ML19320A210
| ML19320A210 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/17/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004210512 | |
| Download: ML19320A210 (1) | |
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DISTRIBUTION:
AEC PDR Local PDu Docket File DR R/F
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PWR-4 File JUL 171972 SHHanauer RSBoyd
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Dockst No. 50-313 FSchroeder RMaccary DKnuth RTedesco Arkansas Power & Light Company ATIN:
Mr. J. D. Phillips efs Vice President & Chief Engineet Sixth and Pine Streets C
Pine Bluff, Arkansas 71601 Regulatory Operations (3)
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Project Leader Licensing Assistant Enclosed for your information is a copy of ob*leSter to the Babcock &
Wilcox Company (B&W) requesting additional information on their topical report entitled " Study of Discontinuities in Control Rod Drive Motor Tube Extensions," BAW-10047 dated June 1972. B&W has indic.ted that the information in this report is applicable for Arkansas Nuclear One -
Unit 1.
Please contact us if you desire any discussion or clarification of our needs as specified in the enclosed letter.
Sincerely,
1 Original cip13d by R. C. DeYoung R. C. DeYoung, Assistant Director for Pressurized Water Reactors Directorate of Licensing
Enclosure:
B&W 1etter requesting 7O D
additional information rJ Oc cc: Borace Jewell, Esquire OM'
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ATOM'O ENERGY COMMISSION WASetiNGTON, D.C. 20545
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JUL 1 7 372 f
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D bd-Mr. James F. Mallay R
Manager, Licensing q1 qg }j }
Nuclear Power Generation d
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Dear Mr..Mallay:
We have completed our initial review of,our topical report BAW-10047,
" Study of Discontinuities in Control Rod Drive Motor Tube Extensions,"
and find that we need additional information to complete our evaluation.
Much of The specific infornation required is listed in the enclosure.
2 at a meeting in Bethesda, Maryland.
In general, we find your investigation into the cause of the discontinuities However, before our and your subsequent inspecticn program adequate. final accept information requested, revision or supplementation to your topical report to reflect this additional information, and incorporation of this topical In report with revisions or supplemen'ts in all appropriate applications.
addition, we will also require a testing program and surveillance program.
The testing progran w'ill verify the predictions of the tenperature response of the C2DM tuba extensions on a statistically significant ncaber of assemblies during the precperational and startup tests for the first The surveillance program will facility utiliting these redesigned unifs.
assure that the naximum temperature of the CRDM tube extension does not approach theerevised design te=perature during plant operation.
The addi:1.onal information and your response to our requirements should be provided in accordance with the review schedules we have established fo We understand that you are those applications affected by this matter.
aware of these schedules through your nor=al communication channels with the respective applicants and vill inform them of your schedules for responding to our needs.
w JUL 17 'ON Mr. James F. Mallay 2 --
Please contact us if you desire any discussion or clarification of the material required.
Sincerely,
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- *** f R. C. DeYoun'g, Assistant Director for Pressurized Water Reactors Directorate of Licensing
Enclosure:
Request for Additional Infornation e
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REQUEST FOR ADDITIONAL INFORMATION BABCOCK & WILCOX TOPICAL REPORT, BAW-10047 l
1.
Provide more information describing the conditions of each test in Table 7-1, such as air flow conditions, insulation, thermal barrier, and drive activity.
2.
Supply all data used to conclude that 450*F is the maximum temperature which could occur. Supply data used to justify statements 3, 4, and 5 l
on page 7-2.
3.
Define the drive activities, cycling and intermittent tripping, to include the speed, frequency and length of the rod movement for each activity.
4.' Was the test facility used for these tests shown in B&W topical report, BAW-10029? If so, provide the flow velocity in the vicinity of the CRD Motor Tube flange and compare this to the Oconee 1 hot functional test results and updated velocities from your additional model tests.
5.
Supply all test results from Oconee 1 that would be appropriate for this subject.
6.
Provide the maximum temperature increase expected for one full length trip.
7.
For the situation where stator cooling water is lost, but electric power to the stator is still supplied, (1) show that the integrity of the reactor coolant pressure boundary and the functionality of the control rods are maintained, or (2) show that sufficient time and suitable instrumentation are available to prevent the above from happening.
In either case provide a conservative " worst case" analysis including the effec (
of single failures.
8.
Provide the " worst operating conditions as defined by the design speci-fications" referred to on page 7-2.
9.
Revise your predicted maximum motor tube extension to include the maximum outlet temperature of 619'F.
10.
State the validity of these tests and analyses for all types (A,B,C) of B&W CRD.
11.
Discuss the effect of venting the CRD on the notor tube extension temperature.
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2-12.
Provide data to show the transient temperature behavior of the extension for the various test and operating conditions.
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