ML20072F642
| ML20072F642 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/21/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 IEB-79-01B, IEB-79-1B, NUDOCS 8303240378 | |
| Download: ML20072F642 (4) | |
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,g DUKE POWER GOMPANY P.O. HOX 33180 CHARLOTTE. N.C. 28242 IIAL H. TUCKER retgenoys mu.....m go.y o m 33,
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March 21, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370
Dear Mr. Denton:
The NRC/FRC Technical Evaluation Report (TER) concerning environmental qualifica-tion of electrical equipment identified two equipment items in Category II.B, Equipment Not Qualified. On February 25, 1983, Duke Power Company provided information to the NRC concerning these items in support of the McGuire Unit 2 license. Based on the February 25 submittal, the Staff stated in the McGuire Unit 2 SER Supplement 6 that the information provided justified interim operation at no more than 5 percent power but did not demonstrate qualification.
Duke Power Company has reviewed the concerns stated in the TER for the Category II.B items as well as the information submitted on this matter on February 25, 1983. Based on our review, we are providing the attached information which addresses the TER concerns and demonstrated qualification of the two equipment items in question.
Duke Power Company has reviewed the TER for proprietary considerations. The TER does not contain sufficient proprietary information to preclude disclosure l
and, accordingly, can be publicly released. However, it is requested that all proprietary test reports provided to the NRC be returned to Duke' Power Company as previously requested.
Please) advise if there are any questions regarding this matter.
s Very truly yours, d
-e Hal B. Tucker GAC/php Attachment D
l B303240370 830321 PDR ADOCK 05000369 P
Mr. Harold R. Denton, Director i
March 21, 1983 Page 2
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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. W. T. Orders NRC Senior Resident Inspector McGuire Nuclear Station
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a MCGUIRE NUCLEAR STATION ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT l
EVALUATION OF NRC/FRC TECHNICAL EVALUATION REPORT SECTION II.B The NRC/FRC Technical Evaluation Report (TER) concerning environmental qualifi-cation of electrical equipment identifies two equipment items in Category II.B, Equipment Not Qualified. Duke Power Company has reviewed the two equipment items in this category and provides the following discussion supporting the qualification of each item.
NRC/FRC Equipment Item 27 - Rotork Model NA-2 Valve Actuators Located Outside Containment Statement of Problem:
Following exposure to 212 F steam environment for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the torque switch mechanism in the Rotork NA-2 style actuator failed resulting in the motor running to stall and burning up following the actuation of a valve in the close direction. Reference Rotork Test Report TR-3025.
Background Information: The torque switch mechanism of the NA-2 actuator was The NA-2 torque switch mechanism (qualification testing as reported in TR-3025.
the component which failed during helix) is made of a thermoplastic material, nilotron, which at approximately 180 F becomes pliable resulting in failure to actuate the torque switch at the end of valve stroke. As noted in our response to the McGuire Unit 1 equipment qualification SER, TR-3025 demonstrates that at least one valve operation is available after the torque switch mechanism has failed; therefore, the valves are capable of moving to their safety position.
It should be emphasized that the torque switch failure will occur only after the valve has reached its safety position and will not affect the valves' ability to remain in its safety position.
Duke has analyzed all NA-2 actuator applications at McGuire and has determined that once the actuator has reached its safety position, no additional safety operation is required. Additionally, all NA-2 actuators at McGuire are located in the Auxiliary Building and access is possible following a pipe rupture, thus allowing for manual operation (by handwheel), if needed in the long term.
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Conclusion:==
Based on the Rotork NA-2 test report TR-3025 and the above discussion, Duke has determined that these actuators are capable of performing their safety function and that continued use of the NA-2 actuator in its current applications is acceptable.
NRC/FRC Equipment Item 39 - Rosemount Transmitters Model ll536A9 (RCS Wide Range Pressure Transmitter) Located in the Annulus Statement of Problem: Based on the FRC review, the Rosemount ll53GA9 transmitter is identified as not qualified for accident conditions.
Reference is made to the Rosemount qualification report submitted as part of the H. B. Robinson facility SER response. This ' report identifies failed components in the 1153 Series A transmitters due to environmental testing in accordance with IEEE 323-1974.
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Background Information: The applicable qualification document, as referenced in Duke's NUREG 0588 response, is Rosemount Report No. 3788, Revision A.
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report documents results of type testing which qualifies the Model 1153 Series A transmitter for Class lE service in Nuclear Power Generating Stations. This testing followed the guidelines of IEEE 323-1971.
Rosemount Report No. 3788, Revision A documents that the Rosemount Model 1153 Series A transmitter successfully completed applicable testing with no significant anomilies.
Qualification temperature was 350 F, relative humidity 100% and radiation dose 7
4X10 R.
The accident environment for the McGuire Units 1 and:2 RCS widaorange pressure transmitters, logated in the annulus, is 142 F, relative humidity 100%
and radiation dose 1.2X10'R.
Pressure, steam, and chemical spray environments are not applicable environmental parameters. With regard to transmitters 0-ring seal integrity, station procedures will require 0-ring seal replacement consistent with transmitters calibration intervals.
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Conclusion:==
The Rosemount report referenced in the H. B. Robinson SER response does not apply to the Duke transmitters. Therefore, based on Rosemount's Report No. 3788, Revision A and the above discussion, Duke has determined that the subject transmitters are qualified to perform their safety function in the annulus accident environment as identified in the McGuire NUREG 0588 response.
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