ML20107M793
| ML20107M793 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/08/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-4-190, GL-84-08, GL-84-8, NUDOCS 8411140266 | |
| Download: ML20107M793 (2) | |
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'AFS 12 87 514 (412) 923-1960 Nuclear Construction Division Telecopy (412) 787 2629 Robinson Plaza, Butiding 2. Suite 210 Pittsburgh PA 15205 November 8, 1984 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. Darrell G. Eisenhut, Director Division of Licensing Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Identification of Backfit Requirement Number 28 Gentlemen:
In a letter to Duquesne Light Company (DLC) dated September 19, 1983, the NRC transmitted the Power Systems Branch, Mechanical Section questions resulting from review of the Beaver Valley Power Station Unit 2 (BVPS-2)
FSAR.
Question 430.74 states, "The engine munted components and piping and certain other component s listed in the various sec t ions of 9.5 and Table 3.2-1 are designed and manuf actured to DEMA standards and/r e manufacturer's standards and are seismic Category I.
This is not in accordance with Regula-tory Guide 1.26 which requires the entire diesel generator auxiliary systems be designed to ASME Section III Class 3 or Quality Group C."
Regulatory Guide 1.26 states, "... systems not covered by this guide, such as... diesel engine and its ge nerators and auxiliary support systems, diesel fuel, should be designed, f abric at ed, erected and tested to quality standards commensurate with the safety function to be pe r f o rmed.
In addition, standard review plan Sections 9.5.4 through 9.5.8 which identify review procedures for the various diesel generator auxiliary systems, do not specify Regulatory Guide 1.26 as an acceptance criterion.
The Power Systems Branch position is a new interpretation of the SRP and the Regulatory Gc;de.
The controls of 10CFR50.109, GNLR 84-08, and NRC Manual Chapter 0514 identify the requirement as a backfit.
DLC requests that the proposed requirement be submitted to NRC management for approval, in accordance with the Of fice of Nuclear Reactor Regulation (NRR) procedure for management of plant specif ic backfitting, prior to transmittal as a licensing requirement.
It also appears that this requirement is being imposed on a generic basis and should be brought to the attention of CRGR.
DUQUESNE LIGHT COMPANY n
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rUnitcd Sectes Nuclsgr Rsgulatory Commission Mr. Darrall G. Eigennut,*Dirsctor Page 2-GLB/wjs Attachment cc:
Mr. H. R. Denton, Director (NRR)
Mr. G. W. Knighton, Chief.
Mr. B.. K. Singh, Project Manager Mr. V. Stello, 'Jr., DEDROGR Mr. G. Walton, NRC Resident Inspector i
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