ML20134H710
| ML20134H710 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/23/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-5-121, NUDOCS 8508290123 | |
| Download: ML20134H710 (1) | |
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e Pittsburgh, PA 15:05 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Eliminaton of Arbitrary Intemediate Pipe Breaks
REFERENCES:
- 1) DLC letter 2NRC-5-042, dated March 1221, 1985, 1985
- 2) NRC letter to DLC dated May Gentlemen:
In Reference 1, Duquesne Light Company (DLC) mquested approval to eliminate arbitrary intemediate pipe breaks in high energy piping systems.
The response in Reference 2 concluded that the request was found to be acceptable.
The purpose of this letter is to clarify two points as follows:
1.
For ASME Code Class 1 piping the stress criterion for postu-lating intemediate breaks is 3.0 Sm instead of 2.4 Sm. Referent.e 1 refers to the criteria of Branch Technical Positions ASB 3-1 and MEB-1; however the change to the 3.0 Sm value was made in FSAR Section 3.6B.E.1.1.1 in Amendment 8, dated September 1984.
Further clarification was also recently given in FSAR Table 1.9-2 on SP.P Section No. 3.6.2, Amendment 10, dated May 1985.
2.
As described in Reference 1, arbitrary intemediate breaks are being eliminated in certain Non-Nuclear Safety (NNS) systems.
Al though the enclosure to Reference 2 does not specifically address NNS systems, from the cover letter, it is our under-standing that the acceptance applies to all the specific systems identified in the request, including NNS systems.
The foregoing will be reflected in a future FSAR amendment that will revise Section 3.6.
DUQUESNE LIGHT COMPANY By NeNNenh JJS/wjs cc: Mr. B. K. Singh, Project Manager Mr. G. Walton, NRC Resident Inspector 8508290123 850823 PDR ADOCK 050 2