ML20029E102
| ML20029E102 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 05/04/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20029E099 | List: |
| References | |
| 70-1151-94-02, 70-1151-94-2, NUDOCS 9405160259 | |
| Download: ML20029E102 (2) | |
Text
-
ENCLOSURE 1 NOTICE OF VIOLATION Westinghouse Electric Corporation Docket No. 70-1151 Columbia, South Carolina License No. SNM-1107 During an NRC inspection conducted on April 4-7, 1994, a violation of NRC requirements was identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," the violation is listed below:
Condit'on S-1 of Special Nuclear Material License Number 1107 (SNM-147) requires that licensed material be used in accordance with statements, representations, and conditions contained in Chapters 2, 3, and 4 of the application dated March 26, 1984, and supplements thereto.
Chapter 2, Section 2.3.1.1 of the license application requires written procedures describing general nuclear criticality control requirements to be maintained and. operations to be conducted in accordance with them.
Chapter 2, Section 2.6 of the license application requires special nuclear material processing to be conducted in accordance with approved.
written procedures or instructions.
Part 7.2 of Chemical Operating Procedure, COP-810101, "UF, Vaporizer",
Revision 28, dated November 5, 1993, requires operators to relieve the pressure in the pigtail through-the eduction line.
Parts 7.1 and 7.2 of Procedure RA-104, " Regulatory Affairs Change Authorizations", Revision 7, dated February 26, 1993, requires Regulatory Affairs engineers to complete Forms RAF-104-2, " Regulatory Affairs Change Verification / Release Forms" to identify required controls for the proposed change (s) and verify implementation of the controls.
Part 7.1 of Procedure RA-106, " Internal Program Audits", Rev. 3, dated March 4,1993, requires Regulatory Affairs managers to identify specific programs to be audited and audit frequencies during the Personnel Management System (PMS) Objectives Development Process at the beginning of each calendar year.
Parts 6.5.2 and 7.6.2 of Procedure RA-304, " Criticality Accident Alarm.
System", Rev. 3, dated March 9, 1990, require the conduct of routine audits of records and activities to ensure continued operability of the criticality accident alarm system, and the conduct of routine siren audibility audits and documentation of the results on Form RA-304-4.
Part 7.4.4 of Procedure MCP-202037, "GA-6M Criticality Alarm Calibratica", Rev. 2, dated May 7, 1992, and Rev. 3, dated May 13, 1993, requires tne calibration frequency of the monitors not to exceed 26 weeks.
9405160259 940504 PDR ADDCK 07001151 C
Contrary to the above:
1.
On January 26, 1994, an operator relieved the pressure in the 401C pigtail through the UF, line which was not in accordance with procedure COP-810101.
This action had not received the appropriate safety review by licensee management.
2.
On April 7, 1994, Change Authorization packages 93162, 93272, 93282, and 93300 which were initiated between August 5 and December 15, 1993, did not contain the Regulatory Affairs Change Verification / Release Form as required by procedure RA-104.
3.
From March 4, 1993 to April 7, 1994, Nuclear Criticality Safety enginaers were not assigned audits to perform during the PMS Objectives Development Process as required by procedure RA-106.
4.
From January 1, 1992 to April 7, 1994, routine audits of records and activities of the operability of the criticality accident alarm system were not conducted as required by procedure RA-304.
5.
From January 1, 1993 to April 7, 1994, the results of routine siren audibility audits were not documented on Form RA-304-4.
6.
Criticality monitors were calibrated on July 7, 1992, February 22 and November 10, 1993.
Time periods between calibrations were 230 and 261 days which exceeded the 26 week (182 day) limit in procedure MCP-202037.
This is a Severity Level IV violation (Supplement VI).
Pursuant to the provisions of 10 CFR 2.201, Westinghouse Electric Corporation is hereby required to submit a written statement or explanation to.the U.S.
Nuclear Regulatory Commission, ATW : Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region II, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a " Reply to a Notice of Violation" and should include:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or Demand for Information may be issued as to why the license should not be modified, 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.
Dated at Atlanta, Georgia this 97(day of May 1994 j
l
,