ML19350D721
| ML19350D721 | |
| Person / Time | |
|---|---|
| Issue date: | 02/05/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19350D711 | List: |
| References | |
| REF-QA-99900507 NUDOCS 8105180456 | |
| Download: ML19350D721 (2) | |
Text
.
Sargent & Lundy Engineers Docket No. 99900507/81-01 gv.
NOTICE OF NONCONFORMANCE Based on the results of an NRC inspection conducted on January 19-23, 1981, it appeared that certain of your activities were rot conducted in full com-pliance with NRC requirements as indicated below:
Criterion V of Appendix B to 10 CFR 50 states:
" Activities affecting quality shall be prescribed by documented instruc-tions, procedures or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures or drawings.
Instructions, procedures, or drawings shall incluce approp-riate quantitative or qualitative acceptance criteria for determining that important activitics have been satisfactorily accomplished."
Monconformances to these requirements are as follows:
A.
General Quality Assurance Procedure GQ-3.12, Revision 3, (Project Status Reports) states in part, "The status report shall indicate as applicable, the following information for each document / activity:
Latest issue date and/or revision of document."
Contrary to the above, Design Criteria Status Report SR No. 298, dated 12/10/80, lists DC-ST-03-S8 as Revision 5, dated 12/14/79, wnereas the latest revision of DC-ST-03-88 is Revision 7, dated 9/7/80.
B.
General Quality Assurance Procedure GQ-3.04, Revision S (Design Criteria) states in part, " Applicable design inputs or requirements.eJch as design bases, regulatory requirements, codes and standards, used for the develop-ment of the design criteria, shall be referenced in the design criteria.
Codes, standards and regulatory requirements referenced shall include the applicable issue and/or addenda."
Contrary to the above, Design Criteria DC-06-01-88, Revision 3, did not incluce the applicable issue for NRC Regulatory Guides 1.7 and 1.26.
C.
Clinton Power Station Classification Criteria Revision 6, dated 10-18-78, l
states in part:
ELECTRICAL CLASSIFICATION Structures, Systems and Ccmponents shall be classified as
" CLASS 1E," "NON-CLASS 1E," or "N/A" (not applicable) in accordance with the following:
8105180
..m 2
--.,.-m
.-a=*=
==--h'a
2 2.4.1 CLASS 1E The Safety Classification of the Electric Equipment and Systems that are essential to Emergency Reactor Shutdown, Containment Isolation, Reactor Core Cooling, and Containment and Reactor Heat Removal, or otherwise are essential in preventing significant release of radioactive mater 1al to the environment.
Contrary to the above, the Component Cooling Water System contains motor operated containment isolation valves that should be electrical " CLASS 1E" (e.g. cantainment isolation valve MO-1CC050); but the Clinton Pcwer Station Classification Table 3.1 lists the entire Component Cooling Water System as electrical class *NON-CLASS 1E".
See DetailsSection II, paragraph B.3. for additional information.
5
-..