ML16341D907
| ML16341D907 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/13/1973 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Searls F PACIFIC GAS & ELECTRIC CO. |
| Shared Package | |
| ML16341D906 | List: |
| References | |
| NUDOCS 8610150224 | |
| Download: ML16341D907 (8) | |
Text
Docket Nos ~ 50-275 and 50-323 AUG 13 m Pacific Gas and Electric Company A'ITN:
Mr. Frederick T. Searle Yice President and General Counsel 77 Scale Street San Francisco, California 94106 Gentleaen:
In accordance vith the Coiiasion's regulations (Section 2.101 of 10 CFR Part 2) ve have conducted a preliE}inary review of your tendered application for licensee to operate tvo nuclear pater reactors at your Diablo Canyon site.
Aa a result of our reviev, we have concluded that your application is not sufficiently cocsplete for us to initiate our detailed review.
'this ccmclusion is due to the extensive nature of the deficiencies identified in.the Final Safety Analysis Report, and the fact that kmviaion 1 of the Standard Foriat and Content of Safety Analyaia Reporta for Nuclear Power Plants (October 1972'as not folloved in the preparation of your FSAR.
%e principal areas of deficiency in the FSAR include tornado design criteria, elope stability, design of Category I atrnctE}re~, protection against dyna}Sic effects associated with pipe rtspturo, and auxiliary ayateas.
Enclosure No.
1 ideutifiee in detail the deficiencies found in the FSAR.
Enclosure 1 also contains requirwents for farther factual infoasation and Justification on other quaationa identified during our prelissinary review that are not apecifioally required by"Revision 1 of the Standard Pors}at Iheae.iteis have been identified by an asterisk.
Subeittal of this additional tnfoaatLon prior to docketing is not aandatory, but vill help to speed up the detailed review of your application.
Enclosure No, 2 1iata additional financial inforIsetion that will be required to cos}plate our review.
this additional inforaatfon aha}id be aubs}itted at the earliest possible date~ Wt ia also not required for acceptance and docketing of the application.
Incorporation into your application by reference of yae Eavireaental
- Report, Supplements j and Appendicea will be acceptable9 ao that no further fnfoa}etim will be required in this area at the present tis}e.
OFFICE 0 SURIIAME P
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t We vould appreciate hearing'from you in the near future regarding your estimated schedule for resubmittal of the Diablo Canyon 1 and 2 applica; pion. If you vish, ve vill be happy to meet vith you to discuss the deficiencies and other requirements identified in Enclosure No. l.
Sincerely, ChfgiIIal Signed ~
A. Gbunbia
- h. Giambusso, Deputy Director for Reactor Pro)acts Directorate of'icensing Enc losures:
1.
PSAR Deficiencies and Other Requirement>>
2.
Additional Pinancia 1 Information Required 3.
Docum>>nt (8'I 4.
Regulatory Staff Position on Shift Manning for Nucleaz Pover Plants cc v/encl>>:
W. J. Lindblad, Pro)ect Engineer Pacific Gas and Electric Oompany 77 Seal>> Street San Prancisco, California 94106 P. h. Crane, Jr., Attorney of Record Pacific Ga>> and Electric Company 24S Market Stre>>t San Francisco, California 94106 DISTRIBUTION:
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19-0. AUXILIARY'SYSTEMS 9.1 Fuel Stora e and Handlin The following areas in this Section are deficient:
a.
%he identification and quantification of the external loads and forces taken into account in the design of the new fuel rack and spent fuel racks, including crane uplift.
b.
.'Ihe identification of the design codes used in the design of the spent fuel racks.
c.
A discussion of preventative measures included to preclude heavy objects from dropping on spent fuel.
d.
A discussion that demons'trates material compatibility in the pool.
e.
Whether the seismic Category I make-up supply for the spent fuel pool satisfies the recommendations of Regulatory Guide 1.13.
f.
The classification of the seismic category of the spent fuel cooling and clean-up system components.
g.
The incorporation of a safety evaluation that includes a failure mode and effects analysis on the spent fuel cooling system, including the ability to assure pool cooling with a full core.
h.
A description of how new fuel is received and handled and how spent fuel is handled and shipped.
i.
A complete discussion of the spent fuel cask crane, a safety evaluation of the crane and its role in refueling, including the design measures provided that prevent or protect the spent fuel and safety related equipment from a cask drop.
The following areas in this Section are deficient:
a.
An evaluation of the safety implications of the Vnit 1 and Unit 2 cross connections in the Auxiliary Saltwater System.
b.
An evaluation that demonstrates the ability of the Auxiliary Saltwater System to function during adverse environmental conditions including periods of high and low water.
ENCLOSURE 6
PGEE FSAR September 1973 (pages 9.1-1 through 9.1-28)
(Item 13)
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