ML20153C083
| ML20153C083 | |
| Person / Time | |
|---|---|
| Issue date: | 02/06/1986 |
| From: | Moist R, Potapovs U NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20153C061 | List: |
| References | |
| REF-QA-99900902 NUDOCS 8602180251 | |
| Download: ML20153C083 (12) | |
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s ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION INSPECTION NO.: 99900902/85-04 DATE(S):
11/18-22/85 ON-SITE HOURS: 78 CORRESPONDENCE ADDRESS: Wyle Laboratories Scientific Services and Systems Group ATTN: Mr. W. W. Holbrook, General Manager Eastern Test and Engineering Operations 7800 Governors Drive Huntsville, Alabama ORGANIZATIONAL CONTACT: Mr. E. W. Smith, Director, Contracts and Purchasing TELEPHONE NUMBER:
(205) 837-4411 PRINCIPAL PRODUCT: Research, engineering, and test operations.
NUCLEAR INDUSTRY ACTIVITY: Wyle Laboratories; Huntsville, Alabama, provides a variety of nuclear services to the industry. These services include environmental and seismic qualification testing of safety-related equipment, refurbishment and recertification of valves, valve and component ficw testing, mechanical and hydraulic snubber testing, decontamination, and repair.
ASSIGNED INSPECTOR:
au/cd2/ 7/. 77)gda/r 5ffd f(f Rf. N. Moist, Equipment Qualification Inspection Date Section (EQIS)
OTHER INSPECTOR (S):
R. H. Lasky, EQIS J. Grossman, Sandia National Laboratories
[, N
'l-C 4 APPROVED BY:
U. Potapovs, Chief. EQIS\\ Vendor Program Branch Date INSPECTION BASES AND SCOPE:
A.
BASES:
10 CFR Part 21 and 10 CFR Part 50, Appendix B B.
SCOPE: This inspection consisted of:
(1) a technical evaluation of equipment qualification (EQ) test activities for safety-related equipment (2) witnessing EQ testing; and (3) verification of implementation of the quality assurance (QA) program.
PLANT SITE APPLICABILITY:
Sequoyah-1, 2 (50-327, 50-328), Watts Bar 1, 2 (50-390,391), Nine Mile Point 1 (50-220)
?D$ B0 860 99900h EX1 E
o e
ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO - 99900902/85-04 RESULTS:
PAGE 2 of 6 A.
Violations None.
B.
Nanconformances None.
C.
Unresolved Items None.
D.
Other Findings or Comments 1.
Technical Evaluation of Test Results The NRC inspectors and Sandia Consultant (NRC inspection team) evaluated test results of two cable tests performed under Qualification Plan.(QP) 17460-44.
The cable tests were conducted for Tennessee Valley Authority (TVA) for use in Watts Bar and Sequoyah Nuclear Power Stations.
Twenty five cable specimens representing eight manufacturers and several different insulation systems were included in the test program for the first test. The NRC inspection team had previously witnessed a portion of a high energy line. break (HELB) environmental test on October 1, 1985. Approximately three minutes into that test, one specimen (39-2) failed, causing an open circuit. Since the NRC's last visit, Wyle personnel performed a failure analysis and determined that a defect at the point where the jacket material was cut for splicing was the cause of failure.. Failure was attributed to damage done to the insulation during installation and not as a. result of the test exposure. This cable was subsequently retested during the second cable test and performed as required.
Sixteen cable specimens representing nine manufacturers and several different insulation systems were included in the test program for the second test.
Review of the test results by the NRC inspection team showed that two cable specimens (8-1, 8-2) lost voltage during the HELB environmental test.
Failure analysis by Wyle for specimen 8-1 (20 year. accelerated aging) determined that a -faulty instrumentation
ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA PEPORT INSPECTION NO.-
99900902/85-04 RESULTS:
PAGE 3 of 6 cable through the penetration and a defect at the point where the jacket material was cut for splicing on the cable specimen was the cause of failure. However, it could not be determined which fault occurred first.
Failure was attributed to damage done to the insulation during installation and not as a result of the test exposure. Wyle retested specimen 8-1 during this visit.
Observation of the test is discussed in paragraph D.2 of this report.
Wyle test personnel began isolating conductors on specimen 8-2 (40 year accelerated aging) and experienced continued failures. Upon inspection by Wyle personnel, a hole was found in the jacket with indications that as a conductor failed it damaged adjacent conductors causing them to fail subsequently. Wyle and TVA are still analyzing and evaluating this cable failure.
Two other cable specimens (24-2, 42-2) had to be retested due to test personnel failing to perform the last power check during the HELB test. During retest both cable specimens would not maintain voltage before heat up of the chamber.
Steam was then introduced into the chamber and temperature was maintained at 104 F for two hours.
Both specimens would not hold voltage. A failure analysis was conducted by Wyle for speciment 42-2 (40 year acceleraud aging) however, the cause of failure was not determined.
Wyle's catomer requested a post design basis accident hi-pot test to be performed on specimen 42-2.
The specimen failed the hi-pot and Wyle's customer indicated specimen 42-1 (20 year accelerated aging) will be tested for qualification.
Failure analysis of cable specimen, 24-2 (40 year accelerated aging) by Wyle determined that a faulty instrumentation cable through the penetration caused the failure.
Failure was attributed to damage done to the insulation during installation and not as a result of test exposure. Specimen 24-2 was put back into the chamber at 104 F and held voltage for one hour.
No further testing was anticipated by Wyle.
The NRC inspection team reviewed other test results for both tests which included the normal plus accident radiation exposure and thermal aging. _No nonconformances were noted. The test report for this testing was being prepared by Wyle and will be reviewed during a future inspection.
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ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO.-
99900902/85-04 RESULTS:
PAGE 4 of 6 The NRC inspection team visually inspected various cables from both tests that had completed the qualification test sequence as described in QP 17460-44. The cables were still wrapped on the same mandrels used during qualification and were identified.
The cables showed no significant damage.
2.
Observation of HELB (Retest)
A HELB environmental qualification test was being performed on cable specimcn 8-1 (20 year accelerated aging) for TVA. This specimen was originally powered at 528V-18 amps during first HELB test conducted on October 1,1985 which subsequently failed. The failure analysis for this specimen was discussed in paragraph D.1.
This retest was performed as prescribed in QP 17460-44 except the cable specimen was powered at 133V-1A. Wyle's customer determined that most applications of the cable were at 133V-1A.
The NRC inspection team observed the test set-up prior to the performance of the ramp to verify that, (a) instrumentation was calibrated, (b) accuracies of instrumentation were consistent with the requirements of the QP, and (c) Wyle Quality Assurance test monitor reviewed test set-up and stamped off the test log.
The NRC inspection team observed the initial ramp of the test on November 21, 1985 and made periodic checks during the remainder of the inspection.
Prior to the NRC inspection team departure on November 22, 1985 the cable specimen was performing as prescribed in the QP. Test results will be reviewed during a future inspection.
3.
Visual Inspection of Terminal Blocks The NRC inspection team viewed photographs of GE EB-5/EB-25 terminal blocks that had completed the qualification sequence as specified in test procedure 17655-PRO-3. The terminal blocks were tested for Niagara Mohawk Power Company for use in Nine Mile Point unit one.
The GE EB-5 terminal block showed no visual evidence of i
corrosion on the terminal screws, however, a very light, powdery rust colored residue covered the terminal connections.
The GE EB-25 terminal blocks showed evidence of external corrosion on the terminal hold-down screws.
The marker strip was also discolored, brittle and physically cracked.
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ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO.-
99900902/85-04 PESULTS:
PAGE 5 of 6 A preliminary test report had been prepared and submitted to Niagara Mohawk Power Company.
The NRC inspection team will review the final test report during a future inspection. With respect to the test results, Wyle personnel indicated that the current of approximately 50 ma measured in the output of an instrument circuit (nominal reading of 12 ma) and discussed during a previous NRC inspection was not a leakage current as originally suspected. The cause of the high current output had not been determined by Wyle during this visit.
4.
Technical Evaluation The NRC inspection team performed a technical evaluation and review of test program 17460-39 for qualification of a Masoneilan Electropneumatic valve positioner for TVA for use in Sequoyah Nuclear Power generating plants units 1 and 2.
Documents examined were: Test Report (TR), Qualification Plan (QP), data sheets and a purchase order. The NRC inspection team reviewed the qualification prescribed in the QP and reviewed test results, including the basis for accelerated thermal aging and radiation. The TR and QP and related engineering documents were examined to verify the following:
a)
Adequate test instrumentation and their accuracies were described and used to meet the requirements of IEEE-STD-323/1974.
b)
Equipment interfaces were addressed, c)
Test acceptance criteria were established as described in the test specification or in the design. engineering documents, such as calculations and engineering letters to meet the requirements of IEEE-STD-323/1974.
d)
Same equipment was used for all phases of testing and represented a standard production item.
e)
Environmental conditions were established and described (e.g., pressure and temperature profiles, and thermal aging factors were consistent with those outlined in the test specification or test plan.)
f)
Test results were adequately reduced and evaluated against established acceptance criteria described in customer test specifications or purchase orders.
ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO.: 99900902/85-04 RESULTS:
PAGE 6 of 6 g)
All prerequisites for the given tests as outlined in the i
test specification had been met.
h)
Test equipment included a description of all materials, parts, and subcomponents.
1)
Notice of Anomaly reports were properly documented.
j)
Appropriate margins were applied.
No nonconformances were noted during this review.
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