ML20211M224
| ML20211M224 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/18/1987 |
| From: | Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20211M194 | List: |
| References | |
| 50-454-87-02, 50-454-87-2, 50-455-87-02, 50-455-87-2, NUDOCS 8702270236 | |
| Download: ML20211M224 (1) | |
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NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-454 Docket No. 50-455 As a result of the inspection conducted on January 1 - 29,-1987, and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the following violations were identified:
1.
Technical Specification 3.3.3.1 requires that Main Control Room Isolation
- Outside Air Intake - Gaseous Radioactivity High - Monitor 0PR034J be operable at all times or else follow Action Statement'27.
Action Statement 27 requires that with OPR034J inoperable, within one hour isolate the OB Control Room Ventilation System and initiate operation of the Control Room Make-up System.
Contrary to the above, from 1700 on December 12, 1986 to 1615 on December 15, 1986, while in Mode 1 for Unit 1 and Mode 3 for Unit 2, radiation monitor 0PR034J was inoperable for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) without action being taken to isolate the 08 Control Room Ventilation System and initiate operation of the Control Room Make-up System.
This is a Severity Level IV violation (Supplement I). (454/87002-03(DRP);
455/87002-02(DRP)).
2.
10 CFR 50, Appendix B, Criterion V, as implemented by the Commonwealth Edison Company's Quality Assurance Manual, Quality Requirement 5.0, requires that activities affecting quality shall be accomplished in accordance with approved instructions, procedures and drawings.
Crosby Valve Company valve test data sheet for 3 inch safety valve style J0-25WR requires that the nozzle ring for safety valve 2CC9428B be set at -100 notches.
Contrary to the above, from November 6 - 20, 1986, while in Modes 5 and 6, the nozzle ring for safety valve 2CC94288 was not set at -100 notches.
This is a Severity Level IV violation (Supplement I) (455/87002-04(DRP)).
The inspection showed that action had been taken to correct the identified violations and to prevent recurrence.
Consequently, no reply to the violations is required and we have no further questions regarding this matter.
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RF/1)annik Dated R. F. Warnick, Chief Reactor Projects Branch 1 gg22g)2 g h y4 D
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