ML20209D752

Submits Review of Section 3/4.4.9, Pressure Temp Limits, & Bases,Per 841217 Memo.Section Acceptable,Except Heatup & Cooldown Curves,Figures 3.4.2 & 3.4.3,applicability Must Be Reduced Up to 5 EFPY

ML20209D752
Person / Time
Site:	05000000, Diablo Canyon
Issue date:	01/08/1985
From:	Johnston W Office of Nuclear Reactor Regulation
To:	Crutchfield D, Crutchfield P Office of Nuclear Reactor Regulation
Shared Package
ML082410749	List: ML20209A984 ML20209B531 ML20209B624 ML20209B724 ML20209B847 ML20209B894 ML20209C131 ML20209C225 ML20209C292 ML20209C320 ML20209C516 ML20209C643 ML20209C669 ML20209C675 ML20209C698 ML20209C705 ML20209C710 ML20209C715 ML20209C720 ML20209C836 ML20209C847 ML20209C848 ML20209C876 ML20209C881 ML20209C908 ML20209C921 ML20209C969 ML20209C975 ML20209C981 ML20209C993 ML20209D004 ML20209D012 ML20209D018 ML20209D030 ML20209D038 ML20209D044 ML20209D045 ML20209D071 ML20209D089 ML20209D114 ML20209D127 ML20209D130 ML20209D135 ML20209D139 ML20209D146 ML20209D154 ML20209D211 ML20209D218 ML20209D230 ML20209D235 ... further results
References
FOIA-86-197, RTR-REGGD-01.099, RTR-REGGD-1.099 NUDOCS 8501140056
Download: ML20209D752 (2)

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NUCLEAR REGULATORY COMMISSION

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g waswincrou. o. c. 2osss JAN 8 1985 Docket No:

50-275/323 MEMORANDUM FOR:

Dennis M. Crutchfield, Assistant Director for Safety Assessment Division of Licensing FROM:

William V. Johnston, Assistant Director Materials, Chemical & Environmental Technology Division of Engineering

SUBJECT:

DIABLO CANYON UNIT 2 - COMPLETION OF REVIEW OF TECHNICAL SPECIFICATIONS In your memorandum of December 17, 1984 you requested that we review the technical specifications, which were enclosed in the PG&E letter DLC-84-309 dated 09/21/84. We have reviewed section 3/4.4.9,

" Pressure / Temperature Limits" and their bases.

Our conclusion is that the section is acceptable except that the heatup and cooldown curves, Figure 3.4-2 and 3.4-3, are applicable for 5 effective full power years (EFPY) and 6 EFPY for Unit 1 and Unit 2, respectively.

If these curves are to be used for both units, the applicability must be reduced to "up to 5 EFPY."

The period of applicability for these curves depends upon the amount of radiation damage to the limiting beltline materials in each unit.

We have utilized the method recommended in Regulatory Guide 1.99 Rev.

1., " Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials," and the materials properties and neutron fluence estimates for the beltline reported in the technical specification bases for Units 1 and 2 to determine the amount of radiation damage.

The licensee appears to have used Figure B 3/4.4-2 in the bases to determine the amount of radiation damage.

For high copper weld, this Figure is non-conservative.

Since both units have high copper welds, this would be the source of the error in their heatup and cooldown curves.

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See Next Page

Contact:

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