ML20136H043
| ML20136H043 | |
| Person / Time | |
|---|---|
| Issue date: | 11/07/1985 |
| From: | Moist R, Potapovs U NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20136H029 | List: |
| References | |
| REF-QA-99900902 NUDOCS 8511250023 | |
| Download: ML20136H043 (11) | |
Text
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ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION INSPECTION NO.-
99900902/85-03 DATE(S h 09/30/85-10/1-4/85 ON-SITE HOURS: 68 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 35807 ORGANIZATIONAL CONTACT: Mr. E. W. Smith, Director, Contracts and Purchasing TFIFPHONF NilMRFR-(205) R37-4411 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 flow testing, mechanical and hydraulic snubber testing, decontamination, and repair.
ASSIGNED INSPECTOR: / Gmdhd M M-A[
// f6
- 3. N. Moist, Equiprment Qualification Inspection Date Section (EQIS)
OTHER INSPECTOR (S):
E. H. Richards, Sandia National Laboratories (SNL)
J. Grossman, S
/
APPROVED BY:
C4 ih%to ll '/T U. Potapovs, Section Chidf, E0IS 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: Browns Ferry 1, 2 & 3 (50-259, 50-260, 50-296),
Sequoyah-1, 2 (50-327, 50-328), Watts Bar 1, 2 (50-390, 50-391), Bellefonte 1, 2 (50-438, 50-439), Nine Mile Point 1(50-220) 8511250023 851121 PDR G A999 EXIWYLE 99900902 PDR
e 6
ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO - 99900902/85-03 RESULTS:
PAGE 2 of 5 A.
Violations None.
B.
Nonconformances None.
C.
Unresolved Items None.
D.
Other Findings or Comments 1.
Observation of Cable Testing Activities A high energy line break (HELB) Environmental Qualification test was being performed on various cables for the Tennessee Valley Authority (TVA) for use in Watts Bar and Sequoyah Nuclear Power stations. Twenty five cable specimens representing 8 manufacturers and several different insulation systems were included in the test program.
Prior to the test, the NRC inspector and the Sandia consultants (NRC Inspection Team) reviewed Wyle's Environmental Qualification Plan (QP) 17360-44 to verify that; (a) test instrumentation was adequately described, (b) test acceptance criteria was established, (c) environmental conditions were established and described (Pressure and temperature profiles and thermal aging), (d) all prerequisites for the given test had been set, (e) appropriate margins were applied and (f) QP was approved by TVA.
The NRC inspection team reviewed the test results of the dry runs which were performed using masses to simulate the cables.
The inspection team reviewed the test set-up to verify that:
(a) specimens were located in the chamber as specified in the QP, (b) Instrumentation was calibrated, (c) accuracies of instrumentation were consistent with the requirements of the QP, (d) themocouples and pressure transducers were located in the chamber as specified in the QP., (e) Wyle Quality Assurance (QA) test monitor reviewed test set-up and stamped off the test log, and (f) functional tests were performed prior to the test.
f
- e #
ORGANIZATION: WYLE LABORATORIES H"NTSVILLE, ALABAMA INSPECTION REPORT NO - 99900902/85-03 RESULTS:
PAGE 3 of 5 The inspection team observed the initial ramp of the test on October 1, 1985 and made periodic checks during the remainder of the inspection. The ramp time for temperature and pressure was to be on a best effort basis. Approximately three minutes into the test one specimen failed, causing an open circuit.
The specimen was removed from the circuit and the circuit was reenergized. The on-site TVA representative authorized Wyle to extend the high temperature plateau an additional twelve minutes to compensate for the time the circuit was deenergized.
This test anomaly was annotated on a Notice of Anomaly Form by the Wyle test engineer. Analysis and evaluation of the specimen will be conducted by Wyle and TVA at the end of the test when the test chamber is opened. The NRC inspection team will follow up on the disposition of this anomaly during a future inspection. The NRC inspection team reviewed the functional test data after the first 26.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and determined that the test data met the requirements of the QP.
2.
Other Testing An accident (HELB/LOCA) simulation test was being performed on GE EB-5/GE EB-25 terminal Blocks for Niagars Mohawk Power Ccmpany (NMPC) for use in Nine Mile Point Unit One. This test was performed to verify results of a previous analysis performed by NMPC. Two ramps were performed, the first to verify the analysis, the second for informational purposes.
The NRC inspection team reviewed Wyle Test Procedure (TP) 17655-PRO-3 to verify that:
(a) test instrumentation was adequately described, (b) test acceptance criteria was established and (c) environmental conditions were established I
and described (pressure and temperature profiles).
The inspection team observed the set up prior to the performance of the second ramp to verify that:
(a) instrumentation was calibrated, (b) accuracies of instrumentation were consistent with the requirements of the TP and (c) functional tests were performed prior to the test.
The NRC inspection team observed the second saturated steam ramp which was more severe than the first ramp on October 2, 1985. The second ramp was modified from the TP with spray introduced later in the profile which was approved by the customer. A leakage current of i
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ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO -
40900002/85-03 RESULTS:
PAGE 4 of 5 approximately 50 ma was measured in one of the two instrument circuits during the ramp. NMPC and Wyle are planning to analyze the results.
The NRC inspection team will review the first and second' ramp test data on a future inspection.
3.
Visual Inspection of Various Cables and Terminal Blocks The NRC Inspection Team visually inspected various cables and viewed photographs of terminal blocks that had completed the qualification sequence as specified in QP 17460-45. The cables are used inside containment at Sequoyah and Watts Bar Nuclear Power Plants.
Five cable specimens representing four manufacturers were included in the test program.
The cables were still wrapped on the same mandrels used during qualification and were identified. The cables showed no significant damage. The NRC inspection team viewed photographs of the terminal blocks taken after the accident test. Ten of the twenty terminal block terminations were coated with 00W RTV 3140. The terminal blocks showed no significant damage.
A test report was being prepared and will be reviewed during a future inspection. The NRC inspection team however did review QP 17460-45 to verify that:
(a) test instrumentation was adequately described, (b) acceptance criteria were established, (c) environmental conditions were established and described (pressure and temperature profiles and thermal aging) and (d) apprapriate margins were applied.
4.
Technical Evaluation The NRC Inspection Team performed a technical evaluation and review of test program 17521-1 for qualification of motor insulation systems used inside containment for use in Nuclear Power Plants for TVA.
Documents examined were: Test report (TR), QP, Data Sheets and a Letter. 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.
l O
ORGANIZATION: WYLE LABORATORIES HUNTSVILLE, ALABAMA REPORT INSPECTION NO.-
99900902/85-03 RESULTS:
PAGE 5 of 5 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.
g)
All prerequisites for the given tests as outlined in the test specification had been met, h)
Test equipment included a description of all materials, parts, and subcomponents.
i)
Notices of Anomalies were properly documented.
j)
Appropriate margins were applied.
No nonconformances were notedidering this review.
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