ML20210D273
| ML20210D273 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/04/1987 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20210D279 | List: |
| References | |
| NUDOCS 8702100051 | |
| Download: ML20210D273 (2) | |
See also: IR 05000455/1987004
Text
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FE8 4 1987 Docket No. 50-455 Commonwealth Edison Company ATTN: .Mr. Cordell Reed Vice President Post Office Box'767 Chicago, IL 60690 Ge'ntlemen: This refers to the special safety inspection conducted by Messrs. P. G. Brochman and J. M. Hinds, Jr. of this office on January 5 - 23, 1987, of activities at Byron Station Unit 2, authorized by NRC Operating License No. NPF-60 and to the discussion of our findings with Mr. R. E. Querio and others of your staff at the conclusion of the inspection. The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas, the inspection consisted of a selective examination of procedures and' representative records, observations, and interviews with personnel. During this inspection, certain of your activities appeared to be in violation of NRC requirements, as described in the enclosed Notice. The violation involved an event where the Unit was taken from operational Mode 4(HotShutdown)tooperationalMode3(HotStandby)withonetrain oftheEmergencyCoreCoolingSystem(ECCS) inoperable. This event is of more than minor safety significance and is of concern to the NRC. Consideration was given, by RIII, for escalated enforcement action because of the importance the NRC places on assuring both trains of the ECCS are operable when changing to Mode 3. However, a decision was made to not pursue escalated enforcement for the following reasons: - (1) the 72 hour time clock of Technical Specification 3.5.2 was not exceeded; (2) the 1 hour time clock of Technical ~ Specification 3.0.3 was not exceeded; (3) there was no fission product inventory in the core, as the reactor had never been taken critical; (4) the event was discovered by the licensee as part of a programmed review of the Master Out-of-Service Board; and (5) once the event was discovered, licensee management gave prompt and extensive attention to the problem and has implemented significant corrective actions to prevent recurrence of the problem. Because we have reviewed your corrective actions described in Paragraph 6 of the enclosed report, no reply to the violation is required. However, the NRC believes that licensee management needs to cA s 8702100051 870204 DR ADOCK 0500 S ._ -. , . _ _,
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Comonwealth Edison Company 2{{B 4 W increase their efforts to ensure that additional attention is paid to the taking out-of-service and the returning to service of critical safety systems, especially in light of the major work which is scheduled to be performed during the upcoming refueling outage for Unit 1. In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC Public Document Room. We will gladly discuss any questions you have concerning this inspection. Sincerely, ORIGINAL CNED U C- Charles E. Norelius, Director Division of Reactor Projects Enclosures: 1. Notice of Violation 2. Inspection Report No. 50-455/87004(DRP) cc w/ enclosures: D. L. Farrar, Director of Nuclear Licensing V. I. Schlosser, Project Manager Gunner Sorensen, Site Project Superintendent R. E. Querio, Plant Manager , l DCS/RSB(RIDS)
Licensing Fee Management Branch
Resident Inspector, RIII Byron Resident Inspector, RIII
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