ML20212M068

Notice of Violation from Insp on 861018-1114

ML20212M068
Person / Time
Site:	Byron
Issue date:	01/22/1987
From:	Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20212M063	List: IR 05000454/1986045 ML20212M061 ML20212M068
References
50-455-86-41, NUDOCS 8701290492
Download: ML20212M068 (2)

Text

i NOTICE OF VIOLATION Conror. wealth Edison Company Docket No. 50-455 As a result of the inspection conducted on October 18 - November 14, 1986, 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. 10 CFR 50.59, " Changes, Tests and Experiments" requires that a licensee maintain records of tests and experiments carried out pursuant to 10 CFR 50.59 (a) which "shall include a written safety evaluation which provides the bases for the deterr.ination that the change, test, or experinent does not involve ar urreviewed safety questicn." Syron Adn.inistrctive Procedures BAP 1210-5, "10 CFR 50.59 Saf ety Evaluation Procedure," Revisicn 3, and BAP 1310-T19 "10 CFR 50.59 Format for Safety Evaluation," which implement the above require that the following be recorded on procedure checklists ar.d foms: 1) the specific reasons justifying the decision that an unreviewed safety question does or does not exist, 2) the review of potential system interactions, and 3) the review of applicable sections of the FSAR, technical specifications, and other potentially applicable documents.

Contrary to the above, the safety evaluations for the 2B Diesel Generator Preoperation Test (DG 22.62) and two retests (R-2020 and R-2021),

Containment Purge Retest ',3-2067), Diesel Generator Ventilation Retest (R-2049) and the Main Stcam Power Operated Relief Valve Component Den.onstr, . ion (C-2061) did not provide the bases for the determination that unreviewed safety questions were not involved in the performance cf the tests nor did they include the information required by the above licent.ee procedures.

This is a Severity Level V violation (Supplement II). (455/86041-01(DRS))

2. 10 CFR 50, Appendix B, Critericr. XVI, as implemented by the Commonwealth Edison Company's Quality Assurance Manual, requires that conditions adverse tc quality be identified and corrected in a n.anner that precludes repetitior.

Ccntrary to the above, for Precperational Test PS 61.60, " Process Sampling Primary," there were two cases in which deficient conditions were resolved during Byron Unit 1 preoperational testing but the resolutions were not incorporated into the Byron Unit 2 preoperational test. As a result Unit 2 testins encountered the same deficiencies. In one case, a test acceptance criteria required that the temperature difference between the component cooling inlet temperature and the sample coolers effluent temperature be oc greater than 6*F. However, the combined instrunient tolerances of the instruments used to measure the temperatures in question was greater than 6*F and consequently the acceptance criteria could not be verified using t'1ese instruments. In the other case, a sample purge flow rate specified in the test was found to be based on an improper design pressure.

ThisisaSeverityLevelVviolation(SupplementII).(455/86041-09(DRS))

8701290492 870121 PDR ADOCK 05000454 O PDR

i i Pursuar.t to the provisions of 10 CFR 2.201, you are required to submit to this i office within thirty days of the date of this Notice a written staten.ent or j explanation in reply, including for each violation: (1)correctiveaction taken and the results achieved; (2) corrective action to be taken to avoid further violaticns; and (3) the date when full confliance will be achieved.

I Consideration may be given to exter. ding your response tinie for scod cause i shown.

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C. J/ Paper)6110, Director

! Datedj /

J Division of Reactor Safety I

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2 Notice of Violation