ML20045J097
| ML20045J097 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/19/1993 |
| From: | Beverly Clayton NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20045J094 | List: |
| References | |
| 50-461-93-09, 50-461-93-9, NUDOCS 9307230041 | |
| Download: ML20045J097 (2) | |
Text
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f NOTICE OF VIOLATION Illinois Power Company Docket No. 50-461 Clinton Power Station License No. NPF-62 4
As a result of the inspection conducted on May 18 through June 28, 1993, and in accordance with the " General Statement of_ Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1993), the following violations were identified:
1.
Part 50 of Title 10 of the Code of Federal Regulations, Appendix B, Criterion V, requires that activities affecting quality shall be prescribed by documented instructions or procedures of a type-appropriate to the circumstances.
Instructions or procedures shall contain appropriate quantitative or qualitative acceptance criteria for deterr.iining that important activities have been satisfactorily accomplished.
Contrary to the above:
a.
On June 9, 1993, operating procedure 3509.01, " Instrument Power System," Appendix E, Part B, did not indicate a end-of-cycle recirculation pump trip. (EOC-RPT) would occur for reactor recirculation breaker 4b, when the Division III nuclear system protective system (NSPS) bus was energized.
b.
On February 26, 1987, procedure 9437.17, " Containment /Drywell Atmosphere H,/0, Monitoring System," section 8.3.1.6, was changed to specify a pressure of 2: 35 psig, from the previous correct pressure of approximately 40 psig-(35-45).
This is a Severity Level IV violation (Supplement I)
(461/93009-01(DRP)).
2.
Technical Specifications 3.3.7.5, Table 3.3.7.5-1, Instrument 7, Action 83-b, required while in Operational Conditions 1, 2, and 3, th'at both the Division I and II containment and drywell H /0, analyzers be 2
operable or else be-in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Contrary to the above, from September ~29, 1986, to_ March 21, 1993, both divisions of the containment and drywell H,/0, analyzers were inoperable (incapable of performing their design function in certain circumstances) and action was not _taken to place _the unit in HOT SHUTDOWN.within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
This is a Severity Level V violation (Supplement I) (461/93009-02(DRP)).
9307230041 930719 C l
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JUL 191993 -
The inspection showed that-steps 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 these matters.
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Dated at Glen Ellyn, Illinois V
this lf4 day of July 1993 Brent Clayton' Chief Reactor Projects Branch I s
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