ML20215H301

Notice of Violation from Insp on 870301-31

ML20215H301
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/13/1987
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20215H296	List: IR 05000267/1987008 ML20215H294 ML20215H301
References
50-267-87-08, 50-267-87-8, NUDOCS 8704200251
Download: ML20215H301 (2)

Text

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APPENDIX A NOTICE OF VIOLATION Public Service Company of Colorado . Docket: 50-267 Fort St. Vrain Nuclear Generating Station License: DPR-34 During an NRC inspection conducted on March 1-31, 1987, violations of NRC requirements were identified. The violations involved improper calibration of instruments and inadequate design control. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violations are listed below:

A. Improper Calibration Criterion XI of Appendix B to 10 CFR Part 50 requires testing be

" performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in the applicable design documents." Appendix B to the licensee's FSAR, Section B.5.11.2, implements this by requiring procedures to incorporate or reference, "the requirements and acceptance limits contained in the applicable design or procurement documents."

Contrary to the above:

1. Pressure instrument number XI93508, a low range (0-100 psia) reactor coolant pressure instrument was calibrated using incorrect (psig vice psia) input values and pressure instrument numbers.

2. PI1108,-1109,-1110,(0-1000 psia) reactor coolant pressure instruments, were not calibrated over the full range of required use.

This is a Severity Level IV violation. (SupplementI)(267/8708-01)

B. _ Inadequate Review of Plant Equipment Change 10 CFR 50.59, " Changes, Tests and Experiments," allows the holder of a license authorizing operation of a production facility to make changes in procedures or the facility itself without prior Commission approval unless the change involves a change in the Technical Specifications or an unreviewed safety question.

Contrary to the above, the licensee designed, approved, reviewed, and installed a change to the reactor pressure vessel thermocouples which could not meet existing Technical Specification 5.4.1 testing requirements.

This is a Severity Level IV violation. (SupplementI)(267/8708-03)

Pursuant to the provisions of 10 CFR 2.201, is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation:

ENCLOSURE CONTAINS SAFEGUARDS INFORMATION.

UPON SEPARATION THIS

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{DP ADOCK h PAGE IS DECONTROLLED.

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2 (1)' the reason for the violations if admitted, (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken'to avoid further violations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

DatedagArlington, Texas this /J day of g 1987 l

ENCLOSURE COtTTAINS SAFEGUARDS INFORMATION.

UPON SEPARATION THIS PAGE IS DECONTR7LLED.