ML20238C718
| ML20238C718 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/03/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Carey J DUQUESNE LIGHT CO. |
| References | |
| TAC-64898, NUDOCS 8709100320 | |
| Download: ML20238C718 (1) | |
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September 3,1987 -
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' Docket No. 50-412 Distribution: Mt File NRC & LPDRs Branch 7UB; PTam SNorris' ACRS 10 EJordan Mr. J. J. Carey, Senior Vice President JPartlow FLitton-Nuclear Group SVarga BBoger Duquesne Light Company OGC-Bethesda
' Post Office Box 4
,i Shippingport, PA 15077
Dear Mr. Carey:
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT 2 - ASME III CODE CASE 1481-1 (TAC #64898) l On March 12, 1987, Duquesne Light Company requested staff approval to use ASME III Code Case 1481-1, " Elevated Temperature Design of Section III, Division 1, Class 2 and-3 components," for the: construction of the thermal hydrogen 1
recombiners installed at the Beaver Valley Power Station, Unit 2.
The Beaver Valley Power Station, Unit 2, thermal hydrogen recombiners were constructed by Rockwell International to the requirements of Class 2 components of Section III, ASME Code,1977 Edition including Winter 1978 Addenda, and Code Case 1481-1. Code Case 1481-1 was approved by the Council l
on March 1, 1976, and annulled after reaching the mandatory amendment date.
l The design-allowab' stress intensity values for the Type 304 stainless steel employed in the construction of the recombiners are shown in Table UHA-23 of Section VIII of the ASME Code. The total service time above 300*F is estimated not to exceed 10,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
j Code Case 1481-1 is acceptable and approved by the Commission for use for the construction of the thermal hydrogen recombiners at the Beaver Valley Power Station, Unit 2.
Although the Code Case was annulled on March 1,'1979, it was active during the construction and procurement of the recombiners. Your use of the Code Case should be documented in the FSAR.
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This completes our action on your March 12, 1987_ submittal. The review was performed by Mr. F. Litton.. If you have any questions, please feel free to contact your project manager, Mr. P. Tam.
Sincerely,
/S/
John F. Stolz, Director Project Directorate I Division of Reactor Projects I/II cc: See next page f'k t
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