ML19326C248
| ML19326C248 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/25/1977 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| References | |
| 1-117-14, NUDOCS 8004220819 | |
| Download: ML19326C248 (3) | |
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DISTRIBUTION AFTER ISSUANCE OF OPERATING LICENSE u.s. Nucs. nan asaut.Arcav ceumissig,3
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l Mr. D. K. Davis Little Rock, Arkansas 37,,,g,3 9, g Daniel H. Williams
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Concerns NRC request for information re. fracture toughness & potential for lamellar tearing of steam generator &
reactor coolant pump supporte materials..
FLANT NAME:
Arkansas Unit No.1 RJL 11/28/77 (2-P) 40 & s9k
?AFTTY FOR AC"" CN/INFORMATICN i 19PETCM CRTEF: (7)
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f H EL PI N G BUILO A R KA N S A S A R K ANS AS POW E R & LIG HT C:O M P A N Y PO. Box 5S1 LIT TLE AOCK. A AK A N S AS 72203. t501137 9 -4000 Evember 25. 1977
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1-117-14 Off N' c,
Director of Nuclear Reactor Regulation
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Mr. D. K. Davis, Acting Chief c).
Operating Reactors Branch #2 p% A,j.
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Docket No. 50-313 License No. DPR-51 Fracture Toughness 6 Potential for Lamellar Tearing of Steam Generator
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G Reactor Coolant Pump Support Materials (File:
1510)
Gentlemen:
Your letter of September 14, 1977, requested that we provide infomation to seven (7) items concerning support materials of steam generators and reactor coolant pumps at Arkansas Nuclear One-Unit 1 (ANO-1). Your letter also requested our evaluation of the fracture toughness of our steam generator and reactor coolant pump support materials but this request was negated by telecon with your Mr. R. Snaider on October 26, 1977.
Although the necessary work has been authorized and the required work activities are in progress, we find that your request to supply the support material infomation within sixty (60) days after receipt of your September 14, 1977, letter does not allow sufficient time for research of antiquated files and review of the information obtained.
Furthermore, the use of critical personnel involved in the ANO-2 pipe hanger effort would be required to supply the reactor coolant pump support material information sooner than proposed below. As indicated in Mr. Cavanaugh's November 17, 1977, letter to Mr. Stolz, the pipe hanger effort on ANO-2 is clearly on the critical path for ANO-2 constmetion completion and is currently the cause of significant delays.
Therefore, as the requested information becomes available for transmittal (early January 1978 for the steam generator support materials and late January 1978 for the reactor coolant pump support materials), we will forward each to you.
p.,n y T AX A AYING. INVESTOR OWNEO MEMBER MlOOLE SOUTH UTILITIdB SYSTEM
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If you should'have further coments and/or questions conderning our reply, please advise.
Very truly yours,
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aniel H. William Manager, Licensing IINE191Edtw
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