ML20081J857

Forwards Rept GE-NE-523-A166-1294, LaSalle Unit 1 RPV Surveillance Matls Testing & Analysis, in Accordance W/App H of 10CFR50

ML20081J857
Person / Time
Site:	LaSalle
Issue date:	03/23/1995
From:	Benes G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20081J858	List: ML20081J857 ML20081J864
References
NUDOCS 9503280224
Download: ML20081J857 (2)

Text

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March 23, 1995 U.S. Nuclear Regulatory Commission Attn: Document Control Desk  ;

Washington, D.C. 20555

SUBJECT:

LaSalle County Nuclear Power Station Unit 1 Reactor Vessel Material Surveillance Program-Appendix H Facility Operating License NPF-11 NRC Docket 50-373 ,

In accordance with Appendix H of 10 CFR 50, Commonwealth Edison Company (Comed)is submitting the following report, GE-NE-523-A166-1294, DRF 137-0010-7, LaSalle Unit 1 RPV Surveillance Materials Testina and Analysis, March 1995.Section III of Appendix H, " Report of Test Results", requires a summary ,

technical report to be submitted within one year after Reactor Vessel Material Surveillance Specimen Capsule withdrawal. The LaSalle Unit 1 300 degree azimuth location Reactor Vessel Material Surveillance Specimen Capsule (Specimen Holder 117C4936G010) was withdrawn from LaSalle Unit 1 on March 25, 1994. <

In your review of this report the following points should be noted:

1. The LaSalle Unit 1 300 degree azimuth location surveillance capsule was irradiated to 0.897E+17 n/cm2 after 6.5 EFPY.

2. All measured 30 ft-lb Charpy energy transition temperature shifts are considered acceptable in accordance with NRC Regulatory Guide 1.99, Revision 2.

3. The measured upper shelf energy decreases for the surveillance capsule materials are less than Regulatory Guide 1.99, Revision 2 predictions, which is acceptable.

The materials exhibit adequate upper shelf energy for continued safe plant operation, and are projected to maintain an upper shelf energy greater than 50 ft-lb through 32 EFPY in accordance with 10 CFR 50 Appendix G.

4. The current 16 EFPY and 32 EFPY Technical Specification heatup and cooldown curves (Technical Specification Figures 3.4.6.1-1 and 3.4.6.1-la) are conservative and are not required to be updated at the present time.

To the best of my knowledge and belief, the statements contained here are true and correct. In some respect these statements are not based on my personal knowledge, but from obtained information furnished by other Commonwealth Edison employees, contractor employees, and consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.

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Please direct any questions you may have concerning this matter to this office. i Very truly yours, ,

i Ga Bw G. Benes Nuclear Licensing Administrator )

Attachment:

GE-NE-523-A166-1294, DRF 137-0010-7, LaSalle Unit 1 RPV Surveillance Materials Testina and Analysis, March 1995.

cc: J. B. Martin, Regional Administrator - RIII P. G. Brochman, Senior Resident Inspector - LSCS W. D. Reckley, Project Manager, NRR Office of Nuclear Facility Safety - IDNS

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