ML19326C327
| ML19326C327 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/26/1973 |
| From: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004220878 | |
| Download: ML19326C327 (3) | |
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p DEC 2 61973
- p Dockct No.
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Arkansas Power & Light Company f ~
ATTN:
Mr. J. D. Phillips
[
Vice President &
Chief Engineer
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Sinth & Pine Strects
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Pine Bluff, Arkansas 71601
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Centlemen:
1 In our letter to you of Decenber 14, 1972 ve requested that you provide us
.R vith analyses and other relevant information needed to evaluate the l
consequences of a high energy line rupture outside containment in p
Arkansas Nuclear One, Unit 1.
That letter furnished criteria you could
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follow in evaluating the effects of such a line rupture. We have H
evaluated your responses as presented in Amendments 36 and 38 to the Final Safety Analysis Report. We are satisfied that you have conducted analyses and made design changes as necessary in accordance with the criteria given in our Dece=bsr 14, 1972 letter. Moreover, we consider that you are co=mitted to an acceptable schedule for completion of the plcnt modifications since your letter of April 23, 1973 co:=iits to do so before the plant is taken above 1% power.
q We have, however, one remaining reservation about the complete acceptability H
of the proposed resolutions. In two locations the large main feedvater
.i and main steam lines are arranged in such a way that a guillotine bresh at a veld night cause unpredictable Zailure of major building structures.
The velds in question are designated in Amendment No. 38 as follows:
In. 38 Figure System Wold No.
A-7 Main Steam 55 Hain Steam 56 A-8 Main Steam 6
r A - 15 Main Feedvater 23 Main Feedvater 24 6
c.1 8004220 h p
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ser DEC 2 01973 2-J. D. Phillips We recognize that these six welds are not terminal points or high stress f}
joints as defined in the enclosure to our December 14, 1972 letter.
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However, your analysis in Amendment No. 38 indicates that these welds p 7 h + S ), a considerable F
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will be subject to 37% to 51% of allowable stress (S A
icyc1 of struas.
p-At these welds the piping is arranged so that, upon a guillotine break,
!?.s the piping could be forced apart and the full force of the blowdown k
released to the compartment involved.
In the case of the main steam l:
aystem, we expect that the steam line tunnel might fail due to overpressure.
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E Full pressure release from the main feedwater system welds noted probably would cause structural failure of the South piping penetration roon.
Although neither of these postulated structural failures is evidently we ruasider it prudent for you to take reasonable steps to further reduce
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an accident more serious in consequence than the design basis for ANO-1, the possibility of their occurrence. Therefore, we will require that U
you provide additional surveillance of the welds centioned above to ensure their integrity during the operating life of the plant. An acceptable technical specification for this surveillance is presented in the enclosure to this letter. We expect to include these or equivalent requirenents in the Technical Specifications for the operating license of Arkansas Nucicar One, Unit 1.
j Sincerely, Original Signed' Voss A. Moore, Assistant Director for Light Water Reactors 2 Directorate of Licensing
Enclosure:
DISTRIBUTION:
Technical Specification AEC PDR ACRS (16)
Local PDR JPanzarella ec: Horace Jewell Docket TR AD's House, Holns & Jcuell LWR Rdg TR BC's 1550 Tower Building VAMoore 5 extra copies Little Rock, Arkansas 72201 JHendrie AKenneke Mr. William Cavanaugh, III DEisenhut h
Production Department OGC fy P. O. Box 551 R0 (3)
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DEC 2 61973 TECIDiICAL SPECIFICATIONS Aussented Inservice Inspection Program for High Energy Lines Outside of Containment Applicability Applies to welds in piping systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures designed specifically to cope with such ruptures.
For Arkansas Nuclear One, Unit 1, this specification applies to six welds in the main steam and main feedwater line,s identified as welds 6, 7, 23, 24, 55 and 56 on Figures A-7, A-8 and A-15 of the Final Safety Analysis Report.
Objective To provide assurance of the continued integrity of the piping systems over their service lifetime.
_ Specifications A.
At the first refueling outage period, a volumetric examination shall be performed with 100 percent inspection of each veld in accordance with the requirement of ASME Section XI Code, Inservice Inspection e
of Nuclear Power Plant Components, to establish system integrity and baseline data.
B.
The inservice inspection at each weld shall be performed in accordance with the requirements of ASME Section XI Code, Inservice Inspection of Nuclear Power Plant Components, with the following schedule:
(The inspection intervals identified below sequentially follow the baseline n==ination of A above).
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