ML20024A481
| ML20024A481 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/26/1983 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024A479 | List: |
| References | |
| 50-454-83-18, 50-455-83-15, NUDOCS 8306170361 | |
| Download: ML20024A481 (2) | |
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Appendix NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-454 Docket No. 50-455 As a result of the inspection conducted on March 1 through April 30, 1983, and in accordance with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982), the following violation was identified:
10 CFR 50, Appendix B, Critericn XI, " Test Control" states, in part:
"A test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satis-factorily in service is identified and performed in accordance with written test procedures which 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, 1982, Section 11, states in part: Preoperational tests which are performed on critical safety Category 1 equipment are controlled by approved written procedures....."
The Byron Startup Manual, Revision 13, dated February 3, 1983, Section 4.7.2,
" Pre-Test Briefing" states in part:
" Prior to starting the test the System Test Engineer will brief participants to:
2.1.3 Review the pertinent special precautions.
2.1.4 Inform each person what he will be expected to do during the test."
Contrary to the above, (a) Initial Condition 7.22.2, " Vibration Equipment for Sections 9.4, 9.5, 9.6, 9.7, 9.17, 9.22, 9.25, 9.26 and 9.27" had not been satisfied prior to performance of Sections 9.4, 9.5 and 9.6.
(b) During the performance of Sections 9.4 and 9.5 of Preoperational Test 2.63.10 " Integrated Hot Functional. Test", precaution 8.19 which required that the test be exited upon any indication of a loose part on the loose parts monitoring system was not observed in that all channels of the loose parts monitoring system were in a high alarm state.
8306170361 830526 PDR ADOCK 05000454 O
Appendix 2
(c) Reactor Coolant System pressure and temperature were not maintained within their expected ranges and testing continued after the out-of-tolerance values were read from the prescribed instrumentation and recorded.
(d) Pre-test briefing of operators prior-to performance of Section 9.5 and 9.6 did not include a review of precaution 8.19 or the Reactor Coolant System temperature and pressure control bands as evidenced by interviews with test support personnel and examples (b) and (c) above.
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 office within thirty days of the date of this Notice a written statement or explanation in reply, including for each item of noncompliance:
(1) cor-rective action taken and the results achieved; (2) corrective action to be taken to avoid further noncompliance; and (3) the date when full compliance
- will be achieved. Consideration may be given to extending your response time for good cause shown.
Dated C. E. Norelius, Director Division of Project and Resident Programs J
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