ML20028A306
| ML20028A306 | |
| Person / Time | |
|---|---|
| Issue date: | 10/15/1982 |
| From: | Phillips H, Alexandra Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028A304 | List: |
| References | |
| REF-QA-99900909 NUDOCS 8211180216 | |
| Download: ML20028A306 (7) | |
Text
1 ORGANIZATION:
SOUTHWEST RESEARCH INSTITUTE SAN ANTONIO, TEXAS Ktrunt 1HbFtbl10N IN5Ftbl1UN N0.:
99900909/82-02 DATE(S) 9/20-21/82 ON-SITE HOURS: 14 CORRESPONDENCE ADDRESS:
Southwest Research Institute ATTN:
Mr. Roger L. Bessey, Group Leader,ics Department of Engineering Mechan 6220 Culebra Road P. O. Drawer 28510 San Antonio, TX 18284 ORGANIZATIONAL CONTACT:
Mr. Timothy A. Fey, Research Engineer TELEPHONE NUMBER:
(512)684-5111 PRINCIPAL PRODUCT: Research and Testing Laboratory NUCLEAR INDUSTRY ACTIVITY: Southwest Research Institute is a nonprofit corporation conductinganumberofresearchprojectssponsoredbybothprivateindustryand various government agencies.
Their current nuclear work includes research projects for NRC inspection of equipment at nuclear power generating plant sites, and con-ducting, nuclear equipment qualification tests for a number of manufacturers and/or utilities.
ASSIGNED INSPECTOR:
bNM
/oh.r/gL A. L. dmith tquipment qualitication Vate' Section($QS)
OTHERINSPECTOR(S):
/0//f/r3 APPROVED BY:
H. 5. Ph1Ilips, Chlet, EQ5 Date INSPECTION BASES AND SCOPE:
A.
BASES:
Appendix B to 10 CFR Part 50 B.
SCOPE:
Review of applicable test plan, witnessing Class 1E qualification tests for NAMC0 limit switches, Seitz safety relief solenoid valves, and PYC0 temperature elements.
PLANT SITE APPLICABILITY:
Grand Gulf Unit 1, Docket No. 05000416; and Clinton Unit 1, Docket No. 05000461 c::st,cgi.n:D onicInL omn.4 37uuuuxL dm***
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ORGANIZATION:
SOUTHWEST RESEARCH INSTITUTE SAN ANTONIO, TEXAS REPORT INSPEcl10N NO.:
99900909/82-02 RESULTS:
PAGE 2 of 3 A.
VIOLATIONS:
None B.
NONCONFORMANCES:
None C.
UNRESOLVED ITEMS:
None D.
OTHER FINDINGS OR COMMENTS:
1.
Background - Mississini Power and Light and the Illinois Power Company have contracted with UTECH, San Jose California, to perform a portion oftheirengineeringeffortfortheClass1Esafety-relatedequipment qualification program for the Grand Gulf I and Clinton I Nuclear Power Stations.
As a result of this contract, NUTECH has prepared a test specification and entered into a contract with Southwest Research Institute (SWRI), San Antonio, Texas, to qualify three Class IE safety-related components.
The items to be tested by SWRI are:
Main Steam Isolation Valve, ion K)ge Control System Limit Switch Leaka a.
(NAMCO, Model EA-740, Revis b.
Safety Relief Valve Solenoid (Seitz AG, Model 0-105-562e).
c.
Temperature Element (Pyco, Model N145C3224).
Currently, SWRI intends to conduct radiation aging tests, thermal aging tests, and seismic tests "in-house" and subcontract the LOCA tests to the CONAX Corporation, Buffalo, New York.
2.
Test Plan - In response to the NUTECH test specification, SWRI has preparedatestplan(SWRIProject 02-7124) to describe the procedures and tests which will be performed on the three components.
An overview of the test plan was made by the inspector during this inspection to assure that the tests that were witnessed were accomplished in accordance with the test plan.
An indepth evaluation of this plan to the specific requirements imposed in IEEE 323, 344, and NUREG-0588, Revision 1, will be performed and reported separately.
J ORGANIZATION:
SOUTHWEST RESEARCH INSTITUTE SAN ANTONIO, TEXAS REPORT ANbFtLi1UN NO.:
99900909/82-02 RESULTS:
PAGE 3 of 3 3.
Quality Assurance - The inspector examined the receiving inspection reports for the five limit switches, five temperature elements, and two safety relief valve solenoids.
The receiving inspection reports indicated that some items received were damaged; subsequently, a deviation and nonconformance report was issued and processed in accor-dance with the provisions contained in the SWRI Quality Assurance Program Manual.
Since SWRI is accom)lishinc LOCA testing under subcontract to CONAX, the applicable purclase orcer was examined to determine that both regulatory (Criterion IV, 10 CFR Part 50, Appendix B) and SWRI quality assurance requirements had been met.
The inspector determined that they had.
4.
Witness of Tests - During this inspection, the NRC inspector witnessed baseline performance tests on all 12 items being tested.
Baseline aer-formance tests were conducted in accordance with paragraph 5.5 of tie test alan to demonstrate that each component parameter was within the opera)ility requirements described in tables 2.2-1 to 2.2-3 of Appendix B of the test plan.
During this testing, no failures were noted and all parameters measured were within the performance envelopes specified in the test plan.
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