ML19320A192
| ML19320A192 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/29/1972 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004210497 | |
| Download: ML19320A192 (1) | |
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Docket No. 50- 313 RCDeYoung AUG : 9 1371 DSkovholt FSchroeder RMaccary DKnuth RTelesco Arkansas Power & Light r~--
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Mr. J. D. Philif==
PWR Branch Chiefs Vies Presidaat & Chief Engineer RWKlecker Sixth and Plaa Streats OGC Pine Bluff, Arkansas 71601 R0(3) l Project Leader Gentlemen:
Licensing Assistant DDavis The Final Safety Analysis Esport for Avhammas Nue1mme One - Mait referescas a vibration analysis and test Program for prototype reactor internals.
letter to the Babcock & Wilcox Company concernfag this s Please contact as if you desire any discussion or clarlficatio material requested in tha== eta-ad latter.
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.y R. C. DeYoung, Assistant Director for Pressurized Water Basetors Directorate of Licensing Emelesure:
As atstad Ho' race Jewell, Esq.
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House, Molms & Jewell 1550 Tower Buildias Little Esek, Arkansas 1
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AUG 2 01572 Mr. James F. Mallay DUPLICATE DOCUMENT Manager, Licensing j
Nuclear Power Generation Entire document previously i
Babcock & Wilcox entered into system under:
Lm bu ginia 24550 ANO s
Dear Mr. Mallay:
No. of pages:
We have been advised that Babc concerning (1) the assessment of damage to the Oconee Unit 1 reactor internals due to flow induced vibration, (2) the redesign of the reactor internals of B&W reactors to reduce flow induced vibration and (3) the vibration predictions and monitoring equipment for the Oconee Unit 1 vibration testing program.
Because these reports are an essential elenent of our evaluation of applications for operaring licenses for several facilities, i.e., Oconee Nuclear Station Units 2 and 3, Three Mile Island Nuclear Station, Unit 1, Arkansas Nuclear One, Unit 1, and Rar.cho Seco Nuc1 car Generating Station, we wilc. need these topical reports on or beftrc September 15, 1972.
If you are unable to comply with this schadule_, it is likely that the overall schedule for completing the licensing review for these projects will have to be extended.
Because B&W has designated Oconec Unit 1 as the prototype reactor for vibration measurements, the results of these Oconee Unit 1 measure =ents will affect a number of facilicies.
If Cconee Unit 1 is not properly established as an acceptable prototype, another facility will need to be established as a prototype or each specific facility will need to perform a complete program of vibration testing as defined in Safety Guide 20, " Vibration Measurements on Reactor Internals", before any licensing action can be completed. Due to the number of projects potentially affected, we believe it prudent to consider contingency plans at this time. Please inform us of your proposed course of action in the event that you are not able to establish the Oconce Unit 1 as an acceptable prototype.
Please contact us if you desire any discussion or clarification of the material requested.
Sincerely, k%w t, -
R. C. DeYoung, Assistant Director for Pressurized Water Reactors Lirectorate of Licensing F#d 79//0 yg 7j
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