810 (2) | |
Text
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Appendix NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-454 As a result of the inspection conducted on March 22 through April 30, 1982, and in accordance with the NRC Enforcement Policy,-47 FR 9987 (March 9, 1982),
the following violation was identified:
10 CFR 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants states in part:
"XI Test Control...A test program shall be established to assure that all testing required to demonstrate that struct res, systems, and components will perform satisfactorily in service is i mntified and performed in accordance with written test procedures whivu incorporate the requirements and acceptance limits contained in applicable design documents."
The Byron FSAR, Chapter 17.0, Quality Assurance, states in part:
"Therefore the CE Topical Report CE-1-A, Revision 7 and all subsequent revisions unless otherwise noted in this chapter, is the basis for the QA Program at Byron /Braidwood station."
Commonwealth Edison Company Topical Report CE-1-A, Quality Assurance Program for Nuclear Generating Stations, Revision 20 dated February 17, I
1982, Section 11, states in part:
"Preoperational tests which are per-formed on critical Safety Category I equipment are controlled by approved written procedures..."
Contrary to the above, on April 21, 1982, the inspector noted that during the performance of Emergency Diesel 1A testing in accordance with Preopera-tional Test Procedure 2.22.10, Section 9.12, the' following conditions existed:
a.
Operators had not been properly briefed.
b.
Test procedures had not been reviewed by operators prior to manning a control station, nor was a copy maintained at each station.
c.
The Test Engineer had entered the test at 11:15 a.m., however, at 2:12 p.m. the operator was maintaining a kilowatt output less than allowed by procedural Step 9.12.23.
8206070342 820519 PDR ADOCK 05000454 G
Appendix 2
d.
On station relief at 3:10 p.m. at the control station in the control room was improper in that the oncoming watch had not reviewed the procedure or been briefed on procedural requirements. Additionally, the information provided by the off going watch was not in accordance with procedural requirements.
This is a Severity Level IV violation (Supplement II).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this of fice within thirty days of the date of this Notice a written state-ment or explanation in reply, including for each item of noncompliance:
(1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further noncompliance; and (3) the date when full com-pliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
MAY I 9 1982 8toriginal signed by R.L. Spessard" Dated R. L. Spessard, Director Division of Project and Resident Programs