ML20128E196
| ML20128E196 | |
| Person / Time | |
|---|---|
| Site: | 07100346 |
| Issue date: | 02/01/1993 |
| From: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20128E067 | List: |
| References | |
| 71-0346-93-02, 71-346-93-2, NUDOCS 9302100341 | |
| Download: ML20128E196 (2) | |
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NOTICE OF NONCONFORMANCE Public Service Company of Colorado Docket No. 71-0346 Denver, Colorado During a U.S. Nuclear Regulatory Commission inspection conducted at Public Service Company of Colorado (PSC), Fort St. Vrain Facility in Platteville, Colorado, on December 1-3, 1992, nonconformances with certain NRC commitments were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1992), the nonconformances are listed below:
A. 10 CFR 5 71.111. " Instructions, procedures, and drawings," requires the licensee to establish procedures that include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished. The licensee shall require that these procedures are followed.
Contrary to the above, the following activities were not conducted in accordance with established procedures.
- 1. Procedure FHPWP-300-123 requires that a Quality Control (QC) person initial and date the acceptance or replacement of a set of " Heli-Coils" on the Model No. FSV-1 packaging. During activities performed on 10/06/91, neither initials nor a date were documented to certify that this step had been completed.
- 2. Procedure FHPWP-300-124 requires that the torquing value for the leveling studs on the Model No. FSV-1 packaging be verified and documented in the procedure. On approximately 50 percent of the
! records reviewed, the torque value was not documented as required by l the procedure.
B. 10 CFR 5 71.123, " Test Control," requires the licensee to establish procedures that include provisions to assure adequate test instrumentation is available and used. The licensee is required'to assure that test requirements have been met.
Contrary to the above, a gauge used to perform leak testing on the'Model No. FSV-1 packaging wu not identified by serial number and documented for future verification.
PSC is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Branch Chief, Transportation Branch, Office of Nuclear Material Safety and Safeguards (NMSS), within 30 days of the date of the letter transmitting this Notice of Nonconformance (Notice). This reply should be clearly marked as a " Reply to a Notice of Nonconformance" and should include, for each nonconformance, (1) admission or denial of the alleged 9302100341 930201 PDR ADOCK 07100346 C PDR
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i 1 o Notice of Nonconformance 2 Docket-No. 71-0346 nonconformance; (2) the reason i r the nonconformance, if admitted; (3) the 4 - corrective steps that have been taken and the results-achieved; (4) the corrective steps that will be taken to avoid further nonconformances; and (5) the date when full compliance will be. achieved. If an adequate reply is not ;
received within the time specified in this Notice, an order may be issued to show cause why the Quality Assurance Program Approval should not be modified, 4 suspended, or revoked, or why such'other action as may be proper should not be ,
taken. Where good-cause is shown, consideration will be given to extending
. the response time.
FOR THE NUCLEAR REGULATORY COMMISSION w k A Charles E. MacDonald, Chief Transportation Branch Division of Safeguards i and Transportation, NMSS
} Dated at R ekville, tiaryland This I day of /:,c2L , 1993 i
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