ML20210D273

Forwards Safety Insp Rept 50-455/87-04 on 870105-23 & Notice of Violation.Stated Event of More than Minor Safety Significance & of Concern to Nrc.Escalated Enforcement Action Considered But Not Pursued for Stated Reasons

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: IR 05000455/1987004 ML20210D273 ML20210D294
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
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         Comonwealth Edison Company
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         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

i Braidwood l Phyllis Dunton, Attorney l General's Office, Environmental I

            Control Division

( D. W. Cassel, Jr., Esq. , Diane Chavez, DAARE/ SAFE I Steve Lewis, OGC

        L. Olshan, NRR LPM
        H. S. Taylor, Quality Assurance

l Division

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