ML20213G888
| ML20213G888 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/11/1987 |
| From: | Hehl C NRC |
| To: | |
| Shared Package | |
| ML20213G885 | List: |
| References | |
| 50-454-87-16, NUDOCS 8705190009 | |
| Download: ML20213G888 (1) | |
Text
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NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-454 As a result of the inspection conducted on April 1-9, 1987, and in accordance with 10 CFR Part 2, Appendix C - General Statement of Policy and Procedure for NRC Enforcement Actions (1985), the following violation was identified:
Technical Specifications, Section 6.8.1.a. states that written procedures shall be established, implemented, and maintained for activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2.
Procedures for surveillance tests listed in the Technical Specifications are required to be written by Part 8.b of Appendix A.
Surveillance Procedure 1BOS 0.1-6, " Unit One Mode 6 Shiftly and Daily Operating Surveillance," requires that reactor cavity water level be determined in accordance with Temporary Change No. 87-1-283. SFP level is also required to be documented. -These surveillances are used to satisfy Sections 4.9.10 and 4.9.11 of the Technical Specifications.
Contrary to the above, the licensee failed to adhere to Procedure 180S 0.1-6 during the Byron Unit 1 core reload, in that, the cavity and SFP levels were not properly documented.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement (1) corrective action or explanation in reply, including)for each violation:
taken and the results achieved; (2 corrective action to be taken to avoid j
further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
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'?n w n. M F 7 OTW W Dated O Cliarles W. Hehl, Chief Operations Branch G
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