ML18219D110
| ML18219D110 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/22/1978 |
| From: | Bien F Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co) |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18219D110 (15) | |
Text
NRC.FO~ 195 (2-76)
U.S. NUCLEAR REGULATORY(~ISSION DOCKET NUMBER
-3/
NRC DISTRIBUTION FoR PART 60 DOCKET MATERIAL FILE NUMBER TO:
Mr, Edson 0 ~ Case FROM:
Indiana 6 Michigan Power Co, New York, N,Y.
10004 Frank N, Brien DATE OF DOCUMENT 03 22 78 DATE RECEIVED 05 03 78 QeCTTER JB ORIGINAL OCOPY DESCRIPTION QNOTORIZED
~C LASS IF I E D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED
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Response
to NRC request of 03/20/78
~ ~,Furnishing info concerning environ quali-fication for equipment inside containment for steam line break and environ qualification tests on safety-related elect terminations inside containment, re final conditions requir to be met prior to proceeding above 20% of rat pwr for Subject Facility. ~,w/att supporting in Notarized 03/22/78 ~ ~ ~ ~
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ENVIRON ANALYSIS DENTON G MULLER GOSSICK I(l STAFF ENGINEERING LITO CTORS F'%VIROVi TECH ERNST BALLARD LOOD NAGEMENT INS RFACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK T 6 I ALTZMAN BAER TLER e~cwM TE TECH GAMMILL 2
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2 Docket No.
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74 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor.Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
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Donald C. Cook Nuclear Plant Unit 02 Docket No. 50-316 From March 16-21, 1978 a test was conducted at the Westinghouse Electric Corporation Canada in Hamilton, Ontario to demonstrate the ability of safety related terminations used inside the containment of Unit 2 at the Donald C. Cook Nuclear Plant to maintain electrical integrity and operability during and after a postulated steam line break incident.
The tested terminations are identical in design, fabrication and installa-tion to those in Unit 2 of the Donald C. Cook Nuclear Plant.
The purpose of this discussion is to describe the test conducted and to present the overall test results.
A formal test report is under preparation.
The termination configurations tested consisted of four three phase sets of motor connections (2 consisting of 010 cable with Scotch 23 tape plus neoprene in an enclosure, and 2 consisting of 010 cable with Bishop 962 tape in an enclosure) and 4 three phase sets of power cable splices (2 consisting of 410 solid Kapton wire to 410 Hypalon cable butt spliced with Raychem Class N material and 2 consisting of 410 solid Kapton to 410.stranded Kapton butt spliced with RT876 heat shrink tubing) and four three phase sets of Cutler-Hammer Power Terminal Blocks (2, 70 ampere blocks and 2 125.ampere blocks).
All test specimens were connected with 410 or 02 AWG conductors and electrical test connections are made to each point.
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The test terminations were subjected to the following environmental profile:
340 (min.) for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 12 psig (min.).
2.
Reduced temperature over approximately 30 minutes to 250 F at 12 psig (min.) and then held at a minimum of 250 for 117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br />, 12 minutes.
3.
Five minutes after the 3'40 F temperature was
- reached, a chemical environment, was created in the test autoclave.
This environment was created by spraying a 2500 ppm boric acid solution, buffered by NaOH to a pH of 9 to 10, into the autoclave.
This environment was maintained for the duration of the test.
Prior to the start of the test, with the test termina-tions in the autoclave and under room ambient conditions, the insulation resistance of all test items were measured individually and in series using a 500 V DC insulation tester.
During the test, the terminations were continuously energized at 600 volts AC, 5 amps.
The autoclave temperature,
- pressure, test. circuit currents and voltages were measured and recorded hourly.
Insulation resistance was measured at intervals during the course of the test.
A test specimen is considered to pass the tests if, with all three phases energized, leakage current, in any one phase does not exceed one ampere.
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Upon termination of the test, a final set of test parameter values were recorded, including insulation resistance.
There was no significant electrical degradation of any of the splices and motor connections during this test.
The auto-clave was depressurized and cooled down to approximately room ambient conditions.
Data was recorded to indicate the approximate cooldown rate.
After the terminations had cooled sufficiently, they were removed from the autoclave and visually inspected for damage and degradation.
None was found.
A deviation in leakage readings on one of the two
$ 10 Solid Kapton wire to 010 stranded Kapton wire splices during the test was proven by post test evaluations to be a
problem in the lead in wires to the test specimen external to the specimen and not in the test specimen (i.e. splice) itself.
Samples of both the 125 ampere and 70 ampere Cutler-4 Hammer terminal blocks exhibited leakage current behaviors above those acceptable under the test criteria.
The results of the tests on these blocks are still being evaluated but preliminary evidence indicates that marker strips on the terminal blocks melted and water collected in the bottom of the boxes.
These two items in all probability contributed to the high leakage current problem and can be corrected.
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The Westinghouse Corporation's Quality Assurance Department and American Electric Power Service Corporation personnel maintained surveillance over the conduct of the test to assure compliance with test procedures.
Third party veri-fication of adherence to test procedure and instrument calibra-tion -requirements was provided by Mr. Warren Dunning of the Franklin Institute.
In summary, the successful completion of the test described demonstrates that these safety related splices and motor connections used inside the containment of Unit 2 at the Donald C. Cook Nuclear Plant are fully capable of maintaining electrical integrity and operability duxing and after a postu-lated steam line break incident.
Additional testing will be necessary to prove the electrical integrity and operability of the power terminal blocks.
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