ML20042E551
| ML20042E551 | |
| Person / Time | |
|---|---|
| Issue date: | 04/12/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20042E548 | List: |
| References | |
| REF-QA-99900277 NUDOCS 9004230592 | |
| Download: ML20042E551 (2) | |
Text
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l The Rockbestos Company i
l Docket / Report No. 99900277/90-01 l
APPENDIX A NOTICE OF NONCONFORMANCE Based on the results of an NRC inspection conducted January 30 through
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t February 2,1990, it appears that certain of your activities were not conducted in accordance with NRC requirements which were. imposed on you by purchase order contracts with NRC licensees.
Nonconformances with these requirements I
are as follows:
i A.
Criterion III of Apppendix B to 10 CFR Part 50, " Design Control " states, in part:
... Design control measures shall provide for verifying or I
checking the adequacy of design, such as by the performance of design.
reviews, by the use of alternate or simplified calculational Lethods, or i
i by the performance of a suitable testing program.
The verifying or I
checking process.shall be performed by individuals or grou)s other than those who performed the original design, but who may be from the 'same organization...."
j Section I-6, " Approval and Release of Design Data." of.Section I, "New or Modified Standard for Nuclear Safety Related Products Manufactured to Rockbestos or Industry Standards," of Rockbestos Quality Procedure S-3, Design Control System, Revision 15, dated June 6, 1986, states, in part:
" Design verification shall be performed by individuals other than those who performed the original design, but who may be from the same organiza-t tion.
The Engineering Department shall identify the verification method.
QA shall monitor the activities...."
Contrary to the above, the Rockbestos design control program was not implemented adequately to ensure that cable information that will be used as nuclear plant design information ano provided to nuclear utilities was checked for adequacy by individuals or groups other-than those who performed the original design in that Rockbestos provided cable ampacities and ampacity calculations (nucleer plant design data) 'that were not formally reviewed and approved anc which were prepared using a computer code that was not formally reviewed and approved for Firezone R cable that l
was sold to the Northeast Utilities / Connecticut Yankee Atomic : Power-Company's Haddam Neck Plant.
B.
Criterion V of Appendix B to 10 CFR Part 50.. " Instructions, Procedures,
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and Drawings," states: " Activities affecting quality shall be prescibed by documented instructions, 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 include appropriate quar.titative or qualitative acceptance criteria for determining that important activities have been s6tisfac-torily accomplished."
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9004230592 900412 PDR QA999 EMVROCK 99900277 PDC
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t Contrary to the above, certain Rockbestos procedures related to measure-ment of coaxial type cable insulation resistance were not appropriate to the circumstances.
Specifically:
1.
The Rockbestos general procedure for measuring insulation resistance on coaxial, twinaxial, and triaxial cables, RTP-0050, dated August 9, 1978, revision dated September 24, 1965, prescribes the use of a separate, 240-amp power supply in conjunction with the insulation resistance measurement instrument.
Use of a separate power supply is inconsistent with use of a Genrad 1864 megohmeter bridge which has an internal power supply and is the instrument specified for use by this revision of RTP-0050.
2.
Type "B" laboratory test data sheets (TOBs) that were prescribed for use with RTP-0050 had not been updated to reflect the revision of RTP-00$0 which required the use of the Genrad 1864 megohmeter bridge-on whole reels of cable.
Test data sheet TDB G338Z, Revision E, dated December 17, 1984, for RSS-6-100/LE type coaxial cable, for example, specified a sample length of 20 feet and also specified a current set (power supply) voltage of 100 volts which is a device and a voltage respectively not used with a Genrad 1864 C.
Criterion XI of Appendix B to 10 CFR Part 50, " Test Control," states, in part:
... Test results shall be documented and evaluated to assure that test requirements have been satisfied."
Contrary to the above, test results in Rockbestos Qualification Report QR-6802, Revision 1, dated July 2,1987, were not adequately evaluated to assure that requirements were satisfied in that post-LOCA insulation resistance values listed as " pass" (1) were taken by an instrument that was not only uncalibrated in the required range, but was also incapable of obtaining a valid reading of the required magnitude, '(2) were not demon-strated, for "B"
and "C" type samples, to have met their acceptance-criterion of 1,000,000 megohms when given as " greater than 360,000 megohms,"
and (3) were shown, for "D" type samples, to be below their 100,000-megohm per 1000-feet specification when corrected to a per-1000-feet value of 90,000 megohms.
D.
Criterion XVI of Appendix B to 10 CFR Part 50, " Corrective Action,"
states, in part: "...In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition...."
Contrary to the above, although Rockbestos established measures to correct certain conditions adverse to quality that were identified as nonconfor-mances during previous NRC inspections, these measures were not fully effective in that some of the same types of nonconformances, such as using test equipment not appropriate nor adequately calibrated for the range of test values, were repeated and identified in this inspection..
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